Text

Rev 7 to CH-ODCM-0001, ODCM, Incorporating TS Amend 171 for Section 3.1 Update/Reflect Changing Environ
	ML20108A716
Person / Time
Site:	Fort Calhoun
Issue date:	12/19/1995
From:	Shipman J; OMAHA PUBLIC POWER DISTRICT
To:	;
Shared Package
ML20108A698	List: LIC-96-0022, Forwards Annual Rept for Jan-Dec 1995 & Revs 6 & 7 to CH-ODCM-0001, Odcm; ML20108A707; ML20108A712; ML20108A716;
References
	CH-ODCM-0001, CH-ODCM-1, NUDOCS 9605020389
	Download: ML20108A716 (124)
	v • d • e

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

l I

! \

Fort Calhoun Station Unit No. 1 I

j 4 i CH-ODCM-0001 CHEMISTRY PROCEDURE i

l

Title:

OFF-SITE DOSE CALCULATION MANUAL.(ODCM)

I 1

+

FC-68 Number: 44594 ;

1

, CT '

s ,/

s Reason for Change: To incorporate Tech Spec I d Amendment #171 for Section 3.1 Table 3-3, Items 3a/b and Sa/b. To a

update / reflect the changing i i

environmental and demographic monitoring zone and to remove redundant verbiage.

Contact Person: James Shipman Documentable Error (a): Page 39 j

1, i

i I(

j

) 9605020389 960430 DR ADOCK05000g85 l

ISSUED: 12-19-95 4:00 pm R7

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 1 OF 123 8

PART I ADMINISTRATIVE SECTION l

i l

l 9

R7

FORT CALHOUN STATION CHEMISTRY PROCEDURE CH-ODCM-0001 PAGE 2 OF 123 TABLE OF C03l TENTS

1.0 INTRODUCTION

2.0 ADMINISTRATIVE .. . . . . . . . . . . . . . . . . . . . . .

9 I 2.1 Resnonsibilities 10 2.2 c' hance Mechanism . . . . . . . . . . . . . . . . . . . . 10 3.0 . . . . . . . . . . . . . . . . . . . . 10 METEOROLOGICAL DATA 4.0 DEFINITIONS . . . . . . . . . . . . . . . . . . 11

5.0 REFERENCES

. . . . . . ... . . . . . . . . . . . . . . 12

. . . . . . . . . . . . . . . . . . . . . . . 13 l

I l

l l

4 I

l O

R7

i FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 3 OF 123 PART II l 1.O RADIOACTIVE EFFLUENTS RELEASE LIMITS . . . . . . . . . . 15 l 1.1 Licuid Effluents . . . . . . . . . . . . . . . . . . . . 15 1.2 Airborne Effluents . . . . . . . . . . . . . . . . . . . 16 2.0 RADIOACTIVE EFFLUENT RELEASE REOUIREMENTS . . . . . . . 18 l 2.1 Licuid Effluent Releases . . . . . . . . . . . . . . . . 18 1 2.2 Airborne Effluent Releases . . . . . . . . . . . . . . . 22 3.0 RADIOLOGICAT EFFLUENT SAMPLING AND ANALYSIS REOUIREMENTS . . . . . . . . . . . . . . . . . . . . . . 29 3.1 Licuid Effluents . . . . . . . . . . . . . . . . . . . . 29 3.2 Airborne Effluents . . . . . . . . . . . . . . . . . . . 30 3.3 Lower Limit of Detection (T,TD) . . . . . . . . . . . . . 30 4.0 RADIOACTIVE EFFLUENT REPORTING REOUIREMENTS~ . . . . . . 31 ;

4.1 Annual Radioactive Effluent Release Renort . . . . . . . 31 l 4.2 Annual Radioloaical Environmental Ooeratina ReDort . . . 32 4.3 Non-Routine Reoort . . . . . . . . . . . . . . . . . . . 33 4.4 EPA 40 CFR 190 Reoortina Reauirements . . . . . . . . . 34 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING REOUIREMENTS . . . 35 O

O R7

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 4 OF 123 LIST OF TABLES a

PART II

1 Radioactive Liquid Effluent Sampling and Analysis . . . 37 I

2 Radioactive Airborne Effluent Waste Sampling

and Analysis . l J . . . . . . . . . . . . . . . . . . . . . 38 )

3 Radiation and Environmental Monitors Operability Requirements .

. . . . . . . . . . . . . . . . . . . . . 41 l

4 Radiological Environmental Monitoring Program l

i . . . . . 42 I

5 Radiological Environmental Sampling Locations and Media

44 6

i Detection Capabilities for Environmental Sample Analysis 4

(LLD)

! . . . . . . . . . . . . . . . . . . . . . . . . . 47 i i 7 Reporting Levels for Radioactivity Concentrations in I Environmental Samples . . . . . . . . . . . . . . . . . 48 1

j LIST OF FIGURES

(% PART II

, d 1 Environmental Radiological Sampling o o ints...............

46 d

n i

i I

s i %)

R7

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 5 OF 123 PART III 1.0 EFFLUENT MONITOR SETPOINTS . . . . . . . . . . . . . . . 50 1.1 Licuid Effluents . . . . . . . . . . . . . . . . . . . . 50 1.2 Licuid Effluent Radiation Monitors . . . . . . . . . . . 51 1.3 Airborne Effluents . . . . . . . . . . . . . . . . . . . 55 1.4 Airborne Effluent Radiation Monitors . . . . . . . . . . 56 1.5 Simultaneous Release Pathways . . . . . . . . . . . . . 62 2.0 RADIOACTIVE WASTE TREATMENT SYSTEM . . . . . . . . . . . 68 2.1 Licuid Radwaste Treatment System . . . . . . . . . . . . 68 2.2 Airborne Radwaste Treatment System . . . . . . . . . . . 69 i

l l

O O

R7

1 FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 6 OF 123 LIST OF TABLES PART III 1 Proportionally Constants for Simultaneous Airborne Releases. . . . . . . . . . . . . . . . . . . . . . . . 67 LIST OF FIGURES PART III 1 Exclusion and Site Boundary Map . . . . . . . . . . . . 70 2 Liquid Radioactive Discharge Pathways . . . . . . . . . 71 3 Liquid Radioactive Waste Disposal System . . . . . . . . 72 4 Airborne Effluent Discharge Pathways . . . . . . . . . . 73 5 Airborne Radioactive Waste Disposal System . . . . . . . 74 O .

R7

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 7 OF 123 PRT H 1.0 EFFLUENT CONCENTRATIONS . .- . . . . . . . . . . . . . . 76 1.1 Licuid Effluent Concentrations . . . . . . . . . . . . . 76 1.2 Airborne Effluent Concentrations . . . . . . . . . . . . 77 2.0 RADIOACTIVE EFFLUENT DOSE CALCULATIONS . . . . . . . . . 78 2.1 Licuid Effluent Dose Calculations . . . . . . . . . . . 78 2.2 Airborne Effluent Dose Calculations . . . . . . . . . . 82 0

l O

R7 l i

l FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 8 OF 123 I

(} LIST OF TABLES PART IV 1 Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases . . . . . . . . . . . . . . . . . . 99 2 Bioaccumulation Factors . . . . . . . . . . . . . . . 100 3 Controlling Locations, Pathways, and Atmospheric ,

Dispersion for Dose Calculations . . . . . . . . . . . 101 1 4 Stable Element Transfer Data . . . . . . . . . . . . . 102 5 Recommended Values for U., to be Used for the Mey4 mum Exposed Individual in Lieu of Site Specific Data . . . 103 6 Animal Consumption Rates . . . . . . . . . . . . . . . . 103 l 7 External Dose Factors for Standing on Contaminated Ground 104 5 Inhalation Dose Factor for Adult . . . . . . . . . . . 106 9 Inhalation Dose Factor for Teenage . . . . . . . . . . . 108 10 Inhalation Dose Factor for Child . . . . . . . . . . 110

) 11 Inhalation Dose Factor for Infant . . . . . . . . . . 112 12 Ingestion Dose Factor for Adult . . . . . . . . . . . 114 13 Ingestion Dose Factor for Teenage . . . . . . . . . . 116 1

14 Ingestion Dose Factor for Child . . . . . . . . . . . 118 15 Ingestion Dose Factor for Infant . . . . . . . . . . . 120 16 Recommended Values for Other Parameters . . . . . . . 122 v .

R7

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 9 OF 123 1.O INTRODUCTION The OFFSITE DOSE CALCULATION MANUAL (ODCM) is the controlling l document for the Fort Calhoun Station's (FCS) Radiological Effluent and Environmental Monitoring programs. The programs are necessary to ensure the requirements set forth in 10 CFR 20, 10 CFR 50.34a, 10 CFR 50.36a, and 10 CFR 50, Appendix I. The document is subdivided into four sections as outlined below:

Part I, Introduction - consists of information necessary for the effective use of the ODCM. ,

Part II, Radiolugical Effluent Controls - consists of 5 separate sections includdug: '

Section 1 Radiological Effluent Release' Limits Section 2 Radiological Effluent Release Requirements Section 3 Radiological Effluent Sampling and Analysis Requirements Section 4 Radiological Effluent Reporting Requirements Section 5 Radiological Environmental Monitoring Requirements Together these sections provide the controls used to permit O radioactive material releases from the Fort Calhoun Station.

Part III, Radiological Effluent Radiation Monitor Calculation -

provides radiation monitor setpcint calculations for the liquid and airborne release pathways.

Part IV, Radiological Effluent Monitoring Calculations - provides the methodology necessary to calculate doses to individuals as a result of radioactive airborne and liquid releases from Fort Calhoun.

The ODCM has been prepared in accordance with the guidance of Nuclear Regulatory Commissions Reg. Guide 1.109, Rev. 1.

The Radiological Effluest Controls Program consists of the following sections in the Radiological Effluent Controls:

A. Radiological Effluent Release Limits - All Sections B. Radiological Effluent Release Requirements - All Sections C. Radiological Effluent Sampling and Analysis Requirements - All Sections D. Radiological Effluent Reporting Requirements - Sections 4.1 and 4.4 ,

R7

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE 1

PAGE 10 OF 123 j 2.O ADMINISTRATIVE Id The Radiological Environmental Monitoring Program consists of the following sections in the Radiological Effluent Controls:

A. Radiological Effluent Reporting Requirements - Sections 4.2

, and 4.3 e

! B. Radiological Environmental Monitoring Requirements - All i Sections

, 2.1 Resnonsibilities 2.1.1 Nuclear Operation Divi %Qn Chemistry Department is responsible for the ky!>.menta. tion end raaintenance of

{ the ODCM.

j 2.1.2 Nuclear Operation Division nparation Department is responsible for the compliance wi.th the ODCM in the operation of Fort Calhoun Station.

t 1

2.2 N=noe Mechanism i

' The ODCM is the controlling document for all radioactive effluent releases. It is defined as a procedure under the ,

guidance of Technical Specification 5.8. It will be revised {

and reviewed by the Plant Review Constittee J.nd approved by the I Plant Manager in accordance with Technical Specification 5.17.

} All changes to the ODCM will be forwarded to the Nuclear l Regulatory Commission during the next reporting period for the i

Annual Report in accordance with the requirements of Technical l Specification 5.17.

i I

)

1 a

4 lO .

l R7 f

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 11 OF 123 3.0 METEOROLOGICAL DATA The Annual Average x/Q is utilized to determine the concentrations of radionuclides at the unrestricted area boundary. This dispersion factor coincides with the highest calculated annual average value for the Fort Calhoun Station. It is based on 3 years of Onsite Meteorological data and the MESODIF II plume trajectory model. This model conforms with the Nuclear Regulatory Commissions Regulatory Guide 1.111. The model employs the sector averaged equations that are utilized for long-term releases. This type of release (long term) is not dependent solely on atmospheric conditions for complying with 10 CFR 20 concentration limits at the unrestricted area boundary.

Real time meteorological data will be utilized in the preparation of the Annual Report. This data is used to calculate the joint frequency table and the dispersion coefficients and deposition factors in all 16 sectors. These are used in the calculation of doses to individuals in unrestricted areas as a result of the operation of Fort Calhoun Station. The models used, GASPAR and LADTAP, conform with the Nuclear Regulatory Comrrissions Reg.

Guide 1.109 and 1.21 for the reporting of doses due to routine radioactive effluent releases.

O O

R7

1 !

1 FORT CALHOUN STATION CH-ODCM-0001 l CHEMISTRY PROCEDURE PAGE 12 OF 123

{ 4.0 DEFINITIONS

! v Air Effluent Concentration (AEC)

' Radionuclide limits listed in 10 CFR 20, Appendix B, Table 2, Column 1. 1 ghannel Check j

A qualitative determination of. acceptable operability by observation j

of channel behavior during normal plant operation. This

determination shall, where feasible, include comparison of the j channel with other independent channels measuring the same variable.

l rhannel Punction Test 1

Injection of a simulated signal into the channel to verify that it j is operable, including any alarm and/or trip initiating action. 3 j Ooerable - Onera*oility i

i I

A system, subayatem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified

] function (s). Implicit in this definition shall be the assumption j that all necessary attendant instrumentation, controls, normal and emergency electrical power sources, cooling or seal water,

p lubrication, or other auxiliary equipment that are required for the

}V i

i system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related support function (s) .

Purce-Puraina A means for the removal and replacement of gases within the containment building.

Source Check verification to a radioactive source, of channel response when the channel sensor is exposed l

i Ventina i i e

l A means for the reduction of pressure greater than atmospheric j

within the containment structure. I

~

! Unrestricted Area i

' Means licensee.

an area, access to which is neither limited or controlled by i 4

Water Effluent Concentration (WEC)

Radionuclide limits listed in 10 CFR 20, Appendix B, Table 2, Column 2. '

R7 4

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 13 OF 123 5.O REFERENCES / COMMITMENT DOCUMENTS Regulatory Guide 1.109, Rev.1 - Calculation of Annual Dose to man from Routine Releases of Reactor Effluents for the purpose of evaluation compliance with 10 CFR 50, Appendix I Regulatory Guide 1.J11, Rev. 1 -

Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors.

Regulatory Guide 1.113, Rev. 1 - Estimating Aquatic Dispersion of Effluents from Accidental and Routine Releases for the purpose of Implementing Appendix I.

Nureg-0133 - Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants.

Nureg-0472, Rev. 3- Draft Radiological Effluent Technical Specifications for PWRs.

Regulatory Guide 1.21, Rev. 1 - Measuring, Evaluating, and Reporting Radioactivity is solid wastes and Releases of Radioactivity Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants.

Code of Federal Regulations, Title 10, Part 20 Code of Federal Regulations, Title 10, Part 50 Fort Calhoun Revised Environmental Report (Unit No. 1) -1972 Fort Calhoun Technical Specifications (Uni t No-. 1)

Updated Safety Analysis Report Commitment Documents:

IMPLEMENTING COMMITMENT SOURCE STEP .UUMBER (CID) DOCUMENT Part II, 2.2.3.1 C.2 920102/01 FC-0133-92 R7 O

4 d

a FORT CALHOUN STATION CH-ODCM-0001 .

CHEMISTRY PROCEDURE '

PAGE 14 OF 123 1

s i

i I

1 i

1

)

l i

1 1

PART II RADIOLOGICAL EFFLUENT CONTROLS !

~

G R7

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 15 OF 123 1.O RADIOACTIVE EFFLUENTS RELEASE LIMITS The limits and conditions for the controlled release of radioactive material in liquid and airborne effluents are to ensure that these releases result in concentrations that are within the limits specified in Technical Specifications and to ensure that releases of radioactive material to the environment be as low as reasonably achievable in conformance with 10 CFR 50.34a and 50.36a. To meet these criteria, the following requirements must be met for all radioactive liquid and airborne effluents from FCS:

1.1 Licuid Effluents ,

1.1.1 The release rate of radioactive material in liquid effluents shall be controlled such that the instantaneous concentrations for radionuclides, other ,

than dissolved or entrained noble gases, do not exceed '

the values specified in 10 CFR 20 for liquid effluents at site discharge. To support plant operations, Supervisar Radiochemistry may increase this limit up to the limit apecified in Technical Specifications y 5.16.1.b. For dissolved or entrained noble gases, the concentration shall be limited to 2.0 E-04 pCi/ml, total activity.

Technical Specification 5.16.1.b establishes the administrative control limit on concentration of I radioactive material, other than dissolved or entrained l noble gases, released in liquid effluents to ,

unrestricted areas conforming to ten times i 10 CFR 20.1001-20.2401, Appendix B, Table 2, Column 2.

For dissolved or entrained noble gases, the .

concentration shall be limited to 2.0 E-04 pCi/ml total activity.

When the concentration of radioactive material released at site discharge exceeds the above limits, appropriate corrective actions shall be taken immediately to restore concentrations within the above limits.

1.1.2 Annual ?esign Objectives 1.1.2.1 The dose or dose commitment to an individual in unrestricted areas from radioactive materials in liquid effluents during any calendar year shall not exceed 1 millirems to the total body.

1.1.2.2 The dose or dose connitment to an individual in unrestricted areas fran radioactive materials in liquid effluents during any calendar year shall not exceed 12 millirems to any orcan.

O R7

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 16 OF 123 1.0 RADIOACTIVE EFFLUENTS PRT.WIL9E LTMITS (Continued) i O 1.1.2.3 The radiation dose contributions from radioactive materials in liquid effluents released ac site discharge shall be determined, in accordance with Part IV, Section 2.1, on a guarterly basis. If the dose contribution, due t.a the cumulative release' of liquid offluents averaged over a calendar quarter, exceeds one-half of the annual design objectives, the following course of actions shall be taken: i A. Make an investigation to identify the causes I for such releases. l B. Define and initiate a program of action to l reduce such releases to the design levels.

C. Submit a special report, pursuant to Technical Specification 5.16, within 30 days from the end of the quarter during which the l

release (s) occurred, identifying the causes and describing the proposed program of action to reduce such releases to the design levels.

1.2 Airborne Effluents 1.2.1 The release rate of radioactive material in airborne effluents shall be controlled such that the instantaneous concentrations for these radionuclides do .

not exceed the values specified in 10 CFR 20 for I airborne effluents at the unrestricted area boundary.

To support plant operations, Supervisor Radiochemistry may increase this limit up to the limits specified in Technical Specifications 5.16.1.g.

Technical Specification 5.16.1.g. establishes the administrative control limit on the concentration resulting from radioactive material, other than noble gases, released in gaseous effluents to unrestricted areas conforming to ten times 10 CFR 20.1001-20.2401, Appendix B, Table 2, Column 1. For noble gases, the concentration shall be limited to five times 10 CFR 20.1001-20.2401, Appendix B, Table 2, Column 1.

When the concentration of radioactive material released to unrestricted areas exceeds the above limits, appropriate corrective actions shall be taken immediately to restore concentrations within the above limits.

O -

R7

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 17 OF 123 1.0 RADIOACTIVE EFFLUENTS RELEASE LIMITS (Continued) 1.2.2 Annual Design Objectives 1.2.2.1 The gamma air dose in unrestricted areas due to the release of noble gares s in airborne effluents shall not exceed 10 millirads during any calendar year; 1.2.2.2 The beta air dose in unrestricted areas due to the release of noble gases in airborne effluents shall not exceed 20 millirads during ,

any calendar year; and 1.2.2.3 The dose to an individual or dose commitment to any organ of an individual in unrestricted l areas due to the release of I-131, Tritium, and l radioactive materials in particulate form with half-lives greater than eight days (excluding l

noble gases) in airborne effluents shall not l exceed is millira== from all exposure pathways during any calendar year.

1.2.2.4 The radiation dose contributions from radioactive materials in airborne effluents shall be determined, in accordance with the Part IV, section 2.2, on a quarterly basis. If the dose contribution, due to the cumulative release of airborne effluents averaged over a calendar quarter exceeds one-half of the annual i design objectives, the following course of actions shall be taken:

A. Mdke an investigation to identify the cause for such release rates.

B. Define and initiate a program of action to reduce such releases to design levels.

C. Submit a special report, pursuant to Technical Specification 5.16, within 30 days from the end of the quarter during which the release (s) occurred, identifying the causes and describing the proposed program of action to reduce dose contributions.

1.3 The dose to any real individual from uranium fuel cycle sources shall be limited to s 25 mrem to the total body or any organ ( except the thyroid, which shall be limited to s 75 neem ) during each calendar year.

~

R7

i.

FORT CALHOUN STATION CH-ODCM-0001

! CHEMISTRY PROCEDURE. L i PAGE la OF 123 2.0 RADIOACTIVE EFFLUENT nurRASE REOUIREMENTS The requirements for the release of radioactive liquid and airborne i

effluents from FCS stated in this Section are to ensure 1. hat the limits of Section 1 will be met, as well as to allow for operational flexibility. When any of the requirements for release of 1

radioactive effluents cannot be complied with, the release shall not be permitted to occur or it shall be immediately terminated, if it

{ is in progress.

4 l 2.1 Liauid Effluent Releases i

j The equipment or subsystem (s) of the liquid radwaste treatment

system as identified in the Part III, section 2.1, shall be i operable. If the radioactive liquid effluents were discharged j without treatment by one or more of the pieces of equipment or

subsystem (s) identified in that section and it is confirmed a that one-half of the annual dose objective will be exceeded l during the calendar quarter, a special report, pursuant to

Technical Specification 5.16, shall be prepared and submitted j to the Nuclear Regulatory Commission within 30 days of the end

of the quarter during which the equipment or subsystem (s) were

inoperable. This report shall include the following

information

1 j A. Identification of equipment or subsystem (s) not operable i and reasons for inoperability.

i f B. Action (s) taken to restore the inoperable equipment to j operable status.

1 l C. Summary description of action (s) taken to prevent a j recurrence.

i k

1 i

O .

R7

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 19 OF 123 2.0 RADIOACTIVE EFFLUENT RELEASE REOUIREMENTS (Continued) 2.1.1 Monitor and Hotel Waste Tanks l

i During release of radioactive liquid effluents, the l following conditions shall be met: '

l 2.1.1.1 There shall be sufficient dilution flow so !

that, at site discharge:

n l C /weci s1 g

1

)

where:

Ci= concentration of the 1"'

radionuclide in the liquid effluent at site discharge.

wect = 10 CFR 20, Appendix B, Table 2, Column 2 limits.

2.1.1.2 The overboard header effluent radiation monitor shall be set in accordance with Part III to alarm and automatically close the discharge valve prior to exceeding 10 CFR 20 limits at site discharge.

NOTE: During the perforrance of daily source checks the ;

effluent radiation monitor is unable to respond, hence I is considered inoperable. Effluent releases may continue uninterrupted during the performance of source checks provided the operator is stationed at the monitor during the check. Effluent releases must be terminated and the actions of the ODCM carried out if the monitor fails its source check, 2.1.1.3 The liquid effluenc radioactivity shall be continuously monitored during the release. If the effluent radiation monitor is inoperable, effluent releases may continue provided that:

(prior to initiating a release)

A. At least two independent samples are analyzed in accordance with applicable chemistry procedures.

B. At least two qualified individuals independently verify the release rate calculations.

R7

_ _ _ _ _ _ _ . . . _ . . _ . . . ~ . . . . . . _ _ _ _ ._. . . _ _ ___

FORT CALHOUN STATION CH-ODOE-0001 CHEMISTRY PROCEDURE PAGE 20 OF 123 2.0 RADIOACTIVE EFFLUENT DRLun_SE DunUIREMENTS (Continued)

O 2.1.1.4 The liquid effluent radioactivity shall be continuously recorded during the release. If the process radiation monitor chart recorder is inoperable and the process radiation monitor is operable then affluent releases may continue provided,that the radioactivity level is recorded manually at least once per four hours during actual release.

2.1.1.5 The liquid effluent flow rate shall be continuously monitored and recorded during the release. If the flow rate recorder is inoperable, effluent releases may continue provided the flow rate is determined at least once per four hours during actual release.

2.1.2 Steam Generator During the release of steam generator blowdown to the discharge tunnel, the following conditions shall be met:

2.1.2.1 There shall be sufficient dilution flow so that, at site discharge:

n C1 /wec, s1 O '

where:

,Ci = concentration of the i*

radionuclide in the liquid effluent at site discharge.

wect = 10 CFR 20, Appendix B, Table 2, l Column 2 limit. !

, 2.1.2.2 The steam generator blowdown radiation monitors shall be set in accordance with Part III to i

alarm and automatically close the blowdown isolation valves prior to exceeding 10 CFR 20 l limits at site discharge.

R7

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 21 OF 123 2.0 RADIOACTIVE EFFLUENT RELEASE REOUTumENTS (Continued)

NOTE: During the performance of daily source checks the effluent radiation monitor is unable to respond, hence is considered inoperable. Effluent releases may continue uninterrupted during the performance of source checks provided the operator is stationed at the monitor during the check. Effluent releases must be terminated and the actions of the ODCM carried out if the monitor fails its source check.

