ML20097B192

Draft Chemistry Manual Procedure CMP-6

ML20097B192
Person / Time
Site:	Fort Calhoun
Issue date:	05/18/1992
From:	OMAHA PUBLIC POWER DISTRICT
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ML20097B178	List: ML20097B176 ML20097B181 ML20097B188 ML20097B192 ML20097B202
References
CMP-6, NUDOCS 9206040194
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Text

1 FORT CALHOUN STATION PAGE 1 OF 13 CllEMISTRY MANUAL PROCEDURE CMP-6 TI D

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PART I ADMINISTRATIVE SECTION l

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- "1 b PAGE 2 OF 13 FORT CALHOUN STATION h CHEMISTRY MANUAL PROCEDURE CMP-6 TABLE OF CONTENTS PART I

1.0 INTRODUCTION

. . . . ................. 6 2.0 ADMINISTRATION . . . ................. 6 2.1 Responsibilities . . ............... 6 2.1.1 Radiological Effluent Program . . . . . . . 6 2.1.2 Radiological Environmental Monitoring Program . ................. 7 2.1.3 Other . . ......... . . . . . . . 7 2.2 Change Mechanism . . ............... 7 3.0 METEOROLOGICAL DATA . ................. 8 4.0 DEFINITIONS . . . . . ................. 8

5.0 REFERENCES

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-1.0 . RADIOACTIVE EiFLUENTS RELEASE LIMITS . . . . . . . . . . 2 1.1 Liquid Effluents . . .............. 2 1.2 Gaseous Effluents . ............... 2 2.0 RADIOLOGICAL EFFLUENT RELEASE REQUIREMENTS . . . . . . . 4 2.1 Liquid Effluents Releases . . . . . . . . . . . . 4 2.1.1 Monitor Tanks ............... 4 2.1.2 Steam Generator . . . . . . . . . . . . . . 6 2.2 Gaseous Effluent Releases . . . . . . . . . . . . 7 2.2.1 Gasecua Auxiliary Building Exhaust Stack . 7 2.2.2 Condenser Offgas . . . . . . . . . . . . . 10 2.2.3 Laboratory and Radwaste Building Stack . . 10 3.0 RADIOLOGICAL EFFLUENT SAMPLING AND ANALYSIS REQUIREMENTS 11 3.1 Liquid Effluents . ............... 11 3.2 Gaseous Effluents . ............... 12 3.3 Lower Limit of Detection (LLD) . . . . . . . . . . 12 4.0 RADIOACTIVE LIQUID EFFLUENT REPORTING REQUIREMENTS . . . 14 4.1 Liquid Effluents . . ............... 14 4.2 Gaseous Effluents . ............... 15 4.3 Semi-Annual Report . ............... 16 4.4 Annual Report . . . ............... 17 4.5 Non-Routine Report ............... 18 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING REQUIREMENTS . . . 10 l:

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'j,] f- PAGE 4 OF 13 CHEMISTRY MANUAL PROCEDURE CMP-6 LIST OF TADLES PART II 1 Radioactive Liquid Waste Sampling and Analysis . . . . . 21 2 Radioactive Gaseous Waste Sampling and Analysis . . . . 22 3 Radis+ ion and Environmental Monitors Operability Requirements . . . . . . . ............... 24 4 Radiological Environmental Monitoring Program . . . . . 25 5 Radiological Environmental Sampling Locations and Media 27 6 - Detection Capabilities for Environmental Sample Analysis (LLD) . . . . . . - . . . . ............... 29 7 Reporting Levels for Radioactivity Concentrations in Environmental Samples . . ............... 30 1