1 2.1.2.3 The radioactivity for each blowdown line shall be continuously monitored by the blowdown ,

radiation monitors and recorded. 1 I

A. If one.of the two radiation monitors is :

inoperable, the activity for both blowdown lines shall be monitored by the operable )

radiation monitor within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of the !

declaration, by Shift Supervisor, of inoperability.

1 B. If both radiation monitors are inoperable, steam generator liquid releases may continue l provided grab samples'are analyzed for l principal gamma emitters at a sensitivity of 5.0E-07 pCi/ml and recorded at least daily when the specific activity of Steam Generator Blowdown is less than or equal to 0.01 pCi/ gram dose equivalent I-131 and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the specific activity of the secondary coolant is greater than 0.01 pCi/ gram dose equivalent I-131.

2.1.2.4 The radioactivity for each blowdown line shall be continuously recorded. If the process radiation monitor chart recorder is not operational, Steam Generator releases may continue provided that the radioactivity level is recorded manually at least once per four hours during actual release.

- O R7

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

FORT CALHOUN STATION E-ODCM-0001 CHEMISTRY PROCEDURE PAGE 22 OF 123 2.0 RADIOACTIVE EFFLUENT DWT.WASE REOUIREMENTS (Continued) 2.2 Airborne Effluent Relmanes The equipment or subsystem (s) of the gaseous radwaste treatment system as identified in Part III, Section 2.2, shall be operable.

If the radioactive airborne effluents were discharged without treatment by one or more of the equipment or subsystems (s) identified in that section and it is confirmed that one-half of the annual dose objective will be exceeded during the calendar quarter, a special report, pursuant to Technical Specification 5.16, shall be prepared and submitted to the Nuclear Regulatory Commission within 30 days of the end of the quarter during which the equipment or subsystem (s) were inoperable. This report shall include the following information:

A. Identification of equipment or subsystem (s) not operable and reason for inoperability. j i

B. Action (s) taken to restore the inoperable equipment to '

operable status.

C. Summary description of action (s) tr. ken to prevent a recurrence.

2.2.1 Auxiliary Building uvhaust Stack NOTE: During the performance of daily source checks the effluent radiation monitor is unable to respond, hence is considered inoperable. Effluent releases may continue uninterrupted during the performance of source checks provided the operator is stationed at the monitor during the check. Effluent releases must be terminated and the actions of the ODCM carried out if the monitor fails its source check.

2.2.1.1 During the ventilation of' airborne effluents from the Auxiliary Building through the Auxiliary Building Exhaust Stack, the following conditions shall be met:

A. The Auxiliary Building Exhaust Stack Noble Gas Monitor, Iodine and Particulate Sampler, shall be operational, OR:

12/95-O -

R7

FORT CALHOUN STATION CH-ODQ4-0001 CHEMISTRY PROCEDURE PAGE 23 OF 123 l

2.0 RADIOACTIVE EFFLUENT RETRASE REOUIREMENTS (Continued) l 2.2.1.1A 1) If the Auxiliary Building Exhaust Stack i Noble Gas Monitor is inoperable, I releases from the containment pressure 12/95 relief line and the containment purge line are to be secured in the most expeditious manner. Ventilation of the auxiliary building via the Auxiliary Building Exhaust Stack may continue l provided grab samples are taken once per 12/95

8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months (+25% == vim"m extension) and analyzed for principal gamma emitters (See Table 2) .

4

, 2) If the Auxiliary Building Exhaust Stack

, Iodine and Particulate Sampler is l ,

inoperable, ventilation of the auxiliary 12/95 I building and releases from the gaseous l waste discharge header, containment 4

pressure relief line or the containment purge line may continue through the Auxiliary Building Exhaust Stack provided sample collection using ,

auxiliary sample collection equipment is initiated within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of the declaration of inoperability, by the l Shift Supervisor, in accordance with l Table 2. 5l B. The Auxiliary Building Exhaust Stack Noble Gas Radiation Monitor shall be set in i accordance with Part III to alarm and ;

automatically terminate the release prior to )

exceeding 10 CFR 20 limits at the 1 4

unrestricted area boundary (see Part III, Figure 1).

C. At least one Auxiliary Building Exhaust Fan l shall be in operation.

l D. 12/95 The Auxiliary Building Exhaust Stack airborne radioactivity shall be monitored and recorded during the release. If the I process radiation monitor chart recorder is inoperable and the noble gas monitor is operable then releases from the Auxiliary Building may continue provided that the radioactivity level is recorded manually at least once per four hours during the actual release.

O R7

i FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 24 OF 123 2.O RADIOACTIVE EFFLUENT RET MSE REOUIREMENTS (Continued)

C4 2.2.1.1 E. The Auxiliary Building Exhaust Stack flowrate shall be monitored and recorded during ventilation of the Auxiliary Building. If the flowrate monitor or recorder is inoperable, ventilation may .

continue provided the flowrate is determined and recorded manually at least once per four hours..

NOTE: During the performance of daily source checks the effluent radiation monitor is unable to respond, hence is considered inoperable. Effluent releases may continue uninterrupted during the performance of source ,

checks provided the operator is stationed at the monitor during the check.

Effluent releases must be terminated ;

and fails its source check.ODCM carried out if the monitor the actions of the '

2.2.1.2 During release of airborne effluents from containment pressure relief line to the Auxiliary Building Exhaust Stack, the following conditions shall be met:

A.

The conditions set forth in Section 2.2.1.1 shall be met.

B. The Containment Pressure Relief Line Flow Rate Annubar D/P shall be monitored and recorded manually at least once per. four (4) hours during the release.

12/95l O .

R7

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 25 OF 123 2.0 RADIOACTIVE EFFLUENT RELEASE REOUIREMENTS (Continued) 2.2.1.3 During release of gaseous radioactive effluent u/95, from Containment Penetration M72 or M74 (Integrated Leak Rate Test Depressurization Vent Path) to the Auxiliary Building Stack the following conditions shall be met:

A. The conditions set forth in Section 2.2.1.1 12/95 shall be met.

B. Automatic release termination capability is not required provided manual isolation can be accomplished in accordance with the requirements of SS-ST-ILRT-0001.

NOTE: During the performance of daily source checks the effluent radiation monitor is unable to respond, hence is considered inoperable. Effluent releases may continue uninterrupted during the performance of source checks provided the operator is stationed at the monitor during the check. Effluent releases must be tenninated and the actions of the ODCM carried out if the monitor fails its source check.

2.2.1.4 During the release of airborne effluents from the containment purge line:

h A. The conditions set forth in Section 2.2.1.1 shall be met.

B. A noble gas monitor shall monitor the containment building atmosphere.

C. The containment purgeline flow rate shall be monitored and automatically recorded during the release. If the flow rate recorder is inoperable, releases from the containment may continue provided the flow rate is recorded manually at least once per four hours during actual release.

I 1

l (Il;

. 1 R7

l FORT CALHOUN STATION CH-0DCM-0001 !

CHEMISTRY PROCEDURE PAGE 26 OF 123 2.0 RADIOACTIVE EFFLUENT RRT un_SE REQUTDWhGENTS (Continued) .

1 -

NOTE: During the performance of daily source checks the effluent radiation monitor is unable to respond, hence is considered inoperable. Effluent releases may continue uninterrupted during the performance of source checks provided the operator is stationed at the monitor during the check. Effluent releases must be terminated and the actions of the ODCM carried out if the monitor fails its source check.

2.2.1.5 During the release of airborne effluents from the gaseous waste discharge header:

A. The conditions set forth in Section 2.2.1.1 shall be met.

B. If the Auxiliary Building Exhaust Stack 12/95 noble gas monitor is inoperable, effluent releases may continue provided that (prior to release):

1) At least two independent samples are analyzed in accordance with the applicable chemistry procedure.

2) At least two qualified individuals p independently verify the release rate calculations.

C. The waste gas discharge header flow rate I 12/95 shall be monitored and automatically recorded during releases. If the flow rate monitor or recorder is inoperable, releases may continue provided the flow rate is determined and recorded manually at least once per four hours during actual release.

~

l l

O . !

R7

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 27 OF 123 2.0 RADIOACTIVE EFFLUENT RELEASE REOUIREMENTS (Continued) 2.2.2 Condenser Offaas NOTE: During the performance of daily source checks the O

effluent radiation monitor is unable to respond, hence is considered inoperable. Effluent releases may continue uninterrupted during the performance of source checks provided the operator is stationed at the monitor during the check. Effluent releases nnst be terminated and the actions of the ODCM carried out if the monitor fails its source check.

2.2.2.1 During power operation, the condenser air ejector discharge shall be monitored for 3ross radioactivity. If this monitor is inoperable, grab samples shall be taken once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

(+25% maximum extension) and analyzed for principal gamma emitters. (See Table 2) 2.2.3 Laboratory and Radioactive Waste Processina Building Stack NOTE: During the performance of daily source checks the effluent radiation monitor is unable to respond, hence is considered inoperable. Effluent releases may continue uninterrupted during the performance of source checks provided the operator is stationed at the monitor during the check. Effluent releases must be terminated and the actions of the ODCM carried out if the monitor fails its source check.

2.2.3.1 During.the release of airborne effluents from the Laboratory and Radioactive Waste Processing Building (LRWPB) the following conditions shall be met:

A. The LRWPB Noble Gas Monitor, Iodine and l

Particulate Sampler shall be operational, 12/95 OR:

O R7

. PORT CALHOUN STATION i CH-ODCN-0001 CHEMISTRY PROCEDURE PAGE 28 OF 123 j 2.0 RADIOACTIVE EPPLUkdT DWT.WRSE DuoDTDuunnus (Continued)

! 2.2.3.1A 1) If the Noble Gas Monitor is t j

' inoperable, ventilation of the LRWPB 12/95.

may continue via the LRWPB stack i

provided grab samples will be taken once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and analyzed for principal gasma emitters.

[2)) .If the Iodine and Particulate Sampler ,

1 is inoperable, ventilation of the LRWPB may continue via the LRWPB Stack provided sample collection 12/95 l using auxiliary sample collection equipment is initiated within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of the declaration of.ino by the Shift Supervisor, in perability, t accordance with Table 2. 12I95I B. The LRWPB noble gas radiation monitor shall l be set in accordance with Part III to alarm at its predetermined setpoints.

C. The LRMPB Stack flow rate shall be monitored 1

and recorded during ventilation of the LRWPB. If the flow rate monitor or recorder is inoperable, ventilation may continue 3.

provided the flow rate is determined and '

recorded manually at least once per four bours.

O .

R7

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 29 OF 123

'3.0 RADIOLOGICAL EFFLUENT SAMPLING AND ANALYSIS REOUIREMENTS The sampling and analysis requirements stated in this Section will provide reasonable assurance that radioactive materials present in the liquid and airborne effluents will be properly identified and accurately quantified. This information will serve as the basis for determining doses to individuals as a result of radioactive effluents from FCS.

Records shall be maintained and reports of the sampling and results of analyses shall be submitted to the Nuclear Regulatory Commission in accordance with Section 4 of these controls. Sampling, analysis and operability testing will typically be documented on Surveillance Tests or on Release Permits or Summaries.

3.1 Licuid Effluents 3.1.1 Radioactive liquid effluent sampling and activity analyses shall be performed in accordance with Table 1.

The results of these analyses shall be used with the calculational methods in Part IV of this manual to assure that the concentration at the point of release is limited to 10 CFR 20 limits for unrestricted areas.

3.1.2 Prior to release of each batch of liquid effluent, the batch shall be mixed, sampled, and analyzed for principal gamma emitters. When operational or other limitations preclude specific gamma radionuclide analysis of each batch:

3.1.2.1 Gross radioactivity measurements shall be made to estimate the quantity and concentrations of radioactive materials released in the batch.

3.1.2.2 A weekly sample composite from proportional aliquots from each batch released during the week shall be analyzed for the principal gamma-emitting radionuclides.

3.1.3 Records shall be maintained of the radioactive concentrations and volume before dilution of each batch of liquid effluent released and of the average dilution flow and length of time over which each discharge occurred. Analytical results shall be submitted to the Commission in accordance with Part II, Section 4.

3.1.4 The radiation monitors for liquid effluents shall have their operability tested in accordance with the requirements in Table 3, Item A.

' 3.1.5 Steam Generator blowdown effluent flowrates shall have their operability tested in accordance with the requirement in Table 3, Item D.

R7

FORT CALHOUN STATION CH-ODCM-0001 I CHEMISTRY PROCEDURE PAGE 30 OF 123 3.O RADIOLOGICAL EFFLUENT SAMPLING AND ANALYSIS REOUTumeglgrg (Continued).

3.2 Airborne Effluents 3.2.1 Radioactive airborne effluent sampling and activity analyses shall be performed in accordance with Table 2. l The results of these analyses shall be used with the calculational methods in Part IV of this manual to assure that the concentration of radioactive materials is limited to 10 CFR 20 limits at the unrestricted area boundary.

3.2.2 The radiation monitors / samplers for airborne effluents shall have their operability tested in accordance with the requirements in Table 3, Item B.

3.2.3 The Auxiliary Building Exhaust and the Laboratory Radioactive Waste Processing' Building Exhaust Stack flowrates shall have their operability tested in accordance with the requirements in Table 3, Item D.

3.3 Lower Limit of Detection (T.T M )

The lower limit of detection (LLD) for liquid and airborne effluent discharges, referenced in Part II, Tables 1 and 2, is defined as the smallest concentration of radioactive material O in a sample that will yield a net count, above system background, that will be detected with-95 percent probability with only 5 percent probability of falsely concluding that a blank observation represents a "real" signal.

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

4.66

sy E

V

D

Y

exp (-AAt)

Where:

J LLD = the lower limit of detection as defined above, in either picocuries or microcuries, per unit mass or volume as a function of the value of D ;

Sb = the standard deviation of the background counting rate or of the counting rate of a blank sample, as appropriate, as counts per minute E = the counting efficiency, as counts per disintegration V = the sample size in units of mass or volume D = 2.22E+06 of disintegrations per minute per microcurie or 2.22 disintegrations per minute per picocurie R7

FORT CALHOUN STATION . CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 31 OF 123 3.0 RADIOLOGICAL EFFLUENT SAMPLING AND ANALYSIS REOUIREMENTS (Continued) 3.3 Y = the fractional radiochemical yield, when applicable l A =

the radioactive decay constant for the particular radionuclide At =

the elapsed time for the plant effluent between the midpoint of sample collection and time of counting Appropriate 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 limit representing the capability of a measurement system and not as a limit for a particular measurement.

LLD verifications will be performed on a periodic basis. This determination is to ensure that the counting system is able to detect levels of radiation at the LLD values for the specific type of analysis required by Tables 1 and 2. They will be performed with a blank (non-radioactive) sample in the same counting geometry as the actual sample.

4.O RADIOACTIVE EFFLUENT REPORTING REOUIREMENTS The reporting requirements for radioactive effluents stated in this Section are to provide assurance that the limits set forth in Section 1 are complied with. These reports will meet the requirements for documentation of radioactive effluents contained in 10 CFR 50.36a; Reg. Guide 1.21, Rev. 1; Reg. Guide 4.8, Table 1; and Reg. Guide 1.109, Rev. 1.

4.1 Annual Radioactive Effluent Release Reoort A report covering the operation of the Fort Calhoun Station during the previous calendar year shall be submitted prior to May 1 of each year per the requirements of Technical Specifications 5.9.4.a. and 10 CFR 50.

The radioactive effluent release report shall include a summary of the quantities of radioactive liquid and airborne effluents and solid waste released from the plant as outlined in Regulatory Guide 1.21, Revision 1.

The radioactive effluent release report shall include a summary of the meteorological conditions concurrent with the release of airborne effluents during each quarter as outlined in Regulatory Guide 1.21, Revision 1.

O R7

.__._m_...- . _ - _ _ . _ _ _ _ . _ _ _ . . _ _ _ _ . _ . _ . _ . _ . _ _ . _ _ _ _ _ _ ._. __

FORT CALHOUN STATION CH-ODCM-0001

CHEMISTRY PROCEDURE i

PAGE 32 OF 123 4.0 RADIOACTIVE EFFLUENT REPORTING REOUIREMENTS (Continued) i 4.1 The radioactive effluent release report shall include an assessment of radiation doses from the radioactive liquid and airborne effluents released from the unit during each calendar quarter as outlined in Regulatory Guide 1.21, Revision 1. The i assessment of radiation doses shall be performed in accordance with calculational methodology of the Regulatory Guide 1.109, Revision 1.

" The radioactive effluent release report shall include any changes to the Process Control Program (PCP) or to the Offsite Dose period.

Calculation Manual (ODCM) made during the reporting Each change shall be identified by markings in the margin of the affected pages clearly indicating the area of the page that was changed and shall indicate the date the change was implemented.

4.2 Annual Radioloaical Environmental Qggrptina Renort The Annual Radiological Environmental Operating Report for the previous one year of operation shall be submitted prior to May 1 of each year. This report contains the data gathered from the radiological environmental monitoring program. The content of the report shall include:

4.2.1 Summarized and tabulated results of the radiological O environmental sampling / analysis activities following the format of Regulatory Guide 4.8, Table 1. In the event that some results are not available, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

4.2.2 Interpretations and statistical evaluation of the results, including an assessment of the observed impacts )

of the plant operation and environment.

4.2.3 The results of participation in a NRC approved Interlaboratory Comparison Program.

4.2.4 The results of land use survey required by Part II, Section 5.4.

4 0 .

R7

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 33 OF 123 4.0 RADIOACTIVE EFFLUENT REPORTING REOUIREMENTS (Continued) 4.2.5 The results of specific activity analysis in which the primary coolant exceeded the limits of Technical Specification 2.1.3. The following information shall be included:

4.2.5.1 Reactor power history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior l to the first sample in which the limit was l exceeded. j 4.2.5.2 Results of the last isotopic analysis for radiciodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radiciodine activity was reduced to less than the limit. Each result should include date and time of sampling and the radiciodine concentrations.

4.2.5.3 Purification system flow history starting ;

48 hourn prior to the first sample in which the limit was exceeded.

4.2.t.4 Graph of the I-131 concentration and one other radiciodine isotope concentration in micro-curies per gram as a function of time for the duration of the specific activity above the steadystate level, AND 4.2.5.5 The time duration when the specific activity of the primary coolant exceeded the radiciodine limit.

4.3 Non-Routine Recort If a confirmed measured radionuclide concentration in an environmental sampling medium averaged over any calendar quarter sampling period exceeds the reporting level referenced in Table 7, and if the radioactivity 17. attributable to plant operation, a written report shall be submitted to the Nuclear Regulatory Commission within 30 days from the end of the quarter.

The report shall include an evaluation of any release conditions, environmental factors, or other aspects necessary to explain the anomalous result.

O R7

FORT CALHOUN STATION CH-ODCM-0001 i CHEMISTRY PROCEDURE PAGE 34 OF 123

$ 4.0 l

RADIOACTIVE EFFLUENT REPORTING REOUIREMENTS (Continued) 4.4 EPA 40 CFR 190 Renortina Reauiromants i

With the calculated dose from the release of radioactive 4

materials in liquid or gaseous effluents-exceeding twice the limits of Part II, Sections 1.1.2, 1.2.2, or 1.3, based on j

' quarterly and annual calculations, prepare and submit a special report to the Commission within 30 days and limit the subsequent releases such that the dose to any real individual 1

from uranium fuel cycle sources is limited to s 25 mrem to the j total body or any organ (except thyroid, which is limited to s 75 mrem) over the calendar year. This special report shall j

include an analysis which demonstrates that radiation exposures to any member of the public from uranium fuel cycle i

sources (including all effluent pathways and direct radiation)

} are less than the 40 CFR 190 standard. Otherwise, obtain a 1

I variance from the Commission to permit releases which exceed the 40 CFR 190 standard. The submittal of the report is to be i

considered a timely request and a variance is granted pending the final action on the variance request from the Cormnission.

j i

i i

j.

i

)

i 4

0 .

R7

h0RT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 35 OF 123 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING REOUIREME/EE The requirements set forth in this Section will provide reasonable assurance that radioactive liquid and airborne effluent releases to the environment in and around Fort Calhoun Station are monitored and that any deviation of radiation levels above background will be j identified. l 5.1 THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) shall be conducted according to Table 4. Analytical results of this l 12/95 program and deviations from the sampling schedule shall be reported to the Nuclear Regulatory Commission in the Annual Radiological Environmental Operating Report (Part II, Section 4.2).

1 5.2 If the level of radioactivity from calculated doses leads to a higher exposure pathway to individuals, this pathway shall be l added to the Radiological Environmental Monitoring Program. 12/95 l 5.3 If the level of radioactivity in an environmental sampling medium exceeds the reporting level specified in Table 7, a Non-routine Report shall be prepared and submitted to the Nuclear Regulatory Commission (Part II, Section 4.3). The detection capabilities of the equipment.used for the analysis of environmental samples must meet the' requirements of Table 6 for Lower Level of Detection (LLD). l 12/95 5.4 A land use survey shall be conducted once per 24 months between the dates of June 1 and October 1. This survey shall identify the location of the nearest milk animal, nearest meat '

animal, nearest vegetable garden, and the nearest residence in each of the 16 cardinal sectors within a distance of five miles. The results of the land use survey shall be submitted to the Nuclear Regulatory Commission in the Annual Radiological Environmental Operating Report (Part II, Section 4.2). The survey shall be conducted under the following conditions:

5.4.1 Within a one-mile radius from the Plant site, l enumeration by door-to-door or equivalent counting l 12/951 techniques.

5.4.2 Within a Five-mile radius, enumeration may be conducted door-to-dcor or by using referenced information from l county agricultural agents or other reliable sources. 1 32,g3 i

O R7

~ ___ . . . . ~ . _ . . . .. . _ __ _ . _ . ___ _ _ . .

d i

FORT CALHOUN STATION l CHEMISTRY PROCEDURE CH-ODCM-0001 s PAGE 36 OF 123 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING REOUIREhDsNTS i

5.4.3 If it is learned from this survey that milk animals are present at a location _which yields a calculated dose 4

i greater than from previously. sampled location (s), the new location (s) shall be added to the monitoring program. The sampling location (s) having the lowest calculated dose may then be dropped from the monitoring

program at the end of the grazing and/or growing season during which the survey was conducted and the new j

location added to the monitoring program. Also, any location (s) from which milk can no longer be obtained l may be dropped and replaced if practicable from the 12/95 monitoring program and the Nuclear Regulatory Commission i

shall be notified in the Annual Radiological q

Environmental Operating Report (Part II, Section 4.2).

5.4.4 Radiological environmental sampling locations and the media that is utilized for analysis are presented in l

Table 5. Details of the emergency TLD locations are i2/95

contained in the Rasiological Emergency Rersipone Plan.

i l 1

5.5 12/95 i Analyses shall be performed on radioactive materials as part of an Interlaboratory Comparison Program that has been j approved by the Nuclear Regulatory Commission. The results of these analyses shall be included in the Annual Radiological j Environmental Operating Report.

4 l 5.6 Deviations from the monitoring program, presented in this section and detailed in Table 4, are permitted if specimens i

j are unobtainable due to mitigating circumstances such as

~

hazardous conditions, seasonal unavailability, malfunction of equipment, or if a person discontinues participation in the program. If the equipment malfunctions, corrective actions

{

will be complete as soon as practicable. If a person no longer supplies samples, a replacement will be made if 12/95 possible. All deviations from the sampling schedule will be i

described in the Annual Radiological Environmental Operating Report,

pursuant to Part II, Section 4.: 2, R7

t;emngAameinen@Moltr CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 37 OF 123 TABLE 1 Radioactive Licuid Effluent Samnline and Analysis Monitor & Hotel waste Tanks Releases O

Lower Limit of Sampling Frequency Type of Detection (LLD)

Activity Analysis (pCi/nd) ll)

Each Batch Principal Gamma Emitters (2) (3) 5.0 E-07 I-131(2) 1.0 E-06 Monthly From Dissolved Noble One Batch Gases (2) (Gamma 1.0 E-05 Enitters)

Monthly Composite (7) H-3 1.0 E-05 Gross a 1.0 E-07 Quarterly Composite (7) Sr-89, Sr-90 5.0 E-08 O

D. Steam Generator Blowdown Lower Limit of Type of Detection (LLD)

Sampling Frequency Activity Analysis (pCi/ml)(1)

Weekly Composite (7) Principal Gamma Emitters (3) 5.0 E-07 I I-131(5) 1.0 E-06 Monthly Dissolved Noble Gases (Gamma 1.L E-05 Emitters)

Monthly Composite (7) H-3 1.0 E-05 Gross a 1.0 E-07 Quarterly Composite (7) Sr-89, Sr-90 5.0 E-08 R7 l

h FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 38 OF 123 TABLE 2 a

Radioactive Airborne Effluent Samnlina and Analvsis A. Gas Decay Tank Releases i

Lower Limit of Type of Detection llLLD)

Sampling Frequency Activity Analysis (pCi/ml)L1)

Prior to each Principal Gamma j release Emitters (4) 1.0 E-04 D. Containment Purge Releases or Containment 4

Pressure Relief Line Releases Lower Limit of Type of Detection (LLD)

Sampling Frequency Activity Analysis (pCi/ml) (1)

Prior to each Principal Gamma release Emitters (4) 1.O E-04 Prior to each release H-3 O _

1.0 E-06

C. Condenser Air Ejector Releases Lower Limit of Type of Detection (LLD)

Sampling Frequency Activity Analysis (pCi/ml)(1)

Monthly (6) Trit.ium (H-3) 1.O E-06 Monthly Principal Gamma Emitters (4) 1.0 E-04 1

4 N

V .