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CMP-6 PART III 1.0 EFFLUENT MONITOR SETPOINTS ........< . . . . . . 2 1.1 Liquid Effluents . . .............. 2 1.2 Liquid Effluent Radiation Monitors . . . . . . . . 3 1.2.1 Steam Generator Blowdown Monitors . . . . . 3 1.2.2 Overboard Discharge Header Monitor . . . . 4 1.3 Gaseous Effluents . .............. 7 1.4 Gascous Effluent Radiation Monitors . . . . . . 0 1.4.1 Auxiliary Effluent Radiation Monitors . . . 8 1.4.2 Auxiliary Building Exhaust Stack Gaseous activity Monitors . . . . . . . . . . . . . 10 1.4.3 Auxilitty Building Txhaust Stack Iodine Monitor . . . ... . . . . . . . . . . . 12 1.4.4 Condenser Air Ejector Monitor . . . . . . . 14 1.4.5 Laboratory and Radioactive Waste Processing Building (LRWPB) Exhaust Stack Particulate Monitor (RM-041) . . . . . . . . . . . . . 16 1.4.6 Laboratory and Radioactive Waste Processing Building Exhaust Stack Iodine Monitor (RM-042)18 1.4.7 Laboratory an6 Radioactive '4ste Processing Building Exhaust Stack Noble Gas Monitor (RM-043) . . ...............  ?,0 1.5 Simultaneous Release Pathways . . . . . . . . . 22 1.5.1 Liquid Release Pathways . . . . . . . . . . 22 1.5.2 Gaseous Release Pathways . . . . . . . . . 22 2.0 RADIOACTIVE WASTE TREATMENT SYSTEM . . . . . . . . . . . 28 2.3 Liquid Radwaste Treatment System . . . . . . . . 28 2.2 Gaseous Radwaste Treatment System . . . . . . . 29 h

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PAGE 6 OF 13 CM- 6 CHEMISTRY MANUAL PF7CEDURE LIST OF TABLES PART III 1 Proportionally Constants for Simultaneous Release Pathways . . . . . ............... 27 j

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PAGE 7 OF 13 CMP-6 PART IV 10 EFFLUENT CONCENTRATION LIMITS - 10 CFR 20 . . . . . . . 2 1.1 Liquid Effluent Concentration Limits . . . . . . 2 1.2 Gas Effluent Concentration Limits . . . . . . . . 3 2.0 RADIOACTIVE EFFLUENT DOSE LIMITS . . . . . . . . . . . . 4 2.1 Liquid Effluent Dose Calculations . . . . . . . . 4 2.2 Gaseous Effluent Dose Calculations . . . . . . . 8 2.2.1 Noble Gas . . . . . . . . . . . . . . . . . 8 2.2.2 Radiciodine, Tritium, and Particulates . . 10 FC/ CMP /01 051892

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CHEMISTRY MANUAL PROCEDURE s dU u 3 ) CMP-C LIST OF TABLES PART IV 1 Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases . . . . . .. ........... 19 2 Bioaccumulation FLctors . . . .. ........... 20 3 Controlling Locations, Pathways, and Atmospheric Dispersion for Dose Calculations . ........... 21 4 Stable Element Transfer Data . . . ........... 22 5 Recommended Values for U,p to be Used for the Maximum Exposed Individual in Lieu of Site Specific Data . ....... 23 6 Animal Consumption Rates . . . .. ........... 23 7 Inhalation Dose Factor for Adult . ........... 24 8 Inhalation Dose Factor for Teenage ........... 26 9 Inhalation Dose Factor for Child ........... 28 10_ Inhalation Dose Factor for Infant ........... 30 11 Ingestion Dose Factor for Adult . ........... 32 12 Ingestion Dose Factor for Teenage ........... 34 13 Ingestion Dose Factor for Child . ........... 36

-14 Ingestion Dose Factn; for Infant . ........... 38 15 Recommended Values for Other Parameters ........ 40 FC/ CMP /01 051892

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] [ffgj) PAGE 9 OF 13 CHEMISTRY MANUAL PROCEDURE CMP-6 1.0 JNIRODUCTION The OFFSITE DOSE CALCULATION MANUAL (ODCM) is the controlling 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, Radiological Effluent Contr..ls - consists of 5 separate sections including:

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 Require-ments Together these sections provide the controls used to permit radioactive material releases from the Fort Calhoun Station.

Part III, Radiological Effluent Radiation Monitor Calcula-tion - provides radiation monitor setpoint calculations for the liquid and gaseous release pathways.

Part IV, Radiological Effluent Monitoring Calculations -

provides the methodology necessary to calculate doses to individuals as a result of radioactive gaseous 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.

2.0 ADMINISTRATIVE 2.1 Besponsibilities 2.1.1 Radiological Effluent Program The Radiological Effluent Program consists of the following sections in the Radiological Effluent Controls:

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s a 7) 57 FORT CALHOUN STATION /- b PAGE 10 OF 13-hs- O 'ja J { cap _e CHEMISTRY MANUAL PROCEDURE 2.1.1 Radiological Effluent Management Program (Continued)

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 4.2 Nuclear Operation Division Chemistry Department is re-sponsible for the implementation and maintenance of this program.

2.1.2 Radiological. Environment Monitoring Program The Radiological Environmental Monitoring Program consists of the following sections in the Radiological Effluent Controls:

A. Radiological Effluent Releases Limits

- All Sections B. Radiological Effluent Reporting Requirements

- Sections 4.3, 4.4, and 4.5 C. Radiological Environmental Monitoring Re-quirements - All Sections Production Engineering Division, Radiological Services is responsible for the implementation and reintenance l of this program.

2.1.3 Other All other portions of this ODCM provide the methrdology-necessary to. implement the Radio-logical Effluent Controls. It is the joint L responsibility of both Chemistry and Radiologi-I cal Services for the maintenance of these l sections.

l- 2.2 Chance Mechanism The ODCM is the controlling document for all radio-active 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 Com-mittee and approved by the Plant Manager in accordance with Technical Specification 5.17. All changes to the L FC/ CMP /01 051892

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T a FORT.CALHOUN' STATION Pt PAGE 11 OF 13 CHEMISTRY MANUAL PROCEDURE $ 'b' [g m -cp b' CMP-6 2.2 Chance Mechanism (Continued)

ODCM will be forwarded to the Nuclear Regulatory Comnission during the next reporting period for the Semiannual Report in accordance with the requirements of Technical Specification 5.17.

3.0 METEOROLOGICAL DATA The Annual Average X/Q is utilized to determine the concen-trations of radionuclides at the site boundary. This dis-persion 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 Nu-clear Regulatory Commissions Regulatory Guide 1.111. The model employs the sector averaged equations that are uti-lized 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 site boundary.

Real time meteorological data will be utilized in the pre-paration of the Semiannual Report. This data is used to calculate the joint frequency table and the dispersion coef-ficients 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, con-form with the Nuclear: Regulatory Commissions Reg. Guide 1.109 and 1.21 for the reporting of doses due to routine radioactive effluent releases.

4.0 DEFINITIONS Channel Check A qualitative determination of acceptable operability by observation of channel behavior during normal plant opera-tion. This determination shall, where feasible, include comparison of-the channel-with other independent channels measuring the same variable.

-Channel Function Test Injection of a simulated signal into the channel to verify

that it is operable, including any alarm and/or trip initia-ting action.

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CHEMISTRY MANUAL PROCEDURE 3 J) hu [L CMP-6 4.0 DEFINITIONS (Continued)

Ooerable - Operability A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of perform-ing its specified function (s). Implicit in this definition shall be the assumption that all necessary attendant instru-mentation, controls, normal and emergency electrical power sources, cooling or seal water, lubrication, or other auxi-liary equipment that are required for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related support func-tion (s).

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

Sampler An inline assembly utilized for the collection of a sample from.a radioactive effluent stream. This sample is utilized for the determination of radionuclide releases from Fort Calhoun Station. No detection capabilities are required to exist for this configuration.

Source Check Verification of channel response when the channel sensor is exposed to a radioactive source.