R7

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 39 OF 123 TABLE 2 (Continued)

D. Auxiliary Building Exhaust Stack and Laboratory and Radwaste Building Exhaust Stack Lowet- Limit of l Type of Detection (LLD) l Sampling Frequency Activity Analysis (#Ci/ml) (1) l Weekly (Charcoal Sample) I-131 1.0 E-12 )

Weekly Principal Gamma (Particulates) Emitters (4), I-131 1.0 E-11 and Particulates with half-lives

> eight days.

Weekly (Noble Gases) Principal Gamma 1.0 E-4 la Emitters (4) '

12/95 Monthly Composite Gross a 1.0 E-11 Quarterly composite (Particulates) Sr-89, Sr-90 1.0 E-11 l

O R7

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTR

Y. PROCEDURE

PAGE 40 OF 123 TABLES 1 and 2 (Continued)

O soTass (1) LLD is defined in Part II, Section 3.3.

(2) Gross Radioactivity is defined as the determination of radioactivity levels without regard to specific radionuclide identification and individual isotopic quantification.

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

(4) .The principal gasma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Hn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, Ce-144 for particulate emissions.

(5) A weekly grab sample and analyses program including gamma isotopic identification will be initiated for the turbine building sump effluent when the steam generator blowdown water composite analysis indicates the I-131 concentration is greater than 1.0 E-06 microcurie / milliliter.

1 Required only when steam generator blowdown radioactivity for O(6) tritium (Table 1, Item B) exceeds 3.0 E-03 microcurie / milliliter.

(7) To be representative of the average quantities and concentrations of radioactive materials in liquid effluents, samples should be collected in proportion to the rate of flow of the effluent stream.

Prior to analyses, all samples taken for the composite should be mixed in order for the composite sample to be representative of the average effluent release.

O .

l R7

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

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 41 OF 123 TABLE 3

-9 I i

Radioloolcal Effluent and Enviromental instrtsnentation operebility Test R ecui rement s !

Da; '.y Quarterly Source Check n e' Channel Channel Refueling Prior to A. Li pid Manitors check Func. Test Calibration Release Ril-u;D/054B X(2) x x .

RM-C5) -

X X X i

Daily Quarterly Source Check Channel Channel Refueling Prior to B. Caseous Manitors Check Func. Test Calibration Release RM-043 X X X -

RM-057 X X x . 12/95 RM-062 X X X X RM 052(1) X X X X RM-043 Sanpler Flow Rate X -

X -

RM-062 sattpler Flow Rate X -

X -

RM 052 sancier Flow Rate (1) X -

X -

Monthly Annual Operations Air Flow C. Erwirnwitt. Manitors Check Calibration RM 025 - 039 X X D. Efftv at Flowrates Daily Channel check Refueling Calibration

f. A Generator Blowdown Flowrate X X Auxiliary Building Exhaust $teck X X

,Flowrate Laboratory and Radioactive Waste X X Processing Building Exhaust Stack Flowrate i

NOTES:

(1) Required when RM-052 is sanpling the Auxiliary Building Exhaust Stack. I (2) visual flowcheck daily 9'

R7 l

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 42 OF 123 TABLE 4 Radiolooleal Environmental Monitorino Procram Exposure Pathway and/or Sanple Collection Site (II Types of Analysis (2) Frequency

1. Direct andiation A. Ten TLD indicator stations, Gamma dose Quarterly one control station, total of 11.

B. An inner-ring of 16 stations, Gamma dose during Site Replaced one in each cardinal sector Area and General Emer- Annually in the general area of the pencies only.

unrestricted area boundary and within 2.5 miles. 12/95 C. An outer-ring of 16 stations, Gamma dose during Site Replaced 1 in each cardinal sector Area and General Emer- Annually located outside of the gencies only, inner-ring, but no more dis-tantthgg)approximately 12/95 5 miles

2. Air Manitoring A. Indicator Stations Weekly 1)Filteg}forGross Betal

1. 3 stations in the general area of the unrestricted 2) Charcoat for 1 131 Weekly area boundary

2. City of Blair, NE. 3) Filter for Gamma Quarterly

% !sotopic composite of l

) wkly. f ttes.

/ B. One background statica Same as A. above 12/95

3. Water A. Missouri River at nearest Gamme Isotopic, N-3 Nonthly com-downstream crinking water posite for intake. Gesum isoto-pic Analysis B. Missouri River downstream Quarterly near the mixing zone, composite for H-3 Analysis C. Missouri River upstream of Plant intake (background).

4. Mitk(') 12/95 A. Nearest family cow when Gamme isotopic and 1 131 Semimonthly available or one dairy farm grazing ses-within 5 miles. son (May to October)

8. One dairy farm between 5 miles and 18.75 miles.

(background)

5. Fish A. Four fish samples within Gamma Isotopic Once per vicinity of Plant discharge, season (May l to October) 1 B. One backgromd sample Lip-stream of Plant discharge. 12/95 12/95 R7

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 43 OF 123 TABLE 4 (Continued) ,

Redf otocical Envirorsnental Monitorino Program Fxposure Pathway and/or Sample Collection SiteCl) Types of Analysis (2) Frequency

6. sediment A. One sample from downstream ares Gamma Isotopic Semiannually on the station side of the Missouri River.

B. One sample from testream of Plant Intake. (backgromd)

7. Vegetables or A. One sample in the highest Gessan Isotopic Once per Food ProdJcts (6) exposure pathway. season (May l to October)

8. One sample outside of 5 miles. (background) 12/95 O

Notes:

(1) See Table 6 for required detection limits.

(2) The Lower Limit of Detection (LLD) for analysis is defined in the ODCM in accordance with the wording of NUREG - 0472, Rev. 3, Draf t 7.

(3) When a gross beta comt indicates radioactivity greater than 1E-12 pCf/ml or 1 pCf /m', a game spectral analysis will be performed.

(4) When milk samples are not available, a broad leaf vegetation or pasture grass sanple shall be collected, when available.

(5) Details of the Emergency TLD Stations are contained in Emergency The Radiological Emergency Response Plan (6)#

Sanples should be collected from garden plots 500 f t' or more. Reference Reg. Guide 4.8 " Environmental Technical Specifications for Nuclear Power Plants", Dec. 1975.

R7

)

FORT CAL o,ATION s .

CNEMISTRY PROCEDURE

^ O CH u ..-0001 PAGE 44 0F 123 L TABLE 5 Radiotonical Environmental SamDtIna location 8 and Media Sample Approximate Approximate Approximate Station Cottection Distance From Vegetables Number Direction Air Monitorine Sites Containment (Degrees from Airborne and Food Airborne TLD Water Milk Sediment Fish Products l

(miles) north) Particutete Iodine 1 I

1 Onsite Station i 110-meter weather tower 0.5 293' l X X X X 2 Onsite Station {

adjacent to old plant 0.6 208*

occess road X X X X 3 offsite Station Intersection of Hwy. 75 0.8 145' X X X X and form access road 4 Blair OPPD office 3.0 303* X X X X 5 EOF Sullding, Nor th Omaha Power Stetton 17.5 157' X X X X 6 Fort Calhoun, NE City Nett 4.8 149' X 7 Fence around intake gate, 101*

Desoto WItdiife Refuge 2.0 X 8 Onsite Station Entrance to 180' Plant Site From Nwy. 75 0.6 X 9 Onsite Station NW of Plant 1.0 310' X 10 Onsite Station WSW of Pint 0.7 250* X 11 offsite Station SE of Plnt 0.9 130* X 12 Met. Utilities Dist., l Florence Treatment Plant 17.0 156' North Omaha, NE X 13 West bank Missouri River, downstream from Plant 0.5 106' discharge X X 14 Upstream from Intake 0.024 345' bldg., west benk of river X X RT 12/95

FORT CAL . STATIOM CHECISTRY PROCEDURE PA 45$F TABLE 5 Radioloalcal Environmental Samu>tino Locations and Media Sanple Approximate Approximate I Approximate Station Cottection Distance From Vegetables Neber Direction Air Monitorina Sites Containment (Degrees from Airborne and Food Airborne TLD Water Milk Sediment Fish (miles) north) Particulate lodine Products 15 Smith Farm (1) 1.9 133* x 16 OPPO Onsite WelI (1) 0.1 154' x

17 Headquarters Oldg., (1)

Desoto Wildlife Refuge 3.1 x 53' -

18 Miller Farm (4) 0.8 206*

x x 19 Flynn Dairy (4) 3.4 310' x 20 Mohr Dairy 7.9 187*

x(2) x(3) 21 Japp Dairy (4) 6.3 219' x 22 Fish Sanpling Area - R.M.

Missouri River 645.0 x

23 Fish Sampling Area - (5) R.M.

Missouri River 666.0 x

24 Legenhausen Farm (4) 0.7 207* x 25 Seltz Farm (2) 2.7 168* x 26 John Welchert Farm (4) 2.7 138' x

27 Jerry Welchert Farm 2.0 296*

x 28 Alvin Pechnik Farm 0.9 164*

x 29 E Ettis Farm 0.7 180*

x 30 Aztell Acreage 0.7 207*

x 31 Hakanson Fars 1.1 205*

x Notes:

(1) Senpling not required for pathway modeling, collections performed for additional inforsation only.

(2)

(3) men a milksites Vegetation sanple la notbased setected evaltable at aUse on Land location, survey aand broad leaf vegetation calculated doses. sample will be collected at that location as a substitute.

(4) location is currently discontinued and is docunented in the table for historical reference only.

(5) Location is 21.0 River miles north of plant. Exact location can not be illustrated on the map.

e RT G G

13 02 01 . 7

f R _

O0 s. o .__

6 _

s4 _

HE -

CG A

P A

I _

NN 2 _

RO - N 1 e OI .

2 FT U

, O 5 IC LN AU

_ H L \

CJ n%s ,

- A g' \ C m

/

T\

[

F u ' '

- 7 6 e 7 '/

u 1 6 m p 2 2 E' *

)

l.

I 5}s 1 _

1-

= 1 O

. . 1 (7 5 6 2 v,

~r 6

Ov 6 ~

i 63 1,, ~

1 F

8 ,~,'

R 4 2

'\

( 2

8 3 / '

' 2 ~ 1 2 % 1 4

g 2 t g J

. s g c

N 7 y2

. R . _

TNN _

I A9 7, RUO L1 . ' OOI B FHT 4 -

LA AT CS 3

3 0 1 2 6 .

s

~

N OE I R TU AD

$ g TE C

O R

0 1 9 /

okY LR AT P

CS I

TM RE OH FC

FORT CA. J STATION CHECISTRY PROCEDURE CD . .A-0001 PAGE 47 0F 123 TABLE 6 Detection Capabilities for Environmental Sancte Analysis (1)(2)(3)

Lower Limit Sf Detection (LLD)

Gross Sanot e Units Beta 11. - 3 !!g ",4 Fe-59 Co-58. 60 Zn-65 Zr-95 Nb-95 I-131 Cs-134 Cs-137 sa-140 Water pcl/L -- 2.0E+03 1.5E+01 3.0E+01 1.5E+01 3.0E+01 1.5E+01 1.5E+01 1.0E+00 1.5E+01 1.8E+01 1.5E+01 Fish pCl/kg -- --

1.3E+02 2.6E+02 1.3E+02 2.6E+02 -- -- --

1.3E+02 1.5E+02 --

(wet)

Milk pcl/L -- -- -- -- -- -- -- --

1.0E+00 1.5E+01 1.8E+01 1.5E+01 Air pCi/m3 1.0E-02 -- -- -- --

' Particu-7.0E-02 -- -- --

late or Gases sediment pCi/kg -- -- -- -- -- -- --

(dry) 1.5E+02 1.8E+02 --

Grass or pCi/kg -- -- -- -- -- -- -- --

6.0E+01 6.0E+01 8.0E+01 --

Broad Leaf (wet)

Vegetation /

Vegetables or Food Products (1) This list does not mean that only these nuctides are to be considered. Other peaks that are identifiable as Plant effluents, together with those of the above Section 5.1. nuclides, shalt also be analyzed and reported in the Annual Radiological Envirorenental Operating Report pursuant to Part II, (2) Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the reccennenda-tions of Regulatory Guide 4.13.

(3) The LLD is defined, for purposes of these specifications, as the amattest concentraticn or radioactive materiet in a souple that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsety concluding that a blank observation represents a "real" signal.

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

4.66 sb LLD =

E -

V - 2.22E+06 -

Y - exp(-Aat) e e -

O

! FORT CAL CNEZISTRY TATION E

J PAGE 48 0F 123 J

CH s .s-0001 TABLE 7 Reportina Levels for Radioactivity Concentrations in Envlie-,tal SaantesIII Seele 1!n_ils N-3 !!D-14 Fe-59 o

[o-18 Co-H Zn-65 M Hb-95 I-131 cs-134 Cs-137 so-140 Water pCl/t. 2.0E+04 1.0E+03 4.0E+02 1.0E+03 3.0E+02 3.0E+02 4.0E+02 4.0E+02 2.0E+00 3.0E+01 5.0E+01 2.0E+02 Fish pCl/kg --

3.0E+04 1.0E+04 3.0E+04 1.0E+04 2.0E+04 -- -- --

1.0E+03 2.0E+03 --

(wet)

Milk pct /L -- -- -- -- -- -- -- --

3.0E+00 6.0E+01 7.0E+01 3.0E+02 Air pCl/E -- -- -- -- -- --

Particutate 9.0E-01 -- -- --

or Gases Grass or pCl/kg -- -- -- -- -- -- --

Broad Leaf (wet) 1.0E+02 1.0E+03 2.0E+03 --

Vegetation /

Vegetables or Food Products 12/95 l

(1)

A Mon-routine report shall be sutaitted when more than one of the radionuctides listed above are detected in the saapting medlue and:

Concentration (1) + foncentration (2) + - - - - - t 1.0 Reporting Level (1) Weporting Levet (2) 1 When radionuclides other than those listed above are detected and are the result of Plant effluents, this report shall be submitted if the poten-tial annual dose to a member of the general ptblic is equal to or greater than the dose objectives of Part 11, section 1.1 and 1.2.

is not required if the measured level of radioactivity was not the result of Plant effluents; however, in such an event, the condition shall beThis report-reported and described in the Annual Radiological Environmental Operating Report.

12/95.

R7

_. A ___. .J a _ _ e _ __ -h-FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 49 OF 123 J

O 1

1 1

j l

1 i

PART III l

RADIOLOGICAL EFFLUENT RADIATION MONITOR CALCULATIONS k

1 O

4 1

i a

4 i

O R7

FORT CALHOUN STATION CHEMISTRY PROCEDURE CH-ODCM-0001 PAGE 50 OF 123 1.0 EFFLUENT MONITOR SETPOINTS 1.1 Licuid Effluents There are two liquid discharge pathways to the Missouri River.

These pathways originate with the radioactive liquid waste processing system (monitor or hotel tanks) and the steam generator blowdown system. Both of these pathways empty into the circulating water system which discharges to the Missouri River (see Figure 1) . Figure 2 depicts the liquid discharge pathways and associated radiation monitors. Figure 3 depicts the methods of liquid effluent treatment. A detailed discussion of the liquid effluent treatment system is presented in Section 2.1.

The flowrate for dilution water varies with the number of circulating water pumps in service, the number of raw water pumps in service, and with the operation of the warm water ;

recirculation.

Some warm water from the condenser outlet is diverted from the circulating water discharge to upstream of the intake structure to help prevent ice from forming on the 1 circulating water pump intakes during winter months. The j

varying dilution flowrate and utilization of warm water recirculation monitor is accounted tank and for in the stream generation dilution calculations for releases.

Alarm setpoints shall be established for the liquid effluent (q

monitoring instrumentation to ensure that the concentration of Vj radioactive material released in liquid effluents at site discharge shall be less than the concentrations specified in 10 CFR 20, Appendix B, Table 2, Column 2.

d Cs-137 is the most abundant radionuclide in liquid effluent streams and is used to' calibrate the liquid effluent monitors.

4

(

O .

R7

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 51 OF 123 1.0 EFFLUENT MONITOR SETPOINTS (Continued) 1.2 Licuid Effluent Radiation Monitors 1.2.1 Steam Generator Blowdown Monitors (RM-054A and B)

These process radiation detectors monitor the flow through the steam generator blowdown lines and automatically close the blowdown isolation valves if the monitor high alarm setpoint is reached The high alarm setpoint calculations are based on controlling the discharge at 10 CFR 20 limits of 1.0E-06 yCi/ml at site discharge.

The following calculations for maximum concentration and i alarm setpoints are valid when steam generator blowdown !

is the only liquid release pathway. For simultaneous radioactive liquid releases of steam generator blowdown and monitor tank discharge, refer to Section 1.5.1.

The maximum allowable concentration in the blowdown line is calculated as follows: ;

(1. 0E-06 pCl/ml) (X,)

Yo Where:

l 1.0E-06 yCi/ml = 10 CFR 20 Limit for unidentified radionuclides at site discharge (10 CFR 20, Appendix B, Note 2)..

X. - Total dilution flow in the discharge tunnel (gpm). (Normal flow is based on 1 circulating water pump at 120,000 gpm. Other flowrates may be used, as required.)

Y. - Blowdown flow rate (gpm). (Normal blowdown flow rate is based on 2 transfer pumps with a design flow of 135 gpm each, 270 gpm total.

Other flow rates may be used, as required.)

A = Maximum allowable blowdown concentration .

(yCi/ml).

O R7

FORT CALHOUN STATION CHEMISTRY PROCEDURE CH-ODCN- 0001 PAGE 52 OF 123 1.0 EFFLUENT MONITOR SETPOINTS (Continued) 1.2.1 The high alarm setpoint (CPM) =

.85 [ (Sf) (A,) + B ]

Where:

.85 -

Correction factor for instrument meter error..

Sr =

Detector sensitivity factor (CPM /pC1/ml).

i (Sensitivity based on Cs-137).

A, =

j Mav4==-

(pCi/ml).

allowable blowdown line activity t

B = Background (CPM).

- Setpoints may be recalculated based on adjusted i

dilution flow and adjusted blowdown flow, An alert setpoint will be chosen at a value below the alarm setpoint so that significant increases in activity will be identified prior to automatic actuation of the blowdown isolation valves. 1 j g 1.2 2 Overboard Discharge Header Monitor (RM-055)

This process radiation monitor provides control of the

' waste monitor tank effluent by monitoring the overboard header prior to its discharge into the circulating water i

discharge tunnel.. The concentration of activity at i

discharge is controlled below the 10 CFR 20 limit of 1.0E-06 pCi/ml at site discharge for unidentified isotopes by the high alarm setpoint which closes the

overboard flow control valve.

The following calculations for maximum concentration and i

alarm setpoints are valid when Monitor Tank discharge is the only liquid release pathway. For simultaneous radioactive liquid releases of monitor tank discharge and i

i steam generator blowdown, refer to Section 1.5.1.

e l

'O -

R7 ;

l i

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 53 OF 123 1.0 EFFLUENT MONITOR SETPOINTS (Continued) 1.2.2 The ma_virmim allowable concentration in the overboard discharge header is:

(1.0E-06 pCi/ml) (X,)

Y, Where:

1.0E-06 pCi/ml =

10 CFR 20 Limit for unidentified radionuclides at site discharge (10 CFR 20, Appendix B, Note 2).

X. -

Total dilution flow in the discharge tunnel (gpm) . (Normal flow is based on 1 circulating water pump at 120,000 gpm. Other flowrates such as raw water pump (s) may be used, as required.)

Y. - Maximum monitor tank discharge flow rate (gpm) . (Normal monitor tank maximum flow is 50 gpm. Other flow rates such as raw water pump (s) may i be used, as required.)

l A. - Maximum allowable activity in

. discharge header (pci/ml) . l l

O R7

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 54 OF 123 1.0 EFFLUENT MONITOR SETPOINTS (Continued) d 1.2.2 The high alarm setpoint (CPM) =

.85 [ (Sf) (A.) + B]

Where:

.85 =

Correction factor for instrument meter error.

Sr -

Detector sensitivity factor (CPM /pCi/ml).

(Sensitivity based on Cs-137).

A, =

Maximum allowable concentration in 3 discharge header (yCi/ml). j B = Background (CPM).

An alert setpoint will be chosen at a value below the alarm setpoint so that significant increases in activity will be identified, prior to automatic actuation of the overboard flow control valve.

O O .

R7

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 55 OF 123 1.0 EFFLUENT MONITOR SETPOINTS (Continued) 1.3 Airborne Effluents The airborne effluent monitoring instrumentation for controlling and monitoring normal radioactive material releases in accordance with 10 CFR 20, Appendix B, Table 2, Column 1 limits at the unrestricted area boundary (see Figure 1), are summarized as follows:

A. Auxiliary Buildina - The Auxiliary Building Exhaust Stack receives discharges from the waste gas decay tanks, containment purge, containment vent systems and the auxiliary building ventilation system.

Radiation Monitor RM-062 provides noble gas I monitoring and iodine and particulate sampling for the Auxiliary Building Exhaust Stack. Backup noble I

, gae monitoring and iodine and particulate sampling j l is provided by RM-052. Ventilation I, solation !

Actuation Signal (VIAS) is actuated by exceeding a monitor's alarm setpoint. Actuation of VIAS will isolate releases from containment and waste gas decay tanks. The Auxiliary Building Exhaust fans will remain in operation.

B. Laboratory and Radioactive Waste Processina Buildina' (LRWPB) - Noble gas monitoring and particulate and iodine sampling is provided by RM-043. This radiation monitor / sampler does not serve a control function.

C. Condenser Off-Gas Monitors - Noble gas activity is monitored by RM-057. The condenser off-gas is discharged directly to the environment. Exceeding the high alarm setpoint on RM-057 will activate isolation of main steam to the Auxiliary Steam System.

An airborne radioactive waste flow diagram with the applicable, associated radiation monitoring instrumentation and controls is presented as Figure 4. The airborne waste disposal system is presented in Figure 5. A detailed discussion of the airborne effluent treatment system is presented in Section 2.2.

O R7

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 56 OF 123 1.0 EFFLUENT MONITOR SETPOINTS (Continued) 1.4 Airborne Effluent Radiation Monitors 1.4.1 Auxiliary Building Exhaust Stack Noble Gas Activity Monitor (RM-062/RM-052)

Either of these monitors may be used to measure the noble gas activity in the exhaust stack. The noble gas is monitored after passing through a particulate filter, and charcoal cartridge. The monitor controls airborne releases so that the 10 CFR 20 limit at the unrestricted area boundary of 5.0E-07 yCi/cc, based upon Xe-133, is not exceeded. The ventilation Isolation Actuation Signal is initiated when the high alarm setpoint is reached. j The following calculations for maximum release rate and alarm setpoint are valid when Auxiliary Building Exhaust Stack is the only airborne release pathway. For simultaneous airborne releases from Auxiliary Building Exhaust Stack, Condenser Off-gas and the LRWPB Exhaust Stack, refer to Section 1.5.2.

The maximum allowable release rate for stack airborne activity is calculated as follows: ,

__ ( 5. 0E-07 pCl/cc) x (1. 0E+06 cc/m3 ) = 1. 0E+05 pCl/sec (5.0E-06 sec/m 3)

Where:

5.0E-07 yCi/cc = 10 CFR 20 Limit at the unrestricted f area boundary (based upon Xe-133). ;

1 5.0E-06 sec/m2 - Annual average dispersion factor at the unrestricted area boundary.

I 1.0E+06 c'c/m> =

Constant of unit conversion.

The high alarm setpoint (CPM):

Setpoinc = . 85 (

(1.0E+05) ( S,.) (60)

(Fy ) (28317)

R7 e,m m:

w , , . - - , - .,.i-. ,. , - - - - ,

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 57 OF 123 1.0 EFFLUENT MONITOR SETPOINTS (Continued)

1.4.1 Where

.85 =

Correction for instrument meter error.

Sr = Detector sensitivity factor (CPM /

pCi/cc). (Sensitivity based on Xe-133) 60 =

Conversion (seconds to minutes) .

28317 =

Conversion factor (ft* to cc).

F, = Auxiliary Building Exhaust stack flow rate (SCFM). (Default maximum flow rate is 122500 cfm for 3 Auxiliary Building exhaust fans and 2 containment purge fans in operation. Other flow rates may be used, as required.)

B = Background (CPM). )

An alarm setpoint will be chosen at a value below the alarm setpoint so that significant increases in activity will be identified, prior to actuation of VIAS.

i O

R7

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 58 OF 123 1.O EFFLUENT MONITOR SETPOINTS (Continued) 1.4.2 Condenser Air Ejector Monitor (RM-057)

This monitor is located in the turbine building and monitors the condenser off-gas. The purpose of this ;

monitor is to monitor the condenser off-gas discharges so that the 10 CFR 20 limit at the unrestricted area boundary of 5.0E-07 yCi/cc, based upon Xe-133, is not exceeded.

The following calculations for ==v4== release rate and alarm setpoint are valid when condenser off-gas is the only airborne release pathway. For simultaneous airborne releases from condenser off-gas, Auxiliary Building Exhaust Stack, and the LRWPB Exhaust Stack, refer to Section 1.5.2.

The maximum allowable release rate for condenser air ejector monitor is as follows:

(5.0E-07 pCi/cc) x (1.0E+06 cc/m 3) = 1. 0E+05 pCl/sec (5.0E-06 sec/m3 )

Where:

5.0E-07 yCi/cc =

10 CFR 20 Limit at the unrestricted area boundary (based upon Xe-133).

5.0E-06 sec/m* =

Annual average dispersion factor at the unrestricted area boundary.

1.0E+06 cc/m8 -

Constant of unit conversion.

The high alarm setpoint (CPM):

Se tpo2n c = . 85 [

(1.0E+05) (Sp ) (60)

(Fy ) (28317) ;

O .

R7

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE l

PAGE 59 OF 123 '

1.0 EFFLUENT MONITOR SETPOINTH (Continued) 3

1.4.2 Where

I

.85 = Correction for instrument meter i error.

l S, = Detector sensitivity factor !

(CPM /gCi/cc). (Sensitivity based on !

.Xe-133) 60 -

Conversion (seconds to minutes).

28317 -

Conversion factor (ft* to cc). ;

F, =

Vent stack flow rate (SCFM) .

Default maximum flow rate is 4755 scfm (3 vacuum pumps in hogging mode. Other flow rates may be used, as required.)

B = Background (CPM).

An alert setpoint will be chosen at a value below the alarm setpoint so that significant increases in activity will be identified, allowing time for corrective actions prior to exceeding the alarm setpoint and tripping of the auxiliary steam supply valve, RCV-978.

9 0

R7

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE l PAGE 60 OF 123 1.0 EFFLUENT MONITOR SETPOINTS (Continued) 1.4.3 Laboratory and Radioactive Waste Processing Building Exhaust Stack Noble Gas Activity Monitor and Iodine and Particulate Sampler (RM-043)

RM-043 is located in the Radwaste Building and samples the LRWPB Exhaust Stack. The monitor alarm setpoint is based on the 10 CFR 20 limit for Xe-133 at the unrestricted area boundary.

The following calculations for maximum release rate and alarm setpoint are valid when the LRWPB Exhaust Stack is the only airborne release pathway. For simultaneous airborne releases from condenser off-gas, Auxiliary Building Exhaust Stack, and the LRWPB Exhaust Stack, refer to Section 1.5.2.

The maximum allowable release rate for RM-043 is as follows:

(5.0E-07 pCl/cc) x (1.0E+06cc/m 3) = 1. 0E+05 pCl/sec (5.0E-06 sec/m3)

Where:

5.0E-07 yCi/cc = 10 CFR 20 Limit at the unrestricted area boundary (based upon Xe-133).

5.0E-06 sec/m* = Annual average dispersion factor at the unrestricted area boundary.

1.0E+06 cc/m* =

Constant of unit conversion. i 4

i O .

R7

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 61 OF 123 l 1.0 EFFLUENT MONITOR SETPOINTS (Continued) 1.4.3 The high alarm setpoint (CPM):

Setpoint = . 85 [

(1. 0E+05 ) (S,.) (60)

(Fy) (28317) +B1 1

Where.

j

.85 -

Correction for instrument meter error.

Sr =

Detector sensitivity factor (CPM /pCi/cc). (Sensitivity based on XE-133) ;

60 -

Conversion (seconds to minutes) .

28317 =

Conversion factor (ft8 to cc).

F, =

LRWPB Exhaust stack flow rate (SCFM) . (Default flow rate is 28700 cfm. Other flow rates may be used if required.

B = Background (CPM).

An alert setpoint will be chosen at a value below the alam setpoint so that significant increases in activity will be identified.

This monitor alarms in the Control Room. There are no automatic control functions associated with the actuation of the alarm.

O R7

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

FORT CALHOUN STATION CH-ODCM-0001 -

CHEMISTRY PROCEDURE PAGE 62 OF 123 1.0 EFFLUENT MONITOR SETPOINTS (Continued) 1.5 S4m"Itaneous Release Pathways F

1.5.1 Liquid Release Pathways The liquid radiation monitors (RM-054A/054B and RM-055) control liquid releases so that 10 CFR 20 limit of 1.0E-06 pCi/ml for unidentified isotopes at site discharge is not exceeded. There are two liquid release pathways that contribute to the concentration at site discharge. These are Steam Generator Blowdown and Monitor Tank Overboard Discharge Header. When more than one pathway is utilized for radioactive releases, it is necessary to adjust the alarm setpoints given in Section 1.2 so that unrestricted area concentration limits are not exceeded.

The calculations for the. alarm setpointa for the liquid effluent monitors will be adjusted as follows:

A, " K, A, + K 1A1

, K, (1.0E-06 pCl/ml) (X,) . K (1.0E-06 pcl/ml) (X,)

1 Yo Y1 Where:

Ar =

Sum of individual maximum allowable concentrations for Steam Generator and Monitor Tank prior to dilution for simultaneous liquid releases (pci/ml)

A, = Maximum allowable concentration in Steam Generator blowdown Line (pCi/ml) ,

l A1 =

Maximum allowable concentration in Monitor Tank Discharge Line (pCi/ml) 4 K= Proportionality constant for Steam Generator (See Table 1)

K1 = Proportionality constant for Monitor Tank (See Table 1)

X= Total dilution flow in Discharge Tunnel (GPM)

R7

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 63 OF 123 1.0 EFFLUENT MONITOR SETPOINTS (Continued) l

1.5.1 Where

l Y, = Steam Generator Blowdown flowrate (GPM)

Yi - Monitor Tank Discharge flowrate (GPM) 1 The High Alarm Setpoint for Steam Generator Blowdown !

monitors, RM-054A/054B, will then be: '

1 Alarm Setpoint (CPM) =

. 8 5 (X, S,., A, + B,] l l

The High Alarm Setpoint for Monitor Tank Discharge {

Monitor, RM-055, will then be: 1 l

l Alarm Setpoint (CPM) = .85 (K1 S,,1 1 A +B] 1 \

l Where:

Sr. -

Detector Sensitivity factor for l RM-054A/054B, CPM /(pCi/ml), based on Cs-137.

Sri =

Detector Sensitivity factor for RM-055, CPM /(pCi/ml), based on Cs-137.

A, =

Maximum allowable concentration in SG Blowdown line. (pCi/ml)

At -

Maximum allowable concentration in MT Discharge line. (pCi/ml)

B. = RM-054A/054B background countrate. (CPM)

B2 - RM-055 background countrate. (CPM) i Where: l K., K 1 - Proportionality constants. See Table 1.

i i

O R7 l i

FORT CALHOUN STATION CHEMISTRY PROCEDURE CH-ODCM-0001 PAGE 64 OF 123-1.0 EFFLUENT MONITOR SETPOINTS (Continued) 1.5.2 Airborne Release Pathway .

2 The noble gas radiation monitors (RM-043, RM-057, and l

RM-062/RM-052) control airborne releases so tt&t 10 CFR 20 limits of 5.0E-07 pCi/cc for noble gages-at'the i unrestricted area boundary is not exceeded. There are i

three pathways that contribute to the concentration at i the unrestricted a,rea boundary. These are the Auxiliary i

Building Exhaust Stack, Condenser Off-gas, and the LRWPB i Exhaust Stack. When more than one pathway is utilized i

for radioactive releases, it is necessary to adjust the i.

alarm setpoints given in Section 1.4-to ensure that unrestricted area concentration limits are not exceeded.

The calculations for the alarm setpoints for the airborne i effluent monitors will be adjusted as follows:

j The maximum allowable release rates for simultaneous j

releases is:

Max. Release Rate = Concg KRg=

g Kg.

Where:

R1 =

RM-062/RM-052 release rate (pCi/sec) i R2 =

RM-057 release rate (pCi/sec)

R3 =

RM-043 release rate (pCi/sec)

K2 *K 3 =

Proportionality constants. See Table 1.

I Conct -

Radionuclide concentration for the l

monitor of interest.

O .

R7

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROC.IDURE PAGE 65 OF 123 1.0 EFFLUENT MONITOR SETPOINTS (Continued) 1.5.2 The maximum release rate is then:

K 2 (5.0E-07 pCl/cc) K2 (5.0E-07 pCl/cc)

5. 0E-06 sec/4n3 5. 0E-06 sec/m3 K 3 (5.0E-07 pCl/cc) ec e ease Race 5.0E-06 sec/m3 7 .

The alarm setpoints for the noble gas monitors will then be:

. E+ , (60)

RM-062/052 = . 85 [ K2 +B]

Fy (28317)

O RM-057 = . 85 [ K,'

' 0)

(Fy ) (28317) +B]

RM-043 = . 85 [ K3 +3)

(Fv) (28317)

O R7

! FORT CALHOUN STATION CHEMISTRY PROCEDURE CH-ODCM-0001 !

' PAGE 66 OF 123 t

1 .0 EFFLUENT MONITOR SETPOINTS (Continued)

O 1.5.2 Where: '

t

.85 -

Correction factor for instrument i 4

meter error. '

K2 + K 3 -

Proportionality constants. See Table 1. l Sr -

Detector sensitivity factor.

{

Fv =

Vent stack flowrate. (Condenser s

off-gas flowrate for RM-057, LRWPB Exhaust stack flow rate for 2

RM-043, Auxiliary Building Exhaust Stack flow rate for RM-062/052).

B =

Monitor background count rate.

60 =

Constant of unit conversion (60 sec/ min).

O l

l O .

R7

l FORT CALHOUN STATION CH-ODCM-0001 :

CHEMISTRY PROCEDURE PAGE 67 OF 123 l TABLE 1 i Proportionally Constants for Simultaneous Airborne Releases.

NOTE: The Fort Calhoun Station is capable of performing simultaneous cirborne releases given that the sum of the Unrestricted Area Fraction ,

Sum for all airborne releases remains less than or equal to 1.0.

{

1. Auxiliary Building Exhaust Stack Total 0.80 K2 Noble Gases 0.70 RM-062 or RM-052 Iodine / Particulate / Tritium 0.10 Contributing Pathways:

a) Auxiliary Building 0.10 b) Containment Building 0.65 c) Waste Gas Decay Tanks 0.05

2. Condenser / Air Ejector Total 0.10 ,

K2 Noble Gases 0.05 RM-057 Tritium 0.05 l

Contributing Pathways:

a) Condenser Off Gas 0.10

3. Laboratory and Radioactive Waste Building Exhaust Stack Total 0.10 K3 Noble Gases 0.05 RM-043 Iodine / Particulate 0.05 Contributing Pathways:

a) Laboratory and Radioactive Waste Building Exhaust Stack 0.10 Airborne Release Total 1.00 NOTE: The Fort Calhoun Station is capable of performing simultaneous liquid releases given that the sum of the Unrestricted Area Fraction Sum for all liquid releases remains less than or equal to 1.0.

B. Proportionally Constants for Simultaneous Liquid Releases.

1. Ko Steam Generator Releases 0.30 RM-054A/054B

2. K1 Waste Liquid Releases 0.70 RM-055 Liquid Release Total 1.00 R7

FORT CALHOUN STATION CHEMISTRY PROCEDURE CH-ODCM- 0001 ?

PAGE 68 OF 123 ,

2.O RADIOACTIVE WASTE TREADGDrr SYSTEM 2.1 Liould nadwasta Traar==nt Svatam The major equipment or subsystem (s) of the liquid radwaste treatment system are comprised of the waste filters, monitor tanks, and evaporator. This equipment, including associated pumps, valves and piping, is used in different combinttions on an as-needed basis to process the liquid effluent to provide compliance with the as low as is reasonably achievable philosophy and the applicable section of 10 CPR Part 20. The liquid radwaste treatment system is described in Section 11.1.2 of the USAR. For affluent release points and monitor locations refer to P&ID's 11405-N-100, M-9 and M-8.

A filtration / ion exchange (FIX) system may be utilized for processing is not in service. liquid radwaste in the event the waste evaporator The system consists of a booster pump, charcoal pretreatment filter, and pressure vessels containing l organic / inorganic resins, which can be configured for optimum performance.

The effluent from the FIX system is directed to the monitor tanks for release.

Waste filters (WD-17A and WD-17B) are used only on those occasions when considered necessary, otherwise the flows from the low activity fluids may bypass the filters.

decontamination factors (iodines, Cs, Rb, others) Nowascredit for O for these filters during the 10 CPR 50 App =adiv I dose design objective evaluation; therefore, the inoperability of these taken filters does not affect the dose contributions to any individual in the unrestricted areas via liquid ~ pthways. The inoperability of waste filters will not be considered a reportable event in accordance with Part II, Section 2.1.

' Every effort will be made to process all liquid waste, except from the hotel waste tanks, through the evaporator or FIX before entering the monitor tanks. If the radioactive liquid waste is discharged without processing and it appears that 1/2 of the annual objective will be exceeded during the calendar quarter, a special report shall be submitted to the Commission pursuant to Part II, Section 2.1.

The quantity of radioactive material contained in each unprotected outdoor liquid holdup tank shall not exceed 10 curies, excluding tritium and dissolved or entrained noble gases.

O .

R7

I l

FORT CALHOUN STATION CH-ODCM-0001 l CHEMISTRY PROCEDURE PAGE 69 OF 123 !

2.0 RADIOACTIVE WASTE TREATMENT SYSTEM l 2.2 Airborne Radwaste Treatment System The waste airborne radioactive material at Fort Calhoun Station is collected in the vent header where the gas compressors take suction, compress the gas and deliver it to one of the four gas decay tanks. The waste airborne radioactive material is treated in these gas decay tanks by holding for radioactive decay prior to final controlled release to the environs. In order to provide conformance with the dose design objectives, gas decay tanks are normally stored for approximately 30 days, with earlier release allowed to support plant operation only, and thus achieve decay of short half-life radioactive materials, e.g., I-131, Xe-133. j If the radioactive airborne wastes from the gas decay tanks i are discharged without processing in accordance with the above l conditions, a special report shall be submitted to the l Commission pursuant to Part II, Section 2.2. l The radioactive effluents from the controlled access area of the auxiliary building are filtered by the HEPA filters in the i auxiliary building ventilation system. If the radioactive i effluents are discharged without the HEPA filters, a special ,

report shall be submitted to the NRC pursuant to Part II, I Section 2.2.

The discharge from the gas decay tanks is routed through charcoal and HEPA filter unit VA-82. No credit was taken for ,

the operation of hydrogen purge filters during the 10 CFR 50, l Appendix I dose design evaluation and doses through the l airborne effluent pathways were well below the design objectives. The unavailability of hydrogen purge filters will not be considered a reportable event as per Part II, Section 2.2.

The containment air is processed through at least one of the redundant containment HEPA and charcoal filters in the Containment air Cooling and Piltering Units prior to purging.

If the containment purges are made without processing through one of the Containment Air Cooling and Filtering Units, a special report shall be submitted to the Commission pursuant to Part II, Section 2.2.

The airborne radwaste treatment system is described in Section 11.1.3 of the USAR. For effluent release points and monitor locations refer to P&ID's 11405-M-1 and M-261.

O R7

PORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 70 OF 123 Figure 1

-._ b _ \

Tr=

su.

\ [0WA r, s UNRESTRICTED AREA BOUNDARY k' s k

I N

s NEBRASKA 1-RESTRICTED r AREA

s

\'

1 N

N FORT -

MET \

l TOWER 2 A '/ CALHOUN U;FT #1 t

/ * \

g

, ,-, j ~~~~~. f3Soggq k ", k & s'

\/

, 's~s's ,

O' TO CONTROILED AREA ADMIN.

BIBG.

BLAIR )

TRAINING p '- -

\

CENTER d' l \

j __ _ __ _ __ _ __

/ 5

)

i UNRESTRICTED AREA 75 i LIQUID EFFLUENTS DISCHARGE \ s 2 AIRBORNE EFFLUENTS DISCHARGE 's TO OMAHA

? Y $

SCALE IN MILES O

L.) EXCL.USION AND SITE BOUNDARY MAP R7

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 71 OF 123 l l

Figure 2 l O

HOTEL S/G S/G A

RAW TANKS B WATER I BLOWDOWN BLOWDOWN V A Jk MONITOR l TANKS Q) @ !

=

c G) l If If ,

OUTFALL

( CIRCULATING g 'll l

WATER j

WARM WATER RECIRCULATION fy RIVER f RIVER U

@ RM-054A -

@ RM-0548

@ RM-055 LIQUID RADIOACTIVE DISCHARGE PATHWAYS Figure 3 CH8915E ,

R7

FORT CALHOUN STATION CHEMISTRY PROCEDURE CH-ODCM-0001 PAGE 72 OP 123 w 4 m w. 2 '

/ AUXILIARY SYSTEMS REACTOR COOLANT HOTEL WASTE PROCESS WASTE WASTE Floor Drains CVCS Bleedoff laundry Waste Sump Flows Equipment Drains i Shower Drains i RC loop Drains i

If r

i I f I f Spent Regenerant( ) -

Waste Holdup Hotel Tanks -

Tanks T&

5530 Gal. ( )

45,800 Gal. 1 0 Gat f I (

I

\f Waste Filters 50 Microns Dernineralizer Vessels 30 GPM

= 00000 Char oal Filter 69 Cu. Ft.

(optional) '

)f l

cc ;

Monitor Tanks I 8770 Gal.

oo If Overboard Header (To River)

IIDUID RADIOACTIVE WASTE DISPOSAL SYSTEM R7

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 73 OF 123 Figure 4

)k RM-043 Noble Gas Monitor, and 1 Iodine & Particulate 1 Sampler )

l 1

l LRWPB Laboratory LABORATORY AND RADIOACTIVE WASTE PROCESSING BUILDING N l RM-062,052 Noble Gas Monitor Iodine & Particulate l Sampler j

]\

O au-os7 nedie Monitoro -

i CONDENSER OFFGAS AUXILIARY BUILDING EXHAUST STACK Condenser Auxiliary Building Containment Ventilation Building Ventilation AIRBORNE EFFLUENT DISCHARGE PATHWAYS O

R7

FORT calif 0UN STATION CHEMISTRY PROCEDURE CH-ODCM-0001 PAGE 74 OF 123 Figure 5 Turbine -

A

[ Yentilation Condenser To Atmosphere 122 s.o. "

A

-a -a

) k To Roof Condenser Vent Vacuum Pumps

+l Charcoal

+ Absorber UI "w Gas Holdup Tanks (4) > >

( 400 CuFt (each) ) >

HEPA Filter WASTE GAS AND CONDENSER OFF-GAS SYSTEMS Inlet Roll Fans O Filters containment o

( "se Containment o m-HEPA Hlter

[

Cooling and m Internal > c50.000 SCFM ^

Recirculation Purge System-HEPA Charcoal Filters Outlet CONTAINMENT BUILDING VENTILATION CONTROL Charcoal Filters Fuel Handling "*

4 Areas J, HEPA

+- Filter C Fans Safety ""

Roll > > Injection r r ~

Filters C

Areas Other

[vO .500 S N Areas '

Ground O- AIRBORNE RADIOACTIVE WASTE DISPOSAL SYSTEM S

R7

FORT CALHOUN STATION CH-ODQ1-0001 CHEMISTRY PROCEDURE PAGE 75 OF 123 4

S RADIOLOGICAL EFFLUENT MONITORING CALCULATIONS 1

l 1

1 I

O\

i R7 !

l

FORT CALHOUN STATION CHEMISTRY PROCEDURE CH-ODCM-0001 PAGE 76 OF 123 1 .O EFFLUENT CONCENTRATIONS O 1.1 Liould Effluent Concentratinne The concentration of radioactive material in liquid effluents I (after dilution in the Circulating Water System) will be limited to B, Appendix theTable concentrations 2, as specified in 10 CFR 20, Column 2. For batch releases (Monitor ;

and Hotel Waste Tanks and Steam Generators) and for continuous !

releases (Steam Generator Blowdown), the analyses will be I performed in accordance with Part II, Table 1, and the concentration of each radionuclide at site discharge will be ;

calculated, based on the following equation. I 3

Radionuclide concentration at site discharge:

A, = *1 S F+f n

and As / weci s1 '

O Where:

A, =

concentration at site discharge for radionuclide, i, in pCi/ml.

ai =

concentration of radionuclide, i, in the undiluted effluent in pC1/ml.

f =

undiluted effluent flowrate, in gpm. ;

F =

total diluted effluent flowrate in gpm.

wect =

water effluent concentration limit for radionuclide, i, per 10 CFR 20, Appendix B, Table 2, Column 2.

O .

R7

l l

1 FORT CALHOUN STATION CH-ODCM-0001 j CHEMISTRY PROCEDURE PAGE 77 OF 123 1.O EFFLUENT CONCENTRATIONS l i

NOTE: In addition to the above defined method, Notes 1 through 4 of 10 CFR Part 20, Appendix B, will also be applicable.

1.2 Airborne Effluent Concentrations The concentration at the unrestricted area boundary, due to airborne effluent releases, will be limited to less than 1 Appendix B, Table 2, Column 1, values. Radiation monitor alarm setpoints are established to ensure that these release limits are not exceeded. In the event an airborne effluent ;

release from the station result in an alarm setpoint being exceeded, an evaluation of the unrestricted area boundary concentration resulting from the release will be performed:

To deterndne the concentration and air effluent concentration (aec) fraction summation at the unrestricted area boundary, the following equations will be used:

Ag = K, Og (x/Q)

O andf Aj/aeci s1 Ja1 Where:

l Ai = Concentration of radionuclide, i, at the unrestricted area boundary K, =

Constant of unit conversion. (1E-6m' /cc) aect = Air effluent concentration limit (10 CFR 20, 1

Appendix B, Table 2, Column 1 value for radionuclide, 1)

Qi - The release rate of radionuclides i, in airborne effluents from all vent releases (in pCi/sec.)

(x/Q) =

SE-6 sec/m .

3 For all vent releases. The k highest calculated annual average relative

" concentration for any area at or beyond the unrestricted area boundary R7

l I

l FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE !

(

PAGE 78 OF 123 j 1 .O l EFFLUENT CONCENTRATIONS n

N./ As appropriate, simultaneous releases from the Auxiliary Building Ventilation Stack, Laboratory and Radwaste Building ;

Stack and condenser off gas will be considered in evaluating '

compliance with the release rate limits of 10 CFR 20. Monitor indications (readings) may be averaged over a time period not to exceed 15 minutes when determining noble gas release rate 3 based on correlation of the monitor reading and monitor sensitivity. Historical annual average dispersion parameters, as presented in Table 3, may be used for evaluating the ,

1 airborne effluent dose rate.

l NOTE: For administrative purposes, more conservative alarm setpoints than those as prescribed above may be imposed.

However, conditions exceeding those more limiting alarm setpoints do not necessarily indicate radioactive material release rates exceeding 10 CFR 20 limits. Provided actual releases do not result in radiation monitor indications exceeding alarm setpoint values based upon the above criteria, no further analyses are required for demonstrating compliance with 10 CFR 20.

2.0 RADIOACTIVE EFFLUENT DOSE CALCULATIONS p 2.1 Liauid Effluent Dome calculatirma d Three pathways for human exposure to liquid releases from FCS to the Missouri River exists: 1) fish, 2) drinking water, and 3) Shoreline deposition. Fish are considered to be taken from the vicinity of the plant discharge. The drinking water for Omaha is located 19 miles downfstream from FCS. The dilution factors for these pathways are derived from the Revised Environmental Report for FCS, (1974), (page 4-2D and 4-31). This report states that during Low-Low river conditions, the concentration at Omaha's water intake will be 514% of the concentration at discharge from FCS and will average 3%. This equates to a dilution factor of 7.14, which is used to calculate the maximum dose to an individual from liquid pathways and a dilution factor of 33.33, for calculating the average dose. All pathways combine to give i the dose to an individual in unrestricted areas.