Ventina A_means for the_ reduction of pressure greater than atmos-pheric within the containment structure.

Unrestricted Area l

Any area at or bevond the site boundary access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and. radioactive materials.

5.0- REFERENCES 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 FC/ CMP /01 051892

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5.0 REFERENCES

(Continued)

-Regulatory Guide 1.111, 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 fror.

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 FC/ CMP /01 051892 )

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Il }l rp tp FORT CALHOUN STATION g '}q l PAGE 2 OF 31 CHEMISTRY MANUAL PROCEDURE '  : J CMP-6 1.0 RADIOACTIVE EFFLUENTS RELEASE LIMITS The limits and conditions for the controlled release of radioactive materjal in liquid and gaseous effluents stated in this Section are to ensure that these releases result in concentrations of radioactive materials in liquid and gase-onc effluents released to unrestricted areas that are within the limits specified in 10 CFR 20 and to ensure that the release of radioactive material to the environment above background 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 gaseous effluents from FCS:

1.1 Licuid Effluenti 1.1.1 The '.tlessa rate of radioactive material in liquid effluents shall be-controlled such that the instantaneous concentrations for radionuclides, other than dissolved or en-trained noble gases, do not exceed the values specified in 10 CFR 20 for liquid effluents in unrestricted areas. For dissolved or entrained noble gases, the concentration shall be limited to 2.0 E-04 #Ci/ml, total activity.

1.1.2 'The dose or dose commitment to an individual in unrestricted areas from-radioactive materiale in liquid effluents during any calendar year shall not exceed 3 millirems to the total body, 1.1.3 The dose or dose commitment to an individual in unrestricted areas from radioactive materials in liquid effluents during any calendar year shall not exceed 10 millirems to any orcan.

When the concentration of radioactive material released to unrestricted areas exceeds the above

! limits, appropriate corrective actions shall be taken l immediately to restore concentrations within the above limits.

1.2 Gaseces Effluents 1.2.1 The release rate of radioactive material in gaseous effluents shall be controlled such that the instantaneous concentrations for these radionuclides do not exceed the values specified in 10 CFR 20 for gaseous effluents in unrestricted areas at and beyond the site boundary.

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CMP-6 1.2 Gaseous Effluents (Continued) 1.2.2 The gamma air dose in unrestricted areas due .

.to the release of noble gases in gaseous effluents shall not exceed 10 millirads during any calendar year; 1.2.3 The be* air dose in unrestricted areas due to the rLieh e of noble gases in gaseous effluents shall not exceed 20 millirado during any calendar year; and 1.2.4 The dose to an individual or dose commitment to any organ of an individual in unrestricted areas due to the release of I-131, Tritium, and radioactive materials in particulate form with half-lives greater than eight days (excluding noble gases) in gaseous effluents shall not exceed 15 millirems from all exposure pathways during any calendar year.

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.

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~j U ,^D'] {\, h "lP l PAGE 4 OF 31 CMP-6 2.0 RADIOACTIVE EFFLUENT RELEASE REOUIREMENTS The requirements for the relense of radioactive liquid and gaseous' effluents from FCS stated in this Section are to ensure that the limits of Section 1 will be met, as well as to allow for operational flexibility. When any of the redairements for release of 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.

2.1 Licuid Effluent Releases 2.1.1 Monitor Tanks During_ release of radioactive liquid efflu-ents, excluding releases from the steam generators, the following conditions shall be met:

2.1.1.1 There shall be sufficient dilution flow so that, at site discaarge:

n

[ Cg/mpc, s1 i=1 where:

C =3 concentration of the 1*

radionuclide in the liquid effluent at site discharge.

mpci = 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.