10 CFR 50, App. I restricts the dose to individuals in the j

unrestricted areas from radioactive materials in liquid '

effluents from the Fort Calhoun Station to the following limits:

e during any calendar quarter 51.5 mrem to total body s5.0 mrem to any organ and e during any calendar year s 3.0 mrem'to total body s 10.0 mrem to any organ R7

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 79 OF 123 2.0 RADIOACTIVE EFFLUENT DOSE CALCULATIONS (Continued) 2.1 The following calculational methods shall be used for determining the dose or dose commitment from liquid effluents.

Doses from Licuid Effluent Pathways A. POTABLE WATER R,p3 = 1100 Q g,1pjegp ( _K, gp )

afP Where:

R.,3 = is the total annual dose to organ, j, of individuals of age group, a, fram all of the radionuclides, i, in pathway, p, in mrem /yr.

U., = is a usage factor that specifies the intake rate for an individual of age group, a, associated with pathway, p, in I/yr. Table 5 b4 = is the mixing ratio (reciprocal of the dilution factor) at the point of withdrawal of drinking water, dimensionless. Table 3 F = is the flow rate of the liquid effluent, in f t'/ sec.

Qi = is the annual release rate of radionuclide, i, in Ci/yr.

D i,3 = is the dose factor specific to a given age group, a, radionuclide, i, pathway, p, and organ, j, which can be used to calculate the radiation dose from an intake of a radionuclide, in mrem /pci. Tables 12-15 At = is the radiological decay constant of radionuclide, 1, in hr 2 t, = is the average transit time required for radionuclides to reach the point of exposure. For internal dose, t, is the total time elapsed between release of the radionuclides and ingestion of water, in hours.

Table 16 1100 = Constant (pCi

yr

f t'/Ci

sec

L)

O R7

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 80 OF 123 2.0 EADIOACTIVE EFFLUENT DOSE CALCULATIONS (Continued) 2.1 B. AQUATIC FOODS R,p3 = 1100

f* DB i jpD,3,$exp (-1g t,)

Where:

R.p3 =

is the total annual dose to organ, j, of individuals of age group, a, from all of the radionuclides, i, in pathway, p, in mrem /yr.

U., =

is a usage factor that specifies the intake rate for an individual of age group, a, associated with I pathway, p, in kg/yr. Table 5 l t

M, =

is the mixing ratio (reciprocal of the dilution factor) at the point of harvest of aquatic food, dimensionless. Table 3 F =

is the flow rate of the liquid effluent, in f t'/sec.

Qi =

is the annual release rate of radionuclide, i, in q Ci/yr. I C' B ip = is the equilibrium bioaccumulation factor for radionuclide, i, in pathway, p, expressed as the ratio of the concentration in biota (in pCi/kg) to the radionuclide concentration in water (in pCi/ liter), in (pC1/kg) / (pci/ liter) . Table 2 D.ip) =

is the dose factor specific to a given age group, a, radionuclide, i, pathway, p, and organ, j , which can I be used to calculate the radiation dose from an intake of a radionuclide, in mrem /pci. Tables 12-15 Ai =

is the radiological decay constant of radionuclide, i, in hr-2 t, =

is the average transit time required for radionuclides 1

to reach the point of exposure. For internal dose, t, is the total time elapsed between release of the radionuclides and ingestion of food, in hours.

Table 16 1100 = Constant (pCi

yr

f t'/Ci

sec

L)

O U .

R7

I FORT CALHOUN STATION CH-ODCM-0001 !

CHEMISTRY PROCEDURE PAGE 81 OF 123 2.0 RADIOACTIVE EFFLUENT DOSE CALCULATIONS (Continued) 2.1 C. SHORELINE DEPOSITS O :

1 l

R,g = 110, 0 0 0 OjTD jp ,jg [exp (-A fy t ) ) [1-exp (-A j3 c))

Where:

R.,3 = is the total annual dose to organ, j, of individuals of age group, a, from all of the radionuclides, i, in pathway, p, in mrem /yr.

U., -

is a usage factor that specifies the exposure time for an individual of age group, a, associated with pathway, p, in hr/yr. Table 5 M6 = is the mixing ratio (reciprocal of the dilution factor) at the point of exposure, dimensionless.

Table 3 W = is the shore-width factor, dimensionless. Table 16 F = is the flow rate of the liquid effluent, in f t 8/sec.

Qi - is the annual release rate of radionuclide, i, in Ci/yr.

T,i

= is the radioactive half life of radionuclide, i, in days.

D i,3 = is the dose factor specific radionuclide, i, which can be used to calculate the radiation dose from exposure to a given concentration of a radionuclide in sediment, expressed as a ratio of the dose rate (in mrem2 /hr) and the areal radionuclide concentration (in pCi/m ) . Table 7 At - is the radiological decay constant of radionuclide, i, in hr-1 t, - is the average transit time required for radionuclides to reach the point of exposure, in hours. Table 16 t3 - is the period of time for which sediment or soil is exposed to the contaminated water, in hours. Table 16 110,000 - Constant [ (100

pCi

yr

f t') / (Ci

sec

L)]

O O

R7

/,

FORT CALHOUN STATION CHEMISTRY PROCEDURE CH-ODCM-0001 PAGE 82 OF 123 2 .0 RADIOACTIVE EFFLUENT DOSE CALCULATIONS, (Continued)

O 2.2 Airborne Effluent Dose Calculations 2.2.1 Noble Gas 10 CFR 50, App. I, restricts the dose to individuals in the unrestricted areas from noble gases in airborne effluents limits:

from the Fort Calhoun Station to the following o During any calendar quarter s5 mrad-gamma air dose s10 mrad-beta air dose and e During any calendar year s10 mrad-gamma air dose s20 mrad-beta air dose The following general equations shall be used to calculate the gamma-air and beta-air doses:

O O .

R7

FORT CALHOUN STATION CHEMISTRY PROCEDURE CH-ODCM-0001 PAGE 83 OF 123 2.0 RADIOACTIVE EFFLUENT DOSE CALCULATIONS (Continued)

Doses from Noble Gases 2.2 A.

Annual Releases Gamma / Beta Air Dose from All Other Noble Gas DY(r,9) or DP(r,9) = 3.17 x io' o,[x/o]"(r,6) (DF} or D )

Where:

DFi, DF# t

=

are the gamma and beta air dose factors for a uniform semi-infinite cloud of radionuclide, i, in mrad-m'/pCi-yr. Table 1 D' ( r,6) or

=

are the annual gamma and beta air doses at D (r,6) distance r, in the sector at angle 9, from the discharge point, in mrad /yr.

Qt -

is the annual release rate of radionuclide, i, in Ci/yr.

[x/Q)"(r,0) =

is the annual average gaseous dispersion factor at distance r, in the sector at angle 0, in sec/m'.

Table 3 3.17x10' =

is the number of seconds per year.pci per ci divided by the number of B. Annual Total Body Dose from All Other Noble Gas Releases D{(r,6) = S, xg(r,6)DFB, 4-1 Where:

DFB t =

is the total body dose factor for a semi-infinite cloud of the radionuclide, 2 i, which includes the attenuation Table 1 of 5 g/cm of tissue, in mrem-m'/pci-yr.

D', ( r,0) =

is the annual total body dose due to immersion in a semi-infinite cloud at distance r, in the sector at angle 9, in mrem /yr.

Xi ( r,6) =

is the annual average ground-level concentration of radionuclide, i, at distance r, angle 6, in pCi/m'.

in the sector at Table 3 Sr = Shielding Factor. Table 16 R7

m. .. _ .m . _ . _ . _ _ . _ _ . _ _ . _ _ _ . _ . _ _ . . . _ _ . _ . _ _ _ . . _ _ _ _ . _ _ _ _

i FORT CALHOUN STATION CH-ODC31-0001 i CHEMISTRY PROCEDURE PAGE 84 OF 123 ,

2.0 RADIOACTIVE EFFLUENT DOSE CALCULATIONS (Continued) 2.2 C. Annual Skin Dose from All Other Noble Gas Releases i

D[(r,6) = 1.11 Sp %j (r,6)DF} + %j(r,6)DFSg Where:

DI(r,0) =

is the annual skin dose due to inimersion in a semi-infinite cloud at distance r, in the sector at angle 9, in mram/yr. i DF4 =

is the beta skin dose factor for a l semiinfinite cloud of radionuclide, i, in i mrem-m'/pCi-yr. Table 1 1.11 = is the average ratio of tissue to air r energy absorption coefficients. l 2.2.2 Radiciodine, Tritium, and Particulates '

10 CFR 50, App. I, restricts the dose to individuals in the unrestricted areas from radioactive materials in O gaseous airborne from the Fort Calhoun Station to:

During any calendar quarter s7.5 mrem to any organ and e During any calendar year 115 mrem to any organ The dose to an individual from radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases with half-lives greater than 8 days in airborne effluents released to unrestricted areas (See Part III, Figure 1) should be determined by the following expressions:

4 0 .

R7

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 85 OF 123 2.0 RADIOACTIVE EFFLUENT DOSE CALCULATIONS (Continued) 2.2 NOTE: In all cases, for releases of tritium, use the dispersion parameter for inhalation (x/Q).

A. Annual Organ Dose from External Irradiation from ,

Radioactivity Deposited on the Ground Plane !

1 A.1 The ground plane concentration of radionuclide, i, {

at distance r, in the sector at angle 0, with respect to the release point, may be determined by:

1

, g) , II.ox1022] (os (r,0)os]

[1-exp (-A f t )

3 ]

Where:

Ci - is the ground plane concentration of the radionuclide, i, at distance r, in .

the sector at angle 6, from the release point, in pCi/m 2, Qi -

is the annual release rate of radionuclide, i, to the atmosphere, in Ci/yr.

ts - is the time period over which the accumulation is evaluated, which is assumed to be 15 years (mid-point of plant operating life). Table 16 6 i (r,0) = is the annual average relative deposition of radionuclide, i, at distance r, in the sector at angle 0, considering depletion of the plume by deposition during transport, in m-2, Table 3 Ai = is the radiological decay constant for radionuclide, i, in yr'*.

2 1.0x10 = is the number of pCi per Ci O

R7

FORT CALHOUN STATION CHEMISTRY PROCEDURE CH-ODCM-0001 PAGE 86 OF 123 2.0 RADIOACTIVE EFFLUENT DOSE CALCULATIONS (Continued)

O 2.2 A.2 The annual organ dose is then calculated using the following equation: ,

Df(r,6) = 87 6 0 S,, Cf(r,6)DFGy 2-2

[

Where:

Ci(r,0) =

is the ground plane concentration of radionuclide, i, at2 distance r, in the sector at angle 0, in pCi/m .

DFG u =

is the open field ground plane dose conversion factor for organ, j, from radionucifde, i, in mram-m2 /pCi-hr. Table 7 l Dj(r,0) =

is the annual dose to the organ, j, at distance r, in the sector at angle 0, in mrem /yr.

Sr =

is the shielding factor that accounts for the dose reduction due to shielding provided by O residential structures during occupancy, dimensionless. Table 16

{

8760 =

is the number of hours in a year k

e O .

R7

FORT CALHOUN STATION CHEMISTRY PROCEDURE CH-ODCM-0001 l PAGE 87 OF 123 l 2.0 RADIOACTIVE EFFLUENT DOSE CALCULATIONS (Continued) 2.2 B.

Annual Dose from Inhalation of Radionuclides in Air B.1 The annual average airborne concentration of I

radionuclide, i, at distance r, in the sector at angle 6, with respect to the release point, may be determined as:

X3(r,0) = 3.17 x 10*Oj [X/0}"(r,0)

Where:

Qi =

is the annual release rate of radionuclide, i, to the atmosphere, in Ci/yr.

xi(r,0) =

is the annual average ground-level

- I concentration of radionuclide, 1, in air at distance r, in the sector at angle 6, in pCi/m'.

Ix/Q)D(r,0) =

l is the annual average atmosphere dispersion factor, in sec/m (see R.G.

1.111). This includes depletion (for i radiciodines and particulates) and radiological decay of the plume.

Table 3 3 .17x10' =

is the number of pCi/Ci divided by the

, number of sec/yr.

B.2 The annual dose associated with inhalation of all radionuclides to organ, j, of an individual in age group, a, is then:

Dfg(r,6) = R, x3 (r,0) DFA19 i=1 Where:

D^. ( r,0 ) =

is the annual dose to organ, j, of an individual in the age group, a, at distance r, in the sector at angle 0, due to inhalation, in mren/yr.

R. =

is the annual air intake for individuals in the age group, a, in m'/yr. Table 5 DFAu . =

is the inhalation dose factor for

' radionuclide, i, organ, j, and age group, a, in mrem /pCi. Tables 8-11 R7 l

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

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 88 OF 123 2.O RADIOACTIVE EFFLUENT DOSE CALCULATIONS (Continued) 2.2 C. Concentrations of Radionuclides in Foods and Vegetation from Atmospheric Releases C.1 Parameters for Calculating Concentrations in '

Forage, Produce, and Leafy Vegetables, excluding Carbon-14 and Tritium c[(r,0) = d,(r,8) 1 - eXP (-1,s C.) ] Bj,[1 - exp (-i c3) )'

r.1,, ,1, f

x <-x,e.)

Where:

CI(r,0) =

is the concentration of radionuclide, i, in and on vegetation at distance r, !

in the sector at angle 0, in pCi/kg. i d i (r,0) = is the deposition rate of radionuclide, i, at distance r, in the sector at angle 0, in pCi/m hr. 2 The deposition rate from the plume is defined by:

(Reg. Guide 1.109, Rev. 1, Page l'.109-26, Equa. C-6) d3 (r,8) = 1.1 x 10s((r,6) @

O Where:

d i (r,0) = is the deposition rate of ,

radionuclide, i. l 5 1 (r,0) = is the relative deposition of radionuclide, i, considering depletion and decay, in m-2 ( ,,,

Regulatory Guide 1.111). Table 3 1.1x10' = is the number of pCi/Ci (1012) d ided by the number of hours per year (8760). .

05 =

is the annual release rate of radionuclide, i, to the atmosphere, in Ci/yr.

R7

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 89 OF 123 2.0 RADIOACTIVE EFFLUENT DOSE CALCULATIONS (Continued) 2.2 For radiciodines, the model considers only the elemental fraction of the effluent:

di (r1 0) = s.s x 10' oi (r1 0) ot Where:

d t (r1 0) =

The deposition rate of radiciodine, i.

5.5 x 10' =

The number of pCi/Ci ( 10 **) divided by the number of hours per year (8760), then multiplied by the amount of radioiodine emissions considered to be nonelemental (0.5).

di (r, 0) =

The relative deposition of radiciodine, 1, considering depletion and decay, in m-2 Table 3.

Q1 =

The total (elemental and nonelemental) radiciodine, i, emission rate.

r =

is the fraction of deposited activity retained on crops, dimensionless. Table 16 Art =

is the effective removal rate constant for radionuclide, i, from crops, in hr-1 Art =A + A.

t X,= 0.0021/hr. Table 16

t. =

is the time period that crops are exposed to contamination during the growing season, in hours.

Table 16 Y, =

is the agricultural productivity (yield) in kg (wet weight)/m 2. Table 16 B,t

=

is the concentration factor for uptake of radionuclide, i, from soil by edible parts of crops, in pCi/ kg (wet weight) per pCi/kg dry soil. Table 4 At =

is the radiological decay constant of radionuclide, i, in hr-2

t. = is the period of time for which sediment or soil is exposed to the contaminated water, in hours (mid-point of plant life). Table 16 P =

is the effective " surface density" for soil, in kg (dry soil)/m 2. Table 16 th = is the holdup time that represents the time interval between harvest and consumption of the food, in hours. Table 16 R7

4 FORT CALHOUN STATION CH-ODOf-0001 CHEMISTRY PROCEDURE '

PAGE 90 OF 123 k

2.0 RADIOACTIVE EFFLUENT DOSE CALCULATIONS (Continued) 2.2 Different values for the parameters t., Y,, and ta, may be used 1

j to allow the use of the Equation for different purposes:

estimating concentrations in produce consumed by man; in leafy vegetables consumed by man; in forage consumed directly as i

pasture grass by dairy cows, beef cattle, or goats; and in forage consumed as stored feed by dairy cows, beef cattle or l goats. See Table 16 ,

i ?

C.2 Parameters for Calculating Radionuclide Concentration in l Milk, excluding Carbon-14 and Tritium l C.2.1 Parameters for Calculating the Concentration of Radionuclide, i, in the Animal's Feed (Milk Cow, Beef Cow, and Goat) l C[(r,0) = f,f,Cf(r,0) + (1 - f,) cf(r,0) + f,(1 - f,) Cf(r,0)

I -

J Where:

i T(r,0) -

is the concentration of radionuclide, i, in the

) animal's feed, in pCi/kg.

l T(r,0) =

is the concentration of

{ radionuclide, i, on pasture i

grass (calculated using 1

Equation C.2.1 with ta=0) , in

' l pCi/kg.

J T(r,0) -

is the concentration of radionuclide, 1, in stored i

feeds (calculated using j Equation C.2.1 with ta=90 days) , in pCi/kg.

=

f, is the fraction of the year that animals graze on pasture.

Table 16 f, - is the fraction of daily feed j that is pasture grass while the

! animal grazes on pasture.

Table 16 1O .

L R7 1

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 91 OF 123 2.0 RADIOACTIVE EFFLUENT DOSE CALCULATIONS (Continued) 2.2 C.2.2 Parameters for Calculating Radionuclide l Concentration in Cow and Goat Milk Cf(r,6) = F,Cf(r,6) O . fexp (-A jef)

Where:

Cdr,0) =

is the concentration of radionuclide, i, in milk, in pCi/ liter.

q'(r,0 ) =

is the concentration of radionuclide, i, in the animal's feed, in pCi/kg.

F. = is the average fraction of the animal's daily intake of radionuclide, i, which appears in each liter of milk, in days / liter.

Table 4 Q, =

is the amount of feed consumed by the animal per day, in kg/ day.

Table 6 t, = is the average transport time of the radionuclide, i, from the feed to the milk and to the receptor (a value of 2 days is assumed) .

Table 16 Ai =

is the radiological decay constant of radionuclide, i, in days-*.

O R7

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 92 OF 123 2.0 RADIOACTIVE EFFLUENT DOSE CALCULATIONS (Continued) 2.2 C.3 Parameters for Calculating Radionuclide Concentration in Cow Meat, excluding Carbon-14 and Tritium (r,6) = F Cf(r,6) f 0,. er, (-Ag C f)

Where:

Cf(r,0) =

is the concentration of radionuclide, i, in meat, in pCi/ liter.

Fr = is the average fraction of the animal's daily intake of radionuclide, i, which appears in each kilogram of flesh, in days / kilogram. Table 4 t, =

is the average time from slaughter to consumption. Table 16 O

O .

R7

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 93 OF 123 2.0 RADIOACTIVE EFFLUENT DOSE CALCULATIONS (Continued) 2.2 C.4 Parameters for Calculating the Carbon-14 Concentrations in Vegetation Carbon-14 is assumed to be released in oxide form (CO or CO2 ) . The concentration of Carbon-14 in vegetation is calculated by assuming that its ratio to the natural carbon in vegetation is the same as the ratio of Carbon-14 to natural carbon in the atmosphere surrounding the vegetation. Also, in the case of intermittent releases, such as from gaseous waste decay tanks, the parameter p is employed to account for the fractional equilibrium ratio achieved. The parameter, p, is defined as the ratio of the total annual release time (for Carbon-14 atmospheric releases) to the total annual time during which photosynthesis occurs (tak a. to be 4400 hrs), under the condition that the value of p should never exceed unity. For continuous Carbon-14 releases, p is taken to be unity. These considerations yield the following relationship:

C[4 (r,6) = 3.17 x 10 7pOz, [x/O] (r,6) 0.11/0.16

= 2.2 x 107 pO 2 ,[x/0) (r,6)

Where:

CI4 (r,0) -

is the concentration of Carbon-14 in vegetation grown at distance r, in the sector at angle 0, in pC1/kg.

Q1. - is the annual release rate of Carbon 14, in Ci/yr.

[x/Q] (r,0) - is the atmospheric dispersion factor, in sec/m'. Table 3 p - is the fractional equilibrium ratio, dimensionless. P-1 (Reg. Guide 1.109, Rev. 1, pg. 26).

0.11 - is the fraction of total plant mass that is natural carbon, dimensionless.

0.16 = is equal to the concentration of natural carbon in the atmosphere, in g/m'.

3.17x10 7 = is equal to 12

(1.0 x 10 pci/ci) (1.0 x 10 g/kg)

(3.15 x 10 sec/yr).

8 R7

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 94 OF 123 2.0 RADIOACTIVE EFFLUENT DOSE CALCULATIONS (Continued) i 2.2 C.5 Parameters for Calculating Tritium Concentrations in vegetation The concentration of tritium in vegetation is calculated from its concentration in the air surrounding the vegetation.

C[(r,6) = 3.17 x 107 0r[x/O] (r,6) (0.75) (0. 5/N)

= 1.2 x 107 0r[x/O] (r,9) /H Where:

1 CI(r,0) =

is the concentration of Tritium in !

vegetation grown at distance r, in the sector at angle 0, in pCi/kg. !

H = is the absolute humidity of the ,

atmosphere at distance r, in the :

sector at angle 0, in g/m' H=8 gm/kg. I Qr -

is the annual release rate of Tritium, in Ci/yr. 1 i

[x/Q)(r,0) =

is the atmospheric dispersion factor, I in sec/m . 3 Ta' ole 3 i 0.5 =

is the ratio of ti'.:ium concentration I in plant water to .:ritium

)

concentration in atmospheric water, '

dimensionless.

0.75 = is the fraction of total plant mass that is water, dimensionless.

O .

R7

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 95 OF 123 2.0 RADIOACTIVE EFFLUENT DOSE CALCULATIONS (Continued) 2.2 D. Annual Dose from Atmospherically Released Radionuclides in Foods D.1 The total annual dose to organ, j , of an individual in age group, a, resulting from ingestion of all radionuclides in produce, milk, and leafy vegetables l is given by:

i 1

ofsr.e> - Y ony [op,cre,e> . v; cia.e> . gepr.e> . @,chr.e>]

Where Dj. (r,0) -

is the annual dose to organ, j, of an individual in age group, a, from dietary intake of atmospherically l released radionuclides, in mrem /yr.

1 DFIo, -

is the dose conversion factor for the ingestion of radionuclide, i, organ, j, and age group, a, in mrem /pci.

Tables 12-15.

I U'. ,14, =

are the ingestion rates of produce (non-leafy vegetables, fruits, and grains); milk, meat, and leafy U5,U'.

vegetables, respectively for individuals in age group, a. Table 5.

Values of F, and f, are 0.76 and 1. 0, respectively.

O R7

I

\

! FORT CALHOUN STATION CH-0DCM-0001 !

CHEMISTRY PROCEDURE PAGE 96 OF 123 2.0 RADIOACTIVE EFFLUENT DOSE CALCULATIONS (Continued)

O

(_,) 2.2 D.1.1 Calculating the Ingested Dose from Leafy l

i and Non-Leafy (produce) Vegetation for i Radionuclide, i, to Each Organ, j, and Age l Group, a ofs,.e> . on,,. [c,41.e> . up,cpr.e)]

Mhare: !

Dj. (r,0) =

is the annual dose from ;

the ingestion of ;

radionuclide, i, to organ, i j, of an individual in age group, a, from dietary intake of atmospherically 1 released radionuclides in l vegetation, in mrem /yr.

1 DFIy . =

is the dose conversion ' l factor for the ingestion '

of radionuclide, i, organ, ;

j, and age group, a, '

in m'em/pci.

r Tables 12-15 1 i

Ui, U; - are the ingestion rates of ,

leafy vegetables and 1 produce (non-leafy vegetables, fruits, and grains), for individuals in age group, a, in kg/yr.

. Table 5 CI =

is the concentration of radionuclide, i, in and on leafy vegetation, in pCi/kg.

CI =

is the concentration of radionuclide, i, in and on produce, in pCi/kg.

R7

l FORT CALHOUN STATION CHE'4ISTRY PROCEDURE CH-CDQ4- 0001 PAGE 97 OF 123 2.0 R3DIOACTIVE EFFLUENT DOSE CALCULATIONS (Continued) 2.2 D.1.2 Calculation Determining the Ingested Dose from Cow Milk for Radionuclide, i, Organ, j, and Age Group, a.

o[,(r,0) -orz,[(@r,0))

Where:

Dj. (r,6) =

is the annual dose from 4

the ingestion of '

radionuclide, i, organ, j, i of an individual in age i group, a, from dietary intake of atmospherically t released radionuclides in '

cow milk, in mrem /yr.

l DFIu . =

is the dose conversion ,

1 factor for the ingestion l of radionuclide, i, organ, j, and age group, a, in mrem /pci. Tables 12-15 U7 = is the ingestion rate of cow milk for individuals 9 '

in age group, a, in t/yr.

Table 5 C7 =

is the radionuclide concentration in cow milk, in pCi/kg. Equation C.2.2 i

. O R7

FORT CALHOUN STATION CHEMISTRY PROCEDURE CH-ODO(-0001 PAGE 98 OF 123 2.O RADIOACTDrE EFFLUENT DOSE CALCULATIONS (Continued)

O 2.2 D.1.3 Calculation Determining the Ingested Dose from Meat for Radionuclide, i, to Organ, j, and Age Group, a.

op.e>.nn.g+.e>) u Where:

Dj (r,0) - is the annual dose from the ingestion of radionuclide, i, organ, j, of an individual in age group, a, from dietary intake of atmospherically released radionuclides in meat, in mrem /yr.

DFIo. = is the dose conversion factor for the ingestion of radionuclide, i, organ, j, and i

I age group, a, in mrem /pci.

Tables 12-15 Ui - is the ingestion rate of meat for individuals in age group, a in kg/yr. Table 5 Ci = is the radionuclide, i, concentration in meat, ,

in pCi/ kg. !

O .

R7

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 99 OF 123 TABLE 1 DOSE FACTORS FOR EXPOSURE TO A SEKI-INFINITE CLOUD OF NOBLE GASES Nuclide B-air *(DFd#

B- Skin * * (DFS. ) v-Air *(DFQ v- Bodv* * (DFBd i

KR-83m 2.88E-04 --

1.93E-05 7.56E-08 KR-85m 1.97E-03 1.46E-03 1.23E-03 1.17E-03 KR-85 1.95E-03 1.34E-03 1.72E-0$ 1.61E-05 KR-87 1.03E-02 9.73E-03 6.17E-03 5.92E-03 KR-88 2.93E-03 2.37E-03 1.52E-02 1.47E-02 KR-89 1.06E-02 1.01E-02 1.73E-02 1.66E-02 KR-90 7.83E-03 7.29E-03 1.63E-02 1.56E-02 Xe-131m 1.11E-03 4.76E-04 1.56E-04 9.15E-05 Xe-133m 1.48E-03 9.94E-04 3.27E-04 2.51E-04 Xe-133 1.05E-03 3.06E-04 3.53E-04 2.94E-04 Xe-135m 7.39E-04 7.11E-04 3.36E.03 3.12E-03 l

Xe-135 2.46E-03 1.86E-03 1.92E-03 1.81E-03 Xe-137 1.27E-02 1.22E-02 1.51E-03 1.42E-03 Xe-138 4.75E-03 4.13E-03 9.21E-03 8.83E-03 Ar-41 3.28E-03 2.69E-03 9.30E-03 8.84E-03 l

l

mrad-m 3 pCi-yr

- mrem-m' pCi-yr

- - 2.88E-04 - 2.88 x 10" R7

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

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 100 OF 123 TABLE 2

' BIOACCOMULATION FACTORS (pCi/kg per pCi/ liter)

FRESHWATER Element Fish Invertebrate H 9.0E-01 9.0E-01 C 4.6E+03 9.1E+03 NA 1.0E+02 2.0E+02 P 1.0E+05 2.0E+04 CR 2.OE+02 2.OE+03 MN 4.0E+02 9.0E+04 FE 1.0E+02 3.2E+03 CO 5.0E+01 2.0E+02 NI 1.0E+02 1.0E+02 CU 5.OE+01 4.OE+02 ZN 2.0E+03 1.0E+04 BR 4.2E+02 3.3E+02 RB 2.0E+03 1.0E+03 SR 3.0E+01 1.0E+02 Y 2.5E+01 1.0E+03 ZR 3.3E+00 6.7E+00 NB 3.0E+04 1.0E+02 MO 1.OE+01 1.OE+01 TC 1.5E+01 5.0E+00 RU 1.0E+01 3.0E+02 RH 1.OE+01 3.OB+02 TE 4.0E+02 6.1E+03 I 1.5E+01 5.0E+00 CS 2.0E+03 1.0E+03 BA 4.0E+00 2.0E+02 LA 2.5E+01 1.0E+03 CE 1.0E+00 1.0E+03 PR 2.5E+01 1.0E+03 ND 2.5E+01 1.0E+03 l

W 1.2E+03 1.0E+01 NP 1.0E+01 4.0E+02 R7

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 101 OF 123 TABLE 3 CONTROLLING LOCATIONS, PATHWAYS AND ATMOSPHERIC DISPERSION FOR DOSE CALCULATIONS Atmoseheric Discersion x/Q D/Q Controlling (X/Q (r,9) ) (6(r,6))

Location Pathway (s) __ Ace Groun (sec/m3) 3 (1/m)

Unrestricted Noble Gases N/A 5.0E-06 N/A Area Boundary Direct Exposure Unrestricted Inhalation Child 5.0E-06 Area Boundary N/A Unrestricted Gamma-Air N/A 5.0E-06 Area Boundary N/A {

Beta-Air i

Miller Farm

milk, ground Child 5.0E-06 1.6E-08 0.8 miles !

plane, meat, 1 SSW inhalation, and vegetation Site Liquid N/A Mixing 7.14 Discharge Ratio, M, M.U.D. Liquid N/A Mixing 30.8 Intake Ratio, M, Location is subject to change depending on the results of the Land Use survey performed annually in accordance with Part II, Section 5.4

. O R7

1 FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 102 OF 123 TABLE 4 STABLE ELEMENT TRANSFER DATA

) Bw F. (Cow) Fr !

Element Vea/ Soil Milk (d/A) MkA.t (d/ka) i H 4.8E+00 1.0E-02 1.2E-02 C 5.5E+00 1.2E-02 3.1E-02'

! Na 5.2E-02 4.0E-02 3.0E-02 l P 1.1E+00 2.5E-02 4.6E-02

)

Cr 2.5E-04 2.2E-03 2.4E-03

. Mn 2.9E-02 2.5E-04 8.0E-04 Fe 6.6E-04 1.2E-03 4.0E-02 Co l 9.4E-03 1.0E-03 1.3E-02

) Ni 1.9E-02 6.7E-03 5.3E-02

Cu 1.2E-01 1.4E-02 8.0E-03

Zn 4.0E-01 3.9E-02 3.0E-02

Rb 1.3E-01 3.0E-02 3.1E-02 i Sr 1.7E-02 8.0E-04 6.0E-04 l

Y 2.6E-03 1.0E-05 4.6E-03 f Zr 1.7E-04 5.0E-06 3.4E-02 j Nb 9.4E-03 2.5E-03 2.8E-01

Mo 1.2E-01 7.5E-03 8.0E-03 i Tc 2.5E-01 2.5E 4.0E-01

Ru 5.0E-02 1.0E-06 4.0E-01 Rh 1.3E+01 1.0E-02 1.5E-03 i( )

I Ag Te 1.5E-01 1.3E+00 5.0E-02 1.0E-03 1.7E-02 7.7E-02

. I 2.0E-02 6.0E-03 2.9E-03 j Cs 1.0E-03 1.2E-02 4.0E-03 1

Ba 5.0E-03 4.0E-04 3.2E-03

La 2.5E-03 5.0E-06 2.0E-04 j Ce 2.5E-03 1.0E-04 1.2E-03 Pr 2.5E-03 5.0E-06 4.7E-03 Nd 2.4E-03 5.0E-06 3.3E-03

, W 1.8E-02 5.0E-04 1.3E-03 j Np' 2.5E-03 5.0E-06 2.0E-04 ,

1 O .

R7

i FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 103 OF 123 l TABLE 5 RECOMMENDED VALUES FOR Un TO BE USED FOR THE MAXIMUM EXPOSED l INDIVIDUAL IN LIEU OF SITE SPECIFIC DATA 1 Pathway Infant Child Teen Adult Fruits, vegetables, &

grain (kg/yr) -

520 630 520 Ltafy vegetables (kg/yr) -

26 42 64 Milk (t/yr) 330 330 400 310 Meat & poultry (kg/yr) -

41 65 110 Fich (fresh or salt)

(kg/yr) -

6.9 16 21 4

Other Seafood (kg/yr) -

1.7 3.8 5 Drinking water (t/yr) 330 510 510 730 Shoreline recreation i (hr/yr) -

14 67 12

! Inhalation (m'/yr) 1400 3700 8000 8000 4

TABLE 6 ANIMAL CONSUMPTION RATES

)

Gr Qa 4

Feed or I'orage Water Animal [Ka/ day (wet weich)1 (t/ day) I

^

Milk Cow 50 60 Beef Cattle 50 50 Goats 6 8 O

R7

FORT CALHOUN STATION CHEMISTRY PROCEDURE CH-ODCM-0001 PAGE 104 OF 123 )

TABLE 7 q) Page 1 of 2 EXTERNAL DOSE FACTORS FOR STANDING ON CONTauTWATED GROUND (ares /hr par pci/m*) {

ELEMENT TOTAL BODY SKIN H-3 0.0 0.0 C-14 0.0 0.0 NA-24 2.50E-08 2.90E-08 P-32 0.0 0.0 Cr-51 2.20E-10 2.60E-10 l

Mn-54 5.80E-09 6.80E-09 Mn-56 1.10E-08 1.30E-08 Fe-55 0.0 0.0 Fe-59 8.00E-09 9.40E-09 Co-58 7.00E-09 8.20E-09 Co-60 1.70E-08 2.00E-08 Ni-63 0.0 0.0 Nr-65 3.70E-09 4.30E-09 Cu-64 1.50E-09 1.70E-09 Zn-65 4.00E-09 4.60E-09 Zn-69 0.0 0.0 Br-83 6.40E-11 9.30E-11 Br-84 1.20E-08 1.40E-08 Br-85 0.0 0.0 Rb-86 6.30E-10 7.20E-10 Rb-88 3.50E-09 4.00E-09 Rb-89 1.50E-08 1.80E-08 Sr-89 5.60E-13 6.50E-13 Sr-91 7.10E-09 8.30E-09 Sr-92 9.00E-09 1.00E-08 Y-90 2.20E-12 2.60E-12 i Y-91M .3.80E-09 4.40E-09 I Y-91 2.40E-11 2.70E-11 Y-92 1.60E-09 1.90E-09 Y-93 5.70E-10 7.80E-10 Zr-95 5.00E-09 5.80E-09 Zr-97 5.50E-09 6.40E-09 Nb-95 5.10E-09 6.00E-09 Mo-99 1.90E-09 2.20E-09 Tc-99M 9.60E-10 1.10E-09 Tc-101 2.70E-09 -

3.00E-09 Ru-103 3.60E-09 4.20E-09 Ru-105 4.50E-09 5.10E-09 Ru-106 1.50E-09 1.80E-09 Ag-110M 1.80E-08 2.10E-08 Te-125M 3.50E-11 4.80E-11 Te-127M 1.10E-12 1.30E-12 Te-127 1.00E-11 1.10E-11 Te-129M 7.70E-10 9.00E-10 Te-129 7.10E-10 8.40E-10 Te-131M 8.40E-09 9.90E-09 Te-131 2.20E-09 2.60E-06 Te-132 1.70E-09 2.00E-09 I-130' 1.40E-08 1.70E-08 R7

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 105 OF 123 TABLE 7 (Continued)

Page 2 of 2 EXTERNAL DOSE FACTORS FOR STANDING ON 2CONTAMINATED GROUND (arem/hr per pCi/m )

MmWT TOTAL BODY SKIN I-131 2.80E-09 3.40E-09 I-132 1.70E-08 2.00E-08 I-133 3.70E-09 4.50E-09 I-134 1.60E-08 1.90E-08

I-135 1.20E-08 1.40E-08 Cs-134 1.20E-08 1.40E-08 Cs-136 1.50E-08 1.70E-08 Cs-137 4.20E-09 4.90E-09 Cs-138 2.10E-08 2.40E-08 Ba-139 2.40E-09 2.70E-09 Ba-140 2.10E-09 2.40E-09

! Ba-141 4.30E-09 4.90E-09 Ba-142 7.90E-09 9.00E-09 La-140 1.50E-08 1.70E-08 La-142 1.50E-08 1.80E-08 Ce-141 5.50E-10 6.20E-10 i' Ce-143 2.20E-09 2.50E-09 Ce-144 3.20E-10 3.70E-10 Pr-143 0.0 0.0 Pr-144 2.00E-10 2.30E-10 Nd-147 1.00E-09 1.20E-09 W-187 3.10E-09 3.60E-09 Np-239 9.50E-10 3.10E-09 l

. O R7

f

~ FORT CALHOUN STATION CHEMISTRY PROCEDURE CH-ODCM-0001 PAGE 106 OF 123 TABLE 8 O N m 2 TION DOSE FACTORS FOR ADULT (arem per pCi Inhaled)

Page 1 of 2 Nuclide Bone Liver T. Body Thyroid Kidnav Luna GI-LLI H 3 -

1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 C 14 2.27E-06 4.26E-07 4.26E-07 NA 24 4.26E-07 4.26E-07 4.26E-07 4.26E-07 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 .1.28E-06 1.28E-06 P 32 1.65E-04 9.64E-06 6.26E-06 -

CR 51 -

1.25E-08 1.08E-05 MN 54 7.44E-09 2.85E-09 1.80E-06 4.15E-07 4.95E-06 7.87E-07 -

1.23E-06 1.75E-04 9.67E-06 MN 56 -

1.55E-10 2.29E-11 FE 55 3.07E-06 1.63E-10 1.18E-06 2.53E-06 2.12E-06 4.93E-07 -

9.01E-06 FE 59 1.47E-06 3.47E-06 1.32E-06 7.54E-07 1.27E-04 2.35E-05 CO 58 -

1.98E-07 2.59E-07 CO 60 1.44E-06 1.16E-04 1.33E-05 1.85E-06 - -

7.46E-04 3.56E-05 NI 63 5.40E-05 3.93E-06 1.81E-06 ,

2.23E-05 1.67E-06 l NI 65 1.92E-10 2.62E-11 1.14E-11 CU 64 1.83E-10 7.00E-07 1.54E-06 7.69E-11 -

5.78E-10 8.48E-07 6.12E-06 ZN 65 4.05E-06 1.29E-05 5.82E-06 -

8.62E-06 1.08E-04 6.68E-06 J 69 4.23E-12 8.14E-12 5.65E-13 -

5.27E-12 1.15E-07 2.04E-0, uA 83 - -

3.01E-08 -

BR 84 - -

3.91E-08 -

2.90E-08 i 2.05E-13 BR 85 - -

1.60E-09 -

RB 86 LT E-24 1.69E-05 7.37E-06 -

RB 88 -

4.84E-08 2.41E-08 -

2.08E-06 4.18E-19 RB 89 -

3.20E-08 2.12E-08 -

SR 89 3.80E-05 -

1.09E-06 1.16E-21 SR 90 1.24E-02 1.75E-04 4.37E-05 7.62E-04 - -

1.20E-03 9.02E-05 SR 91 7.74E-09 -

3.13E-10 SR 92 8.43E-10 4.56E-06 2.39E-05 3.64E-11 - -

2.06E-06 5.38E-06 Y 90 2.61E-07 -

7.01E-09 - -

2.12E-05 6.32E-05

.Y 91M 3.26E-11 -

1.27E-12 Y, 91 5.78E-05 -

1.553-06 2.40E-07. 1.66E-10 Y- 92 1.29E-09 2.13E-04 4.81E-05 3.77E-11 - -

1.96E-06 9.19E-06 Y 93 1.18E-08 -

3.26E-10 ZR 95 6.06E-06 5.27E-05 1.34E-05 4.30E-06 2.91E-06 -

6.77E-06 2.21E-04 1.88E-05 ZR 97 1.21E-08 2.45E-09 1.13E-09 3.71E-09 9.84E-06 6.54E-05 NB 95 1.76E-06 9.77E-07 5.26E-07 9.67E-07 6.31E-05 1.30E-r

{~h99 1.51E-08 2.87E-09 -

3.64E-08 1.14E-05 3.10E-t s,j99M 1.29E-13 3.64E-13 4.63E-12 5.52E-12 9.55E-08 5.20E-07 4

R7

- - ,_. _4

1 FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 107 OF 123 TABLE 8 INHALATION DOSE FACTORS FOR ADULT (arem per pCi Inhaled)

Page 2 of Nuclide Bone __ Liver. T. Body Thyroid Kidney Lunc GI-LLI TC 101 5.22E-15 7.52E-15 7.38E-14 -

1.35E-13 4.99E-08 1.36E-21 1 RU 103 1.91E-07 -

8.23E-08 -

7.29E-07 6.31E-05 1.38E-05 RU 105 9.88E-11 -

3.89E-11 -

1.27E-10 1.37E-06 6.02E-06 RU 106 8.64E-06 -

1.09E-06 -

1.67E-05 1.17E-03 1.14E-04 AG 110M 1.35E-06 1.25E-06 7.43E-07 -

2.46E-06 5.79E-04 3.78E-05 TE 125M 4.27E-07 1.98E-07 5.84E-08 1.31E-07 1.55E-06 3.92E-05 8.83E-06 TE 127M 1.5PE-06 7.21E-07 1.96E-07 4.11B-07 5.72E-06 1.20E-04 1.87E-05 TE 127 1.75E-10 8.03E-11 3.87E-11 1.32E-10 6.37E-10 8.14E-07 7.17E-06 TE 129M 1.22E-06 5.84E-07 1.98E-07 4.30E-07 4.57E-06 1.45E-04 4.79E-05 TE 129 6.22E-12 2.99E-12 1.55E-12 4.87E-12 2.34E-11 2.42E-07 1.96E-08 TE 131M 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1.82E-05 6.95E-05 TE 131 1.39E-12 7.44E-13 4.49E-13 1,17E-12 5.46E-12 1.74E-07 2.30E-09 TE 132 3.25E-08 2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 6.37E-05 I 130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61E-06 -

9.61E-07 I 131 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 -

7.85E-07

_ 132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 -

5.08E-08 I 133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 -

1.11E-0 l I 134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 -

1.26E-1 I 135 3.35E-07 8.73E-07 3.21E-07 5.60E-05 1.39E-06 -

6.56E-07 CS 134 4.66E-05 1.06E-04 9.10E-05 -

3.59E-05 1.22E-05 1.30E-06 CS 136 4.88E-06 1.83E-05 1.38E-05 -

1.07E-05 1.50E-06 1.46E-06 CS 137 5.98E-05 7.76E-05 5.35E-05 -

2.78E-05 9.40E-06 1.05E-06 CS 138 4.14E-08 7.76E-08 4.05E-08 -

6.00E-08 6.07E-09 2.33E-13 BA 139 1.17E-10 8.32E-14 3.42E-12 -

7.78E-14 4.70E-07 1.12E-07 BA 140 4.88E-06 6.13E-09 3.21E-07 -

2.09E-09 1.59E-04 2.73E-05 BA 141 1.25E-11 9.41E-15 4.20E-13 -

9.75E-15 2.422-07 1.45E-17 BA 142 3.29E-12 3.38E-15 2.07E-13 -

2.86E-15 1.49E-07 1.96E-26 LA 140 4.30E-08 2.17E-08 5.73E-09 - -

1.70E-05 5.73E-05 LA 142 8.54E-11 3.88E-11 9.65E-12 - -

7.91E-07 2.64E-07 CE 141 2.49E-06 1.69E-06 1.91E-07 -

7.'83E-07 4.52E-05 1.50E-05 CE 143 2.33E-08 1.72E-08 1.91E-09 -

7.60E 09 9.97E-06 2.83E-05 CE 144 4.29E-04 1.79E-04 2.30E-05 -

1.06E-04 9.72E-04 1.02E-04 PR 143 1.17E-06 4.69E-07 5.80E-08 -

2.70E-07 3.51E-05 2.50E-05 "R 144 3.76E-12 1.56E-12 1.91E-13 -

8.81E-13 1.27E-07 2.69E-18 147 6.59E-07 7.62E-07 4.56E-08 -

4.45E-07 2.76E-05 2.16E-05 w 187 1.06E-09 8.85E-10 3.10E-10 - -

3.63E-06 1.94E-0 NP 239 2.87E-08 2.82E-09 1.55E-09 -

8.75E-09 4.70E-06 1.49E-0 R7

FORT CALHOUN STATION CHEMISTRY PROCEDURE CH-ODCM-0001 PAGE 108 OF 123 TABLE 9 p) g n m.ATION DOSE FACTORS FOR TEINAGER (aram per pCi Inhaled) l Page 1 of 2 i Nuc1ide Bone Liver T. Body Thyroid Kidney Luno GI-LLI H 3 -

1.59E-07 1.59E-07 1.59E-07 C 14 1.59E-07 1.59E-07 1.59E-07 3.25E-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 NA 24 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 P 32 2.36E-04 1.37E-05 6.95E-06 - -

CR 51 -

1.16E-05 MN 54 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.75E-07 6.39E-06 1.05E-06 -

1.59E-06 2.48E-04 8.35E-06 MN 56 -

2.12E-10 3.15E-11 FE 55 4.18E-06 2.24E-10 1.90E-06 7.18E-06 i

2.98E-06 6.93E-07 - -

1.55E-05 7.99E-07 l

! FE 59 1.99E-06 4.62E-06 1.79E-06 i 1.91E-04 2.23E-05 l

CO 58 -

2.59E-07 3.47E-07 CO 60 1.68E-04 1.19E-05 1.89E-06 2.48E-06 - -

1.09E-03 3.24E-05 NI 63 7.25E-05 5.43E-06 2.47E-06 - -

3.84E-05 1.77E-06 !

N2 65 2.73E-10 3.66E-11 1.59E-11 CU 64 1.17E-06 4.59E-06 1 2.54E-10 4

1.06E-10 -

8.01E-10 1.39E-06 7.68E-06 ZN 65 4.82E-06 1.67E-05 7.80E-06 -

1.08E-05 d 1.55E-04 5.83E-06 7 69 6.04E-12 1.15E-11 8.07E-13 -

7.53E-12 1.98E-07 3 . 5 6E - (., .

J 83 - -

4.30E-08 - - -

LT E-24 BR 84 - -

5.41E-08 - - -

LT E-24 BR 85 - -

2.29E-09 RB 86 LT E-24 2.38E-05 1.05E-05 - - -

2.21E-06 RB 88 -

6.82E-08 3.40E-08 - - -

3.65E-15 4

RB 89 -

4.40E-08 2.91E-08 -

SR 89 4.22E-17 I 5.43E-05 -

1.56E-06 -

3.02E-04

^

SR 90 4.64E-05 1.35E-02 -

8.35E-04 2.06E-03 2

9.56E-05 SR 91 1.10E-08 -

4.39E-10 -

7.59E-06 I SR 92 3.24E-05 1.19E-09 -

5.08E-11 - -

3.43E-06 1.49E-05 t

Y 90 3.73E-07 -

1.00E-08 3.66E-05 6.99E-05

Y 91M 4.63E-11 -

1.77E-12 - -

4.00E-07 3.77E-09 Y 91 8.26E-05 -

2.21E-06 - -

3.67E-04 Y 92 5.11E-05 i 1.84E-09 -

5.36E-12 - -

3.35E-06 2.062-05 Y 93 1.69E-08 -

4.65E-10 - -

1.04E-05 7.24E-05 ZR 95 1.82E-05 5.73E-06 3.94E-06 -

8.42E-06 3.36E-04 1.86E-05 i ZR 97 1.72E-08 3.40E-09 1.57E-09 -

5.15E-09 1.62E-05 7.88E-05 NB 95 2.32E-06 1.29E-06 7.08E-07 -

1.25E-06 9.39E-05 1.21E-0~

/~ 99 -

2.11E-08 4.03E-09 -

5.14E-08 1.92E-05 3.36E-k 99M 1.73E-13 4.83E-13 6.24E-12 -

7.20E-12 1.44E-07 7.66E-07 R7

FORT CALHOUN STATION CHEMISTRY PROCEDURE CH-ODCM-0001 1 PAGE 109 OF 123 {

TABLE 9 ,

INHALATION DOSE FACTORS FOR TEENAGER l (arem per pCi Inhaled) i Page 2 of 2 ,

Nuclide Bone Liver T. Body Thyroid Kidney Lunc GI-LLI l TC 101 7.40E-15 1.05E-14 1.03E-13 RU 103 2.63E-07 1.90E-13 8.34E-08 1.09E-16 1.12E-07 -

9.29E-07 9.79E-05 1.36E-05 RU 105 1.40E-10 -

5.42E-11 -

1.76E-10 2.27E-06 1.13E-05 RU 106 1.23E-05 -

1.55E-06 AG 110M 2.38E-05 2.01E-03 1.20E-04 1.73E-06 1.64E-06 9.99E-07 -

3.13E-06 8.44E-04 3.41E-05 l

TE 125M 6.10E-07 2.80E-07 8.34E-08 1.75E-07 l 6.70E-05 9.38E-06 '

TE 127M 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 TE 127 2.07E-04 1.99E-05 2.51E-10 1.14E-10 5.52E-11 1.77E-10 9.10E-10 1.40E-06 1.01E-05 TE 129M 1.74E-06 8.23E-07 2.81E-07 5.72E-07 6.49E-06 l 2.47E-04 5.06E-05 !