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"U IT l CHEMISTRY MANUAL PROCEDURE CMP-6 2.1 Llauid Effluent Releases (Continued) 2'.1.1 M.onitor Tanks 2.1.1.3 The liquid effluent radioactivity shall be continuously monitored during the release. If the efflu-ent radiation monitor is inoper-able, effluent releases may con-tinue provided that: (prior co initiating a release)

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

D. At least two shift qualified chemistry technicians indepen-dently verify the release rate calculations.

2.1.1.4 The liquid effluent radioactivity shall be continuously recorded dur-ing the release. If the process radiation monitor chart recorder is not operational and radioactivity levels cannot be recorded automa-tically, effluent releases may con-tinue provided that the radioacti-vity level is recorded manually at least once por 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 inoper-able, effluent releases may continue provided the flow rate is determined at least once per four hours during actual release.

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i li PAGE 6 OF 31 CHEMISTRY liANUAL PROCEDURE- L [J [j CMP 2.1.2 Steam Generator During the release of steam generator blow-down_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 Ci /mpc, S1 where:

C 3

= concentration of the 1*

radionuclide in the liquid effluent at site discharge.

mpc;= 10 CFR 20, Appendix B, Table 2, Column 1 limit.

2.1.2.2 The steam generator blowdown radia-tion monitors shall be set in accordance with Part III to alarm and automatically close the blowdown isolation valves prior to exceeding 10 CFR 20 limits.

2.1.2.3 The radioactivity for each blowdown line shall be continuously moni-tored and recorded by the blowdown radiation monitors.

A. If one of the two radiation monitors is inoperable, the activity for both blowdown lines shall be monitored by the operable radiation monitor.

B. If both radiation monitors are inoperable, steam generator liquid releases may continue provided grab samples are analyzed for 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 FC/ CMP /01 051892 o

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[j CMP-6 2.1.2 Steam Generator (Contin'aed) 2.1.2.3 to 0.01 pCi/ gram dose equiva-lent I-131 and at least B. Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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 re-corded. If the process radiation monitor chart recorder is not oper-ational, Steam Generator releases may continue provided that the radioactivity level is recorded manually at least once per four hours during actual release.

2.2 Gaseous Effluent Releases 2.2.1 Gaseous Auxiliary Buildina Enhaust Stach 2.2.1.1 During release of gaseous radioac-tive effluents from containment' pressure relief line to the Auxiliary Building Exhaust Stack, the following conditions shall be met:

A. The Auxiliary Building Exhaust Stack noble gas monitor, iodine sampler and particulate ,

sampler shall be operational.

B. The Auxiliary Building Exhaust Stack noble gas radiation _ mon-itor shall be set in accor-dance with Part III to alarm and automatically terminate the release prior to exceeding 10 CFR 20 limits at cite boundary (see Figure 1).

C. At least one Auxiliary Build-ing exhaust fan shall-be in operation.

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7 C7 FORT CALHOUN STATION 7]i }N] $  % PAGE 8 OF 31 1 CHEMISTRY MANUAL PROCEDURE 2 30 d - CMP-6 2.2 Gaseous Effluent Releases 2.2.1 Gaseous Auxiliary Buildina Exhaust Stack 2.2.1.1 D. The Auxiliary Building Exhaust Stack gaseous radioactivity shall be monitored and recorded during the release.

If the process radiation monitor chart recorder is not operational and gaseous radioactivity levels cannot be recorded automatically, releases from containment may continue provided that the gaseous radioactivity level is recorded manually at least once per four hours during the actual release.

E. The containment 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 determined at least once per four hours during actual release.

2.2.1.2 During the release of gaseous radioactive effluents from the containment purge line:

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

B. A noble gas monitor shall monitor the containment build-ing atmosphere. If the process radiation monitor chart recorder is not operational and gaseous radioactivity levels cannot be recorded automatically, releases from containment may continue pro-vided-that the gaseous radioactivity level is recorded manually at least once per four hours during the actual release.