TE 129 8.87E-12 4.22E-12 2.20E-12 6.485-12 3.32E-11 TE 131M 1.23E-08 7.51E-09 4.12E-07 2.02E-07 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05 TE 131 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 2.92E-07 1.89E-09 ;

TE 132 4.50E-08 3.63E-08 2.74E-08 3.07E-08 i 130 2.44E-07 5.61E-05 5.79E-05 '

I 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 -

1.14E-06 I 131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 -

8.11E-07

)

- 132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 133 1.59E- I I 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 -

1.29E-0 j I 134 1.11E-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 -

2.55E-09 I 135 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 CS 134 6.28E-05 8.69E-07 1.41E-04 6.86E-05 -

4.69E-05 1.83E-05 1.22E-06 CS 136 6.44E-06 2.42E-05 1.71E-05 -

1.38E-05 2.22E-06 1.36E-06 CS 137 8.38E-05 1.06E-04 3.89E-05 -

3.80E-05 CS 138 1.51E-05 1.06E-06 5.82E-08 1.07E-07 5.58E-08 -

8.28E-08 9.84E-09 3.38E-11 BA 139 1.67E-10 1.18E-13 4.87E-12 -

1.11E-13 8.08E-07 8.06E-07 BA 140 6.84E-06 8.38E-09 4.40E-07 2.85E-09 BA 141 2.54E-04 2.86E-05 i 1.78E-11 1.32E-14 5.93E-13 -

1.23E-14 4.11E-07 9.33E-14 BA 142 4.62E-12 4.63E-15 2.84E-13 3.92E-15 2.39E-07 5.99E-20 LA 140 5.99E-08 2.95E-08 7.82E-09 I

LA 142 2.68E-05 6.09E-05 1.20E-10 5.31E-11 1.32E-11 - -

1.27E-06 1.50E-06 CE 141 3.55E-06 2.37E-06 2.71E-07 -

1.11E-06 7.67E-05 1.58E-05 CE 143 3.32E-08 2.42E-08 2.70E-09 CE 144 1.08E-08 1.63E-05 3.19E-05 6.11E-04 2.53E-04 3.28E-05 -

1.51E-04 1.67E-03 1.08E-04 PR 143 1.67E-06 6.64E-07 8.28E-08 -

3.86E-07 6.04E-05 2.67E-05 "R 144 5.37E-12 2.20E-12 2.72E-13 -

1.26E-12 2.19E-07 2.94E-14 147 9.83E-07 1.07E-06 6.41E-08 W 187 6.28E-07 4.65E-05 2.28E-0 1.50E-09 1.22E-09 4.29E-10 - -

5.92E-06 2.21E-0; NP 23' 9 4.23E-08 3.99E-09 2.21E-09 -

1.25E-08 8.11E-06 1.65E-05 R7

i l

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 110 OF 123 TABLE 10 INEALATION DOSE FACTORS FOR CHILD (aram per pCi Tnhaled)

Page 1 of 2 Nuclide Bone Liver T. Body Thyroid Kidney Luno GI-LLI H 3 -

3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 C 14 9.70E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 NA 24 4.35E-06 4.35E-06 4.35E-06. 4.35E-06 4.35E-06 4.35E-06 4.35E-06 P 32 7.04E-04 3.09E-05 2.67E-05 - -

CR 51 1.14E-05 4.17E-08 6.57E-09 2.31E-08 4.59E-06 2.93E-07 MN 54 -

1.16E-05 2.57E-06 -

2.71E-06 4.26E-04 6.19E-06 MN 56 -

4.48E-10 8.43E-11 FE 55 4.52E-10 3.55E-06 3.33E-05 6.80E-06 1.28E-05 2.10E-06 - -

3.00E-05 FE 59 7.75E-07 l 5.59E-06 9.04E-06 4.51E-06 - -

3.43E-04 1.91E-05 CO 58 -

4.79E-07 8.55E-07 CO 60 2.99E-04 9.29E-06 3.55E-06 6.12E-06 - -

1.91E-03 2.60E-05 i

NI 63 2.22E-04 1.25E-05 7.56E-06 - -

7.43E-05 1.71E-06 NI 65 8.08E-10 7.99E-11 4.44E-11 CU 64 2.21E-06 2.27E-05 5.39E-10 2.90E-10 -

1.63E-09 2.59E-06 9.92E-06 l ZN 65 1.15E-05 3.06E-05 1.90E-05 1.93E-05 2.69E-04 4.41E-06~

69 1.81E-11 2.61E-11 2.41E-12 -

1.58E-11 3.84E-07 BR 83 2.75E-L.

1.28E-07 - - -

LT E-24 BR 84 - -

1.48E-07 LT E-24 BR 85 - -

6.84E-09 LT RB 86 E-24 5.36E-05 3.09E-05 - - -

2.16E-06 RB 88 -

1.52E-07 9.90E-08 - - -

4.66E-09 RB 89 -

9.33E-08 7.85E-08 SR 89 1.62E-04 5.11E-10 4.66E-06 - -

5.83E-04 4.52E-05 SR 90 2.73E-02 -

1.74E-03 3.99E-03 9.28E-05 SR 91 3.28E-08 -

1.24E-09 - -

1.44E-05 SR 92 4.70E-05 3.54E-09 -

1.42E-10 - -

6.49E-06 6.55E-05 Y 90 1.11E-06 -

2.99E-08 - -

7.07E-05 7.24E-05 Y 91M 1.37E-10 -

4.98E-12 - -

7.60E-07 4.64E-07 Y 91 2.47E-04 -

6.59E-06 7.10E-04 Y 92 5.50E-09 4.97E-05 1.57E-10 - -

6.46E-06 6.46E-05 Y 93 5.04E-08 ZR 95 1.38E-09 - -

2.01E-05 1.05E-04 5.13E-05 1.13E-05 1.00E-05 -

1.61E-05 6.038-04 1.65E-05 ZR 97 5.07E-08 7.34E-09 4.32E-09 -

1.05E-08 3.06E-05 9.49E-05 95 6.35E-06 2.48E-06 1.77E-06 -

2.33E-06 1.66E-04 1.00E-0" 4.66E-08 499 1.15E-08 3.66E-05 1.06E-07 3.42E .

99M 4.81E-13 9.41E-13 1.56E-11 -

1.37E-11 2.57E-07 1.30E-06 R7

a FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 111 OF 123 TABLE 10 4 INHALATION DOSE FACTORS FOR CHILD I (arem per pCi Inhaled)

Page 2 of Nuclide Bone Liver T. Body Thyroid Kidney Luna GI-LLI TC 101 2.19E-14 2.30E-14 2.91E-13 -

3.92E-13 1.58E-07 4.41E-09 l

RU 103 7.55E-07 -

2.90E-07 -

1.90E-06 1.79E-04 1.21E-05 l RU 105 4.13E-10 -

1.50E-10 -

3.63E-10 4.30E'-06 2.69E-05 RU 106 3.68E-05 -

4.57E-06 -

4.97E-05 3.87E-03 1.16E-04 AG 110M 4.56E-06 3.08E-06 2.47E-06 -

5.74E-06 1.48E-03 2.71E-05 TE 125M 1.82E-06 6.29E-07 2.47E-07 5.20E-07 -

1.29E-04 9.13E-06 TE 127M 6.72E-06 2.31E-06 8.16E-07 1.64E-06 1.72E-05 4.00E-04 1.93E-05 TE 127 7.49E-10 2.57E-10 1.65E-10 5.30E-10 1.91E-09 2.71E-06 1.52E-05 TE 129M 5.19E-06 1.85E-06 8.22E-07 1.71E-06 1.36E-05 4.76E-04 4.91E-05 TE 129 2.64E-11 9.45E-12 6.44E-12 1.93E-11 6.94E-11 7.93E-07 6.89E-06 TE 131M 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05 8.32E-05 TE 131 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-11 5.55E-07 3.60E-07 TE 132 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-04 3.72E-05 I 130 2.21E-06 4.43E-06 2.28E-06 4.99E-04 6.61E-06 -

1.38E-06 I 131 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 -

7.68E-07

_ 132 5.72E-07 1.10E-06 5.07E-07 5.23E-05 1.69E-06 -

8.65E-07 I 133 4.48E-06 5.49E-06 2.08E-06 1.04E-03 9.13E-06 -

1.48E-0 I 134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 -

2.58E- i

[

I 135 1.33E-06 2.36E-06 1.12E-06 2.14E-04 3.62E-06 -

1.20E-06 CS 134 1.76E-04 2.74E-04 6.07E-05 -

8.93E-05 3.27E-05 1.04E-06 CS 136 1.76E-05 4.62E-05 3.14E-05 -

2.58E-05 3.93E-06 1.13E-06 CS 137 2.45E-04 2.23E-04 3.47E-05 -

7.63E-05 2.81E-05 9.78E-07 CS 138 1.71E-07 2.27E-07 1.50E-07 -

1.68E-07 1.84E-08 7.29B-08 BA 139 4.98E-10 2.66E-13 1.45E-11 -

2.33E-13 1.56E-06 1.56E-05 BA 140 2.00E-05 3.75E-08 1.17E-06 -

5.71E-09 4.71E-04 2.75E-05 BA 141 5.29E-11 2.95E-14 1.72E-12 -

2.56E-14 7.89E-07 7.44E-08 BA 142 1.35E-11 9.73E-15 7.54E-13 -

7.87E-15 4.44E-07 7.41E-10 LA 140 1.74E-07 6.08E-08 2.04E-08 - -

4.94E-05 6.10E-05 LA 142 3.50E-10 1.11E-10 3.49E-11 - -

2.35E-06 2.05E-05 CE 141 1.06E-05 5.28E-06 7.83E-07 -

2.31E-06 1.47E-04 1.53E-05 CE 143 9.89E-08 5.37E-08 7.77E-09 -

2.26E-08 3.12E-05 3.44E-05 CE 144 1.83E-03 5.72E-04 9.77E-05 -

3.17E-04 3.23E-03 1.05E-04 PR 143 4.99E-06 1.50E-06 2.47E-07 -

8.11E-07 1.17E-04 2.63E-05 "R 144 1.61E-11 4.99E-12 8.10E-13 -

2.64E-12 4.23E-07 5.32E-08 147 2.92E-06 2.36E-06 1.84E-07 -

1.30E-06 8.87E-05 2.22E-05 W 187 4.41E-09 2.61E-09 1.17E-09 - -

1.11E-05 2.46E-0 NP 239 1.26E-07 9.04E-09 6.35E-09 -

2.63E-08 1.57E-05 1.73E-0 R7

FORT CALHOUN STATION CH-ODCM-0001 :

CHEMISTRY PROCEDURE PAGE 112 OF 123 TABLE 11 r e m TICK DOSE FACTORS FOR INFANT O (aram per pCi Inhaled)

Page 1 of 2 Nuclide Bone Liver T. Body Thyroid Kidnav Luna GI-LLI H 3 -

4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 C 14 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 I NA 24 7.54E-06 7.54E-06 7.54E-06. 7.54E-06 7.54E-06 7.54E-06 7.54E-06 P 32 1.45E-03 8.03E-05 5.53E-05 - - -

1.15E-05 CR 51 - -

6.39E-08 4.11E-08 9.45E-09 9.17E-06 2.55E-07 MN 54 -

1.81E-05 3.56E-06, -

3.56E-06 7.14E-04 5.04E-06 MN 56 -

1.10E-09 1.58E-10 -

7.86E-10 '8.95E-06 5.12E-05 FE 55 1.41E-05 8.39E-06 2.38E-06 - -

6.21E-05 7.82E-07 FE 59 9.69E-06 1.68E-05 6.77E-06 - -

7.25E-04 1.77E-05 CO 58 -

8.71E-07 1.30E-06 - -

5.55E-04 7.95E-06 CO 60 -

5.73E-06 8.41E-06 - -

3.22E-03 2.28E-05 NI 63 2.42E-04 1.46E-05 8.29E-06 - -

1.49E-04 1.73E-06 NI 65 1.71E-09 2.03E-10 8.79E-11 - -

5.80E-06 3.58E-05 CU 64 -

1.34E-09 5.53E-10 -

2.84E-09 6.64E-06 1.07E-05 ZN 65 1.38E-05 4.47E-05 2.22E-05 -

2.32E-05 4.62E-04 3.67E-05 ff69

% .1 83 3.85E-11 6.91E-11 5.13E-12 2.72E-07 2.87E-11 1.05E-06 9.44E s LT E-24 BR 84 - -

2.86E-07 - - -

LT E-24 BR 85 - -

1.46E-08 - - -

LT E-24 RB 86 -

1.36E-04 6.30E-05 - - -

2.17E-06 RB 88 -

3.98E-07 2.05E-07 - - -

2.42E-07 ;

RB 89 -

2.29E-07 1.47E-07 - - -

4.87E-08 SR 89 2.84E-04 -

8.15E-06 - -

1.45E-03 4.57E-05 SR 90 2.92E-02 -

1.85E-03 - -

8.03E-03 9.36E-05 SR 91 6.83E-08 -

2.47E-09 - -

3.76E-05 5.24E-05 SR 92 7.50E-09 -

2.79E-10 - -

1.70E-05 1.00E-.04 Y 90 2.35E-06 -

6.30E-08 -- -

1.92E-04 7.43E-05 Y 91M 2.91E-10 -

9.90E-12 - -

1.99E-06 1.68E-06 Y 91 4.20E-04 -

1.12E-05 - -

1.75E-03 5.02E-05 Y 92 1.17E-08 -

3.29E-10 - -

1.75E-05 9.04E-05 Y 93 1.07E-07 -

2.91E-09 - -

5.46E-05 1.19E-04 ZR.95 8.24E-05 1. 99 E- 05 1.45E-05 -

2.22E-05 1.252-03 1.55E-05 ZR 97 1.07E-07 1.83E-08 8.36E-09 -

1.85E-08 7.88E-05 1.00E-04 i NB 95 1.12E-05 4.50M-06 2.70E-06 -

3.37E-06 3.42E-04 9.05E-O' 1.15E-07 2.31E-08 -

1.89E-07 9.63E-05 3.48E-O 99 99M 9.98E-13 2.06E-12 2.66E-11 -

2.22E-11 5.79E-07 1.45E-Oe R7

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 113 OF 123 TABLE 11 INHALATION DOSE PACTORS FOR INFANT (arem per pCi Inhaled)

Page 2 of 2 Nuclide Bone Liver T. Body Thyroid Kidney Luno GI-LLI TC 101 4.65E-14 5.88E-14 5.80E-13 RU 103 6.99E-13 4.17E-07 6.03E-07 1.44E-06 -

4.85E-07 3.03E-06 RU 105 8.74E-10 3.94E-04 1.15E-05 2.93E-10 -

6.42E-10 1.12E-05 3.46E-05 RU 106 6.20E-05 -

7.77E-06 7.61E-05 AG 110M 8.26E-03 1.17E-04 7.13E-06 5.16E-06 3.57E-06 -

7.80E-06 2.62E-03 2.36E-05 TE 125M 3.40E-06 1.42E-06 4.70E-07 1.16E-06 -

3.19E-04 9.22E-06 TE 127M 1.19E-05 4.93E-06 1.48E-06 3.48E-06 2.68B-05 9.37E-04 1.95E-05 TE 127 1.59E-09 6.81E-10 3.40E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 TE 129M 1.01E-05 4.35E-06 1.59E-06 )

3.91E-06 2.27E-05 1.20E-03 4.93E-05 i TE 129 5.63E-11 2.48E-11 1.34E-11 4.82E-11 1.25E-10 2.14E-06 1.88E-05 15 131M 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.42E-04 TE 131 1.24E-11 5.87E-12 1.89E-07 8.51E-05 3.57E-12 1.13E-11 2.85E-11 1.47E-06 5.87E-06 '

TE 132 2.66E-07 1.69E-07 1.26E-07 130 1.99E-07 7.39E-07 2.43E-04 3.15E-05 I 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 -

1.42E-06 i

I 131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 -

7.56E-07 132 1.21E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 133 1.36E-I 9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 -

1.54E-0 I 134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 -

9.21E-07 I 135 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 CS 134 1.31E-06 2.83E-04 5.02E-04 5.32E-05 -

1.36E-04 5.69E-05 9.53E-07

.CS 136 3.45E-05 9.61E-05 3.78E-05 -

4.03E-05 8.40E-06 1.02E-06 CS 137 3.92E-04 4.37E-04 3.25E-05 -

1.23E-04 5.09E-05 CS 138 9.53E-07 3.61E-07 5.58E-07 2.84E-07 -

2.93E-07 4.67E-08 BA 139 6.26E-07 1.06E-09 7.03E-13 3.07E-11 -

4.23E-13 4.25E-06 3.64E-05 BA 140 4.00E-05 4.00E-08 2.07E-06 -

9.59E-09 1.14E-03 BA 141 2.74E-05 1.12E-10 7.70E-14 3.55E-12 -

4.64E-14 2.12E-06 BA 142 3.39E-06 2.84E-11 2.36E-14 1.40E-12 -

1.36E-14 1.11E-06 4.95E-07 LA 140 3.61E-07 1.43E-07 3.68E-08 -

LA 142 1.20E-04 6.06E-05 7.36E-10 2.69E-10 6.46E-11 - -

5.87E-06 4.25E-05 CE 141 1.98E-05 1.19E-05 1.42E-06 -

3.75E-06 3.69E-04 1.54E-05 CE 143 2.09E-07 1.38E-07 1.58E-08 -

4.03E-08 8.30E-05 CE 144 3.55E-05 2.28E-03 8.65E-04 1.26E-04 -

3.84E-04 7.03E-03 1.06E-04 PR 143 1.00E-05 3.74E-06 4.99E-07 -

1.41E-06 3.09E-04 2.66E-05 "R 144 3.42E-11 1.32E-11 1.72E-12 -

4.80E-12 1.15E-06 3.06E-06 147 5.67E-06 5.81E-06 3.57E-07 -

2.25E-06 2.30E-04 187 2.23E-0 w 9.26E-09 6.44E-09 2.23E-09 - -

2.83E-05 2.54E-0_

NP 239 2.65E-07 2.37E-08 1.34E-08 -

4.73E-08 4.25E-05 1.78E-05 R7

FORT CALHOUN STATION CH-ODCM-0001 !

CHEMISTRY PROCEDURE PAGE 114 OF 123 TABLE 12

/^) INGESTION DOSE FACTORS FOR ADULT C) (arem per pCi Ingested) l l

Page 1 of 2 i Nuclide. Bone Liver T. Body Thyroid Kidney Lunct GI-LLI H 3 -

1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.053-07 1.05E-07 C 14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 NA 24 5.68E-07 5.68E-07 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 P 32 1.93E-04 1.20E-05 7.46E-06 - -

CR 51 -

2.17E-05 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 MN 54 -

4.57E-06 8.72E-07 -

1.36E-06 -

1.40E-05 MN 56 -

1.15E-07 2.04E-08 FE 55 1.46E-07 -

3.67E-06 2.75E-06 1.90E-06 4.43E-07 - -

1.06E-06 1.09E-06 FE 59 4.34E-06 1.02E-05 3.91E-06 2.85E-06 3.40E-05 1

CO 58 -

7.45E-07 1.67E-06 - -

CO 60 1.51E-05 2.14E-06 4.72E-06 - - -

4.02E-05 NI 63 1.30E-04 9.01E-06 4.36E-06 - - -

1.88E-06 NI 65 5.28E-07 6.86E-08 3.13E-08 - - -

1.74E-06 CU 64 -

8.33E-08 3.91E-08 ZN 65 4.84E-06 2.10E-07 -

7.10E-06 1.54E-05 6.96E-06 -

1.03E-05 -

9.70E-06 69 1.03E 08 1.97E-08 1.37E-09 -

1.28E-08 R 83 2.96E u 4.02E-08 - - -

5.79E-08 BR 84 - -

5.21E-08 - - -

4.09E-13 BR 85 - -

2.14E-09 - - -

LT E-24 RB 86 -

2.11E-05 9.83E-06 - - -

4.16E-06 RB 88 -

6.05E-08 3.21E-08 - - -

8.36E-19 RB 89 -

4.01E-08 2.82E-08 - - -

2.33E-21 SR 89 3.08E-04 -

8.84E-06 - - -

4.94E-05 SR 90 7.58E-03 -

1.86E-03 - - -

2.19E-04 SR 91 5.67E-06 -

2.29E-07 - - -

2.70E-05 SR 92 2.15E-06 -

9.30E-08 - - -

4.26E-05 Y 90 9.62E-09 -

2.58E-10 - - -

1.02E-04 j Y 91M 9.09E-11 -

3.52E-12 - - -

2.67E-10 Y 91 1.41E-07 -

3.77E-09 - - -

7.76E-05 Y 92 8.45E-10 -

2.47E-11 - - -

1.48E-05 Y 93 2.68E-09 -

7.40E-11 - - -

8.50E-05 ZR 95 3.04E-08 9.75E-09 6.60E-09 -

1.53E-08 -

3.09E-05 ZR 97 1.68E-09 3.39E-10 1.55E-10 -

5.12E-10 -

1.05E-04 95 6.22E-09 3.46E-09 1.86E-09 -

3.42E-09 -

2.10E o" 99 -

4.31E-06 8.20E-07 -

9.76E-06 -

9.99E-99M 2.47E-10 6.98E ,10 8.89E-09 -

1.06E-08 3.42E-10 4.13E-07 R7

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 115 OF 123 TABLE 12 INGESTION DOSE FACTORS FOR ADULT (mrem par pCi Ingested)

Page 2 of f Nuclide Bone Liver T. Body Thyroid .Kidngg_ Luno GI-LLI TC 101 2.54E-10 3.66E-10 3.59E-09 -

6.59E-09 1.87E-10 1.10E-21 RU 103 1.85E-07 -

7.97E-08 -

7.06E-07 -

2.16E-05 RU 105 1.54E-08 -

6.08E-09 -

1.99E-07 -

9.42E-06 RU 106 2.75E-06 -

3.48E-07 -

5.31E-06 -

1.78E-04 AG 110M 1.60E-07 1.48E-07 8.79E-08 -

2.91E-07 -

6.04E-05 TE 125M 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 -

1.07E-05 TE 127M 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 -

2.27E-05 TE 127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 -

8.68E-06 TE 129M 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 -

5.79E-05 TE 129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 -

2.37E-08 TE 131M 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 -

8.40E-OL TE 131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 -

2.79E-09 TE 132 2.52E-06 1.63E-06 1.53E-06 1.POE-06 1.57E-05 -

7.71E-05 I 130 7.56E-07 2.23E-06 8.80E-07 1 G-04 3.48E-06 -

1.92E-06 I 131 4.16E-06 5.95E-06 3.41E-06 1..jE-03 1.02E-05 -

1.57E-06

. 132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 -

1.02E-07 I 133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 -

2.22E-0 I 134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 -

2.51E-1 I 135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 -

1.31E-06 CS 134 6.22E-05 1.48E-04 1.21E-04 -

4.79E-05 1.59E-05 2.59E-06 CS 136 6.51E-06 2.57E-05 1.85E-05 -

1.43E-05 1.96E-06 2.92E-06 CS 137 7.97E-05 1.09E-04 7.14E-05 -

3.70E-05 1.23E-05 2.11E-06 CS 138 5.52E-08 1.09E-07 5.40E-08 -

8.01E-08 7.91B-09 4.65E-13 BA 139 9.70E-08 6.91E-11 2.84E-09 -

6.46E-11 3.92E-11 1.72E-07 BA 140 2.03E-05 2.55E-08 1.33E-06 -

8.67E-09 1.46E-08 4.18E-05 BA 141 4.71E-08 3.56E-11 1.59E-09 -

3.31E-11 2.02E-11 2.22E-17 BA 142 2.13E-08 2.19E-11 1.34E-09 -

1.85E-11 1.24E-11 3.00E-26 LA 140 2.50E-09 1.26E-09 3.33E-10 - - -

9.25E-05 LA 142 1.28E-10 5.82E-11 1.45E-11 - - -

4.25E-07 CE 141 9.36E-09 6.33E-09 7.18E-10 -

2.94E-09 -

2.42E-05 CE 143 1.65E-09 1.22E-06 1.35E-10 -

5.37E-10 -

4.56E-05 CE 144 4.88E-07 2.04E-07 2.62E-08 -

1.21E-07 -

1.65E-04 PR 143 9.20E-09 3.69E-09 4.56E-10 -

2.13E-09 -

4.03E-05

' 144 3.01E-11 1.25E-11 1.53E-12 -

7.05E-12 -

4.33E-18 147 6.29E-09 7.27E-09 4.35E-10 -

4.25E-09 -

3.49E-05 W 187 1.03E-07 8.61E-08 3.01E-08 - - -

2.82E-0 NP 239 1.19E-09 1.17E-10 6.45E-11 -

3.65E-10 -

2.40E-0 R7

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 116 OF 123 TABLE 13 O INGESTION DOSE FACTORS FOR Tenrmn (arem per pCi Inhaled)

Page 1 of 2 l Nuclide Bone Liver T. Body Thyroid Kidnav Luna GI-LLI H 3 -

1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 C 14 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 NA 24 2.30E-06 2.30E-06 2.30E-06. 2.30E-06 2.30E-06 2.30E-06 2.30E-06 l P 32 2.76E-04 1.71E-05 1.07E-05 - - -

2.32E-05

! CR 51 - -

3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.05E-07 MN 54 -

5.90E-06 1.17E-06 -

1.76E-06 -

1.21E-05 MN SG -

1.58E-07 2.81E-08 -

2.00E-07 -

1.04E-05 FE 55 3.78E-06 2.68E-06 6.25E-07 - -

1.70E-06 1.16E-06 FE 59 5.87E-06 1.37E-05 5.29E-06 - -

4.32E-06 3.24E-05 CO 58 -

9.72E-07 2.24E-06 - - -

1.34E-05 CO 60 -

2.81E-06 6.33E-06 - - -

3.66E-05 NI 63 1.77E-04 1.25E-05 6.00E-06 - - -

1.99E-06 NI 65 7.49E-07 9.57E-08 4.36E-08 - - -

5.19E-06 CU 64 -

1.15E-07 5.41E-08 -

2.91E-07 -

8.92E-06 ZN 65 5.76E-06 2.00E-05 9.33E-06 -

1.28E-05 -

8.47E-06 i 69 1.47E-08 2.80E-08 1.96E-09 -

1.83E-08 -

5.16E-0.

BR 83 - -

5.74E-08 - - -

LT' E-24 BR 84 - -

7.22E-08 - - -

LT E-24 BR 85 - -

3.05E-09 - - -

LT E-24 RB 86 -

2.98E-05 1.40E-05 - - -

4.41E-06 RB 88 -

8.52E-08 4.54E-08 - - -

7.30E-15 RB 89 -

5.50E-08 3.89E-08 - - -

8.43E-17 ;

SR 89 4.40E-04 -

1.26E-05 - - -

5.24E-05 l SR 90 8.30E-03 -

2.05E-03 - - -

2.33E-04 SR 91 8.07E-06 -

3.21E-07 - - -

3.66E-05 SR 92 3.05E-06 -

1.30E-07 - - -

7.77E-05 3

Y 90 1.37E-08 -

3.69E-10 - - -

1.13E-04 1 Y 91M 1.29E-10 -

4.93E-12 - - -

6.09E-09 Y 91 2.01E-07 -

5.39E-09 - - -

8.24E-05 Y 92 1.21E-09 -

3.50E-11 - - -

3.32E-05 Y 93 3.83E-09 -

't.05E-10 - - -

1.17E-04 ZR 95 4.12E-08 1.30E-08 8.94E-09 -

1.91E-08 -

3.00E-05 ;

ZR 97 2.37E-09 4.69E-10 2.16E-10 -

7.11E-10 -

1.27E-04 95 8.22E-09 4.56E-09 2.51E-09 -

4.42E-09 -

1.95E-F 99 -

6.03E-06 1.15E-06 -

1.38E-05 -

1.08E .

l 99M 3.32E-10 9.26E-10 1.20E-08 -

1.38E-08 5.14E-10 6.08E-07 R7 m

l I

FORT CALHOUN STATION CH-ODCM-0001 l CHEMISTRY PROCEDURE PAGE 117 OF 123 l TABLE 13 INGESTION DOSE FACTORS FOR TEENAGER (aram per pCi Inhaled) l Page 2 of 2 Nuclide Bone Liver T. Body Thyroid Kidney Luno GI-LLI I TC 101 3.60E-10 5.12E-10 5.03E-09 -

9.26B-09 3.12E-10 8.75E-17 RU 103 2.55E-07 -

1.09E-07 -

8.99E-07 -

2.13E-05 l RU 105 2.18E-08 -

8.46E-09. -

2.75E-07 -

1.76E-05 RU 106 3.92E-06 -

4.94E-07 -

7.56E-06 -

1.88E-04 AG 110M 2.05E-07 1.94E-07 1.18E-07 -

3.70E-07 -

5.45E-05 TE 125M 3.83E-06 1.38E-06 5.12E-07 1.07E-06 - -

1.13E-05 TE 127M 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 -

2.41E-05 TE 127 1.58E-07 5.60E-08 3.40E-08 1.09E-07 6.40E-07 -

1.22E-05 ,

TE 129M 1.63E-05 6.05E-06 2.58E-06 5.26E-06 6.82E-05 -

6.12E-05 l TE 129 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.88E-07 -

2.45E-07 TE 131M 2.44E-06 1.17E-06 9.76E 07 1.76E-06 1.22E-05 -

9.39E-05 TE 131 2.79E-08 1.15E-08 8.72E-09 2.15E-08 1.22E-07 -

2.29E-09 TE 132 3.49E-06 2.21E-06 2.08E-06 2.33E-06 2.12E-05 -

7.00E-05 I 130 1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 -

2.29E-06 I 131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41E-05 -

1.62E-06 I

_ 132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 -

3.18E-0 I 133 2.01E-06 3.41E-06 1.04E-06 4.76E-04 5.98E-06 -

2.58E-06 I 134 1.46E-07 3.87E-07 1.39E-07 6.45E-06 6.10E-07 -

5.10E-09 I 135 6.10E-07 1.57E-06 5.82E-07 1.01E-04 2.48E-06 -

1.74E-06 CS 134 8.37E-05 1.97E-04 9.14E-05 -

6.26E-05 2.39E-05 2.45E-06 CS 136 8.59E-06 3.38E-05 2.27E-05 -

1.84E-05 2.90E-06 2.72E-06 ,

CS 137 1.12E-04 1.49E-04 5.19E-05 -

5.07E-05 1.97E-05 2.12E-06 CS 138 7.76E-08 1.49E-07 7.45E-08 -

1.10E-07 1.28E-08 4.76E-11 BA 139 1.39E-07 9.78E-11 4.05E-09 -

9.22E-11 6.74E-11 1.24E-06 BA 140 2.84E-05 3.48E-08 1.83E-06 -

1.18E-08 2.34E-08 4.38E-05 BA 141 6.71E-08 5.01E-11 2.24E-09 -

4.65E-11 3.43E-11 1.43E-13 BA 142 2.99E-08 2.99E-11 1.84E-09 -

2.53E-11 1.99B-11 9.18E-20 LA 140 3.48E-09 1.71E-09 4.55E-10 - - -

9.28E-05 LA 142 1.79E-10 7.95E-11 1.98E-11 - - -

2.42E-06 CE 141 1.33E-08 8.88E-09 1.02E-09 -

4.18E-09 -

2.54E-05 CE 143 2.35E-09 1.71E-06 1.91E-10 -

7.67E-10 -

5.14E-05 CE 144 6.96E-07 2.88E-07 3.74E-08 -

1.72E-07 -

1.75E-04 PR 143 1.31E-08 5.23E-09 6.52E-10 -

3.04E-09 -

4.31E-05 "R 144 4.30E-11 1.76E-11 2.18E-12 -

1.01E-11 -

4.74E-1 147 9.38E-09 1.02E-08 6.11E-10 -

5.99E-09 -

3.68E-0 W 187 1.46E-07 1.19E 0,7 4.17E-08 - - -

3.22E-05 NP 239 1.76E-09 1.66E-10 9.22E-11 -

5.21E-10 -

2.67E-05 R7

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 118 OF 123 TABLE 14

) INGESTION DOSE FACTORS FOR CHILD s/ Daram per pCi Ingested)

Page 1 of 2 Nuclide Bone Liver T. Body Thyroid Kidney Luna GI-LLI H 3 -

2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 C 14 2.03E-07 1.21E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 NA 24 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 P 32 8.25E-04 3.86E-05 3.18E-05 - - -

2.28E-05 CR 51 - -

8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07 MN 54 -

1.07E-05 2.85E-06 -

3.00E-06 -

8.98E-06 MN 56 -

3.34E-07 7.54E-08 -

4.04E-07 -

4.84E-05 FE 55 1.15E-05 6.10E-06 1.89E-06 - -

3.45E-06 1.13E-06 FE 59 1.65E-05 2.67E-05 1.33E-05 - -

7.74E-06 2.78E-05 CO 58 -

1.80E-06 5.51E-06 - - -

1.05E-05 CO 60 -

5.29E-06 1.56E-05 - - -

2.93E-05 '

NI 63 5.38E-04 2.88E-05 1.83E-05 - - -

1.94E-06 NI 65 2.22E-06 2.09E-07 1.22E-07 - - -

2.56E-05 CU 64 -

2.45E-07 1.48E-07 -

5.92E-07 -

1.15E-05 ZN 65 1.37E-05 3.65E-05 2.27E-05 -

2.30E-05 -

6.41E-06 k69 4.38E-08 6.33E-08 5.85E-09 -

3.84E-08 -

3.99E-L BR 83 - -

1.71E-07 - - -

LT E-24 BR 84 - -

1.98E-07 - - -

LT E-24 BR 85 - -

9.12E-09 - - -

LT E-24 RB 86 -

6.70E-05 4.12E-05 - - -

4.31E-06 RB 88 -

1.90E-07 1.32E-07 - - -

9.32E-09 RB 89 -

1.17E-07 1.04E-07 - - -

1.02E-09 SR 89 1.32E-03 -

3.77E-05 - - -

5.11E-05 SR 90 1.70E-02 -

4.31E-03 - - -

2.29E-04 SR 91 2.40E-05 -

9.06E-07 - - -

5.30E-05 SR 92 9.03E-06 -

3.62E-07 - - -

1.71E-04 Y 90 4.11E-08 -

1.10E-09 - - -

1.17E-04 Y 91M 3.82E-10 -

1.39E-11 - - -

7.48E-07 Y 91 6.02E-07 -

1.61E-08 - - -

8.02E-05 Y 92 3.60E-09 -

1.03E-10 - - -

1.04E-04 Y 93 1.14E-08 -

3.13E-10 - - -

1.70E-04 ZR 95 1.16E-07 2.55E-08 2.27E-08 -

3.65E-08 -

2.66E-05 ZR 97 6.99E-09 1.01E-09 5.96E-10 -

1.45E-09 -

1.53E-04 95 2.25E-08 8.76E-09 6.26E-09 -

8.23E-09 -

1.62E-0" 99 -

1.33E-05 3.29E-06 2.84E-05 499M 9.23E-10 1.81E-09 3.00E-08 2.63E-08 9.19E-10 1.10E-1.03E-06 R7

FORT CALHOUN STATION CH-ODCM-0001 CHEMISTRY PROCEDURE PAGE 119 OF 123 l TABLE 14 i

INGESTION DOSE FACTORS FOR CHILD l (arem per pCi Ingested)

Page 2 of 2 Nuclide Bone Liver T. Body Thyroid Kidney Luna GI-LLI TC 101 1.07E-09 1.12E-09 1.42E-08 -

1.91E-08 5.92E-10 3.56E-09 RU 103 7.31E-07 -

2.81E-07 -

1.84E-06 -

1.89E-05 RU 105 6.45E-08 -

2.34E-08. -

5.67E-07 -

4.21E-05 RU 106 1.17E-05 -

1.46E-06 -

1.58E-05 -

1.82E-04 AG 110M 5.39E-07 3.64E-07 2.91E-07 -

6.78E-07 -

4.33E-05 ,

TE 125M 1.14E-05 3.09E-06 1.52E-06 3.20E-06 - -

1.10E-05 l l

TE 127M 2.89E-05 7.78E-06 3.43E-06 6.91E-06 8.24E-05 -

2.34E-05 !

TE 127 4.71E-07 1.27E-07 1.01E-07 3.26B-07 1.34E-06 -

1.84E-05 TE 129M 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 -

5.94E-05 l TE 129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 -

8.34E-06 l TE 131M 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41E-05 -

1.01E-04 TE 131 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51E-07 -

4.36E-07 TE 132 1.01E-05 4.47E-06 5.40E-06 6.51E-06 4.15E-05 -

4.50E-05 I 130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 -

2.76E-06 I 131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 -

1.54E-0

. 132 8.00E-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 -

1.73E-0 I 133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 -

2.95E-06 I 134 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 -

5.16E-07 I 135 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 -

2.40E-06 CS 134 2.34E-04 3.84E-04 8.10E-05 -

1.19E-04 4.27E-05 2.07E-06 CS 136 2.35E-05 6.46E-05 4.18E-05 -

3.44E-05 5.13E-06 2.27E-06 CS 137 3.27E-04 3.13E-04 4.62E-05 -

1.02E-04 3.67E-05 1.96E-06 CS 138 2.28E-07 3.17E-07 2.01E-07 -

2.23E-07 2.40E-08 1.46E-07 BA 139 4.14E-07 2.21E-10 1.20E-08 -

1.93E-10 1.30E-10 2.39E-05 BA 140 8.31E-05 7.28E-08 4.85E-06 -

2.37E-08 4.34E-08 4.21E-05 BA 141 2.00E-07 1.12E-10 6.51E-09 -

9.69E'-11 6.58E-10 1.14E-07 BA 142 8.74E-08 6.29E-11 4.88E-09 -

5.09E-11 3.70E-11 1.14E-09 LA 140 1.01E-08 3.53E-09 1.19E-09 - - -

9.84E-05 LA 142 5.24E-10 1.67E-10 5.23E-11 - - -

3.31E-05 CE 141 3.97E-08 1.98E-08 2.94E-09 -

8.68E-09 -

2.47E-05 CE 143 6.99E-09 3.79E-06 5.49E-10 -

1.59E-09 -

5.55E-05 CE 144 2.08E-06 6.52E-07 1.11E-07 -

3.61E-07 -

1.70E-04 PR 143 3.93E-08 1.18E-08 1.95E-09 -

6.39E-09 -

4.24E-05 l 't 144 1.29E-10 3.99E-11 6.49E-12 -

2.11E-11 -

8.59E-0 l

> 147 2.79E-08 2.26E-08 1.75E-09 -

1.24E-08 -

3.58E-0 W 187 4.29E-07 2.54E-07 1.14E-07 - - -

3.57E-05 NP 239 5.25E-09 3 . 77E -10 2.65E-10 -

1.09E-09 -

2.79E-05 R7

FORT CALHOUN STATION CHEMISTRY PROCEDURE CH-ODCM-0001 PAGE 120 OF 123 TABLE 15 O INGESTION DOSE FACTORS FOR INFANT (arma per pCi Ingested)

Page 1 of 2 i Hug.lide Bone Liver T. Body Thyroid Kidnav Lunct GI-LLI H 3 -

3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 C 14 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 NA 24 1.01E-05 5.06E-06 1.01E-05 1.01E-05. 1.01E-05 1.01E-05 1.01E-05 1.01E-05 P 32 1.70E-03 1.00E-04 6.59E-05 - -

! CR 51 2.30E-05 1.41E-08 9.20E-09 2.01E-09 1.79E-08 4.11E-07 1

MN 54 -

1.99E-05 4.51E-06 -

4.41E-06 -

7.31E-06 i

MN 56 -

8.18E-07 1.41E-07 7.03E-07 7.43E-05

{ FE 55 1.39E-05 8.98R-06 2.40E-06 FE 59 3.08E-05 4.36E-06 1.14E-06

! 5.38E-05 2.12E-05 - -

1.59E-05 2.57E-05 i

t l CO 58 -

3.60E-06 8.98E-06 - -

CO 60 8.97E-06 1 1.08E-05 2.55E-05 - - .

2 57E-05 j NI 63 6.34E-04 3.92E-05 2.20E-05 - - .

1.95E-06 l NI 65 4.70E-06 5.32E-07 2.42E-07 CU 64 -

6.09E-07 4.05E-05 2.82E-07 -

1.03E-06 -

1.25E-05 i ZN 65 1.84E-05 6.31E-05 2.91E-05 -

3.06E-05 -

5.33E-OR 69 9.33E-08 1.68E-07 1.25E-08 -

6.98E-08 -

1.37E-0.,

! BR 83 - -

3.63E-07 BR 84 -

LT E-24 3.82E-07 - - -

LT E-24

! BR 85 - -

1.94E-08 I RB 86 LT E-24 1.70E-04 8.40E-05 - - -

4.35E-06 RB 88 -

4.98E-07 2.73E-07 4

i 4.85E-07

.' RB 89 -

2.86E-07 1.97E-07 - -

SR 89 9.74E-08 2.51E-03 -

7.20E-05 - - -

5.16B-05 SR 90 1.85E-02 -

4.71E-03 - - -

2.31E-04 SR 91 5.00E-05 -

1.81E-06 - -

SR 92 5.92E-05 1.92E-05 -

7.13E-07 - -

Y 90 2.07E-04 8.69E-08 -

2.33E-09 - - -

1.20E-04 Y 91M 8.10E-10 -

2.76E-11 Y 91 2.70E-06 1.13E-06 -

3.01E-08 - - -

8.10E-05 Y 92 7.65E-09 -

2.15E-10 - - -

1.46E-04 Y 93 2.43E-08 -

6.62E-10 - -

ZR 95 1.92E-04 2.06E-07 5.02E-08 3.56E-08 -

5.41E-08 -

2.50E-05 ZR 97 1.48E-08 2.54E-09 1.16E-09 -

2.56E-09 -

1.62E-04 95 4.20E-08 1.73E-08 1.00E-08 -

1.24E-08 -

1.46E-r-99 -

3.40E-05 6.63E-06 5.08E-05

99M 1.92E-09 3.96E-09 5.10E-08 4.26E-08 2.07E-09 1.12E-1.15E-06 R7

T l

I FORT CALHOUN STATION CH-ODCM-0001 l CHEMISTRY PROCEDURE PAGE 121 OF 123 I TABLE 15 INGESTION DOSE FACTORS FOR INFANT (arem per pCi Ingested)

Page 2 of 2 Nuclide Bone Liver T. Body Thyroid Kidney Luno GI-LLI l TC 101 2.27E-09 2.86E-09 2.83E-08 -

3.40E-08 1.56E-09 4.86E-07 RU 103 1.48E-06 -

4.95E-07 -

3.08E-06 -

1.80E-05 1 RU 105 1.36E-07 -

4.58E-08 -

1.00E-06 -

5.41E-05 l 1

RU 106 2.41E-05 -

3.01E-06 -

2.85E-05 -

1.83E-04 AG 110M 9.96E-07 7.27E-07 4.81E-07 -

1.04E-06 -

3.77E-05 TE 125M 2.33E-05 7.79E-06 3.15E-06 7.84E-06 - -

1.11E-05 TE 127M 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 -

2.36E-05 TE 127 1.00E-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 -

2.10E-05 7L 129M 1.00E-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 -

5.97E-05 TC 129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 -

2.27E-05 I TE 131M 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21E-05 -

1.03E-04 TE 131 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 -

7.11E-06 TE 132 2.08E-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05 -

3.81E-05 I 130 6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 -

2.83E-06 !

T 131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 -

1.51E-0 l

. 132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 -

2.73E-0 '

i 133 1.25E-05 1.82E-05 5.33E-06 3.31E-03 2.14E-05 -

3.08E-06 I 134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 -

1.84E-06 I 135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 -

2.62E-06 CS 134 3.77E-04 7.03E-04 7.10E-05 -

1.81E-04 7.42E-05 1.91E-06 CS 136 4.59E-05 1.35E-04 5.04E-05 -

5.38E-05 1.10E-05 2.05E-06 CS 137 5.22E-04 6.11E-04 4.33E-05 -

1.64E-04 6.64E-05 1.91E-06 CS 138 4.81E-07 7.82E-07 3.79E-07 -

3.90E-07 6.09E-08 1.25E-06 BA 139 8.81E-07 5.84E-10 2.55E-08 -

3.51E-10 3.54E-10 5.58E-05 BA 140 1.71E-04 1.71E-07 8.81E-06 -

4.06E-08 1.05E-07 4.20E-05 BA 141 4.25E-07 2.91E-10 1.34E-08 -

1.75E-10 1.77E-10 5.19E-06 BA 142 1.84E-07 1.53E-10 9.06E-09 -

8.81E-11 9.26E-11 7.59E-07 LA 140 2.11E-08 8.32E-09 2.14E-09 - - -

9.77E-05 LA 142 1.10E-09 4.04E-10 9.67E-11 - - -

6.86E-05 CE 141 7.87E-08 4.80E-08 5.65E-09 -

1.48E-08 -

2.48E-05 CE 143 1.48E-08 9.82E-06 1.12E-09 -

2.86E-09 -

5.73E-05 CE 144 2.98E-06 1.22E-06 1.67E 07 -

4.93E-07 -

1.71E-04 PR 143 8.13E-08 3.04E-08 4.03E-09 -

1.13E-38 -

4.29E-05

144 2.74E-10 1.06E-10 1.38E-11 -

3.84E-11 -

4.93E-0 147 5.53E-08 5.68E-08 3.48E-09 -

2.19E-08 -

3.60E-05 W 187 9.03E-07 6.28E-07 2.17E-07 - - -

3.69E-05 NP 239 1.11E-OF 9.93E-10 5.61E-10 -

1.98E-09 -

2.87E-05 R7

- -.-.__ - . . - . . - - .- - . - . =, - . . . -

l l FORT CALHOUN STATION CH-ODCM-0001 l CHEMISTRY PROCEDURE l

PAGE 122 OF 123 TABLE 16 :

RECCBGENDED VALUES FOR OTHER PARAMETERS Page 1 of 2 !

Parameter Symbol I Definition Values f, Fraction of produce ingested grown in garden 0.76 '

of interest. I l

l f, Fraction of Icafy vegetables grown in garden 1. 0 ' l l of interest.

P Effective surface density of soil (assumes a 240 kg/m2 l 15 cm plow layer, expressed in dry weight) '

r Fraction of deposited activity retained on 0.25 crops, leafy vegetables, or pasture grass. 1.0 (for iodines) i 1

0.2 (for other !

particulates)

S, Attenuation factor accounting for shielding provided by residential structures, 0.7 (for maximum individuals) 0.5 (for general l population) t3 Period of long-tenn buildup for activity in 1.31 x 108 hr

( sediment or soil (nominally 15 yr) .

t. Period of crop, leafy vegetable, or pasture 720 hrs (30 days, grass exposure during growing season. for grass-cow-milk-man path-way) 1440 hrs (60 days for crop /

vegetation-man pathway) t, Transport time from animal feed-milk-man 2 days (for max. !

provided by residential structures.

individual) l 4 days (for gen. l population) l i

ta Time delay between harvest of vegetation l or crops and ingestion.

i) For ingestion of forage by animals Zero (for pasture grass) 2160 hr (90 days

for stored l

feed)

\

\ (b R7

FORT CAWOUN STATION CH-ODCM-0001 l CHEMISTRY PROCEDURE PAGE 123 OF 123 TABLE 16 i RECOBOGNDED VALUES FOR OTHER PARAMETERS .

Page 2 of Parameter Symbol Definition Values ii) For ingestion of crops by man 24 hr (1 day, for leafy vege-tables & max.

individual) l feed) 1440 hr (60 days for produce &

maximum in-dividual) 336 hr (14 days for general population) t, Environmental transit time, release to 12 hr (for max.

receptor (add time from release to exposure individual) point to minimums shown for 24 hr (for gen.

distribution) population) 24 hr (for max.

individual) 168 hr (7 days for population sport fish doses) l 240 hr (10 days ,

for population l commercial ;

fish doses) I l

t, Average time from slaughter of meat animal to 20 days consumption.

Y, Agricultural productivity by unit area 0.7 kg/m2 (for (measured in wet weight) grass-cow-milk man pathway) i 2.0 kg/m2 (for I produce or l' leafy vegeta-bles ingested by man)

W Shore-width factor for river shoreline 0.2

( L Rate constant for removal of activity on plant 0.0021 hr~1

! or leaf surfaces by weathering (corresponds to a 14-day half , life) 1 R7 l

ML20108A716

Contents

Text

Title:

1.0 INTRODUCTION

5.0 REFERENCES

Y. PROCEDURE

1.4.1 Where

1.4.2 Where

1.5.1 Where

Navigation menu

ML20108A716

Text

Title:

1.0 INTRODUCTION

5.0 REFERENCES

Y. PROCEDURE

1.4.1 Where

1.4.2 Where

1.5.1 Where

Navigation menu

Search