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- CMP-6 2.2 Qasppus Effluent Relearga 2.2.1 Gaseous Auxiliary Buildina Exhaust Stack 2.2.1.3 During the release of gaseous effluents from_the gaseous waste discharge header:

A. The Auxiliary Building Exhaust Stack noble gas radiation mon-itor shall be set in accor-dance with Part III to alarm and automatically terminate the release prior to exceeding 10 CFR 20 limits at site boundary (see Figure 1).

B. If the Auxiliary Building Exhaust Stack radiation monitor is inoperable, efflu-ent releases may continue pro-vided that (prior to release):

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

ii. At least two shift quali-fled chemistry techni-clans independently verify the_ release rate calculations.

C. At least one Auxiliary Build-ing exhaust fan shall be in operation.

D. The waste gas discharge header flow rate shall be monitored and automatically recorde) during releases. If the flow rate recorder is inoperable, releases may continue provided the flow rate is determined at least once per four hours during actual release.

2.2.1.4 The Auxiliary Building Exhaust Stack noble gas monitor, particu-late sampler, or iodine sampler may be inoperable provided that:

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$7 1 CMP-6 2.7 Gaseous Effluent Releases 2.2.1 Gaseous Auxiliary Buildina Exhaust Stagh 2.2.1.4 A. Whenever the Auxiliary Build-ing Exhaust Stack noble gas monitor is inoperable, releases from the containment pressure relief line and the containment purge line are to be cecured in the most expeditious manner.

Ventilation of the auxiliary building via the Auxiliary Building Exhaust stack may continue provided grab samples are taken and analyzed once per eight (8) hours for principal gamma emitters.

B. Whenever the Auxiliary Building Exhnust Stack iodine-or particulate sampler (s) is/are inoperable, releases from the gaseous waste discharge header, containment pressure relief line or the containment purge line are to be secured in the most expeditious manner. These releases may continue provided samples are collected using auxiliary sample collection equipment in accordance with Table 2.

C.

Whenever the Auxiliary Building Exhaust Stack ~ odine or particulate samplor(,-)

b is/are inoperable, ventilation L of the auxiliary building via the Auxiliary Building Exhaust Stack may continue provided sample collection using auxiliary sample collection equipment is initiated within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of the discovery of the inoperability in accordance with Table 2.

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2.2.2 Condenser Offaas-2.2.2.1 'During power operation, the con-denser _ air ejectoridischarge shall be monitored'for gross:radioacti-vity. _If this monitor is-inoper-able, grab samples shall be taken and analyzed daily for principal gamma emitters. (See Table 2) 2.2.3 Laboratory and Radioactive Waste Processina Buildina Stack 2.2.3.1 The Laboratory and Radioactive Waste Processing Building (LRWPB)

Stack noble gas monitor, particu-late _ sampler or Jodine sampler _may be inoperable and= effluents-via-this-pathway may continue provided:

2.2.3.1- A. If the noble-gas monitor is '

inoperable, grab samples will be-taken once per-:24 hours and analyzed for principal gamma emitters.

B. If the. iodine or particulate sampler (s) is/are. inoperable, ventilation of the'LRWPB may continue via-the LRWPB Stack' provided sample collection using'auxilir.ry sample collecion equipment is initiated within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of the-discovery ofithe inoperability in accordance with Table 2.

C. The LRWPB Stack flow rate shall be monitored and recorded during ventilation of the LRWPB. If the flow rate recorder is' inoperable,

_ ventilation may continue provided the flow rate is determined'at least once per .

four hours.

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Ti 7 c7 FORT CALHOUN STATION b PAGE 12 OF 31 CHEMISTRY MANUAL PROCEDURE L ) E u!- f- CMP-6

3. 0 ' RADIOLOGICAL EFFLUENT SAMPLING AND ANALYSIS REQUIREMENTS The sampling and analysis requirements stated in this Sec-tion will provide reasonable assurance that radioactive materials'present in the liquid and gaseous 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 Regu-latory Commission in accordance with Section 4 of these Controls.

3.1 Licuid Effluents 3.1.1 Radioactive liquid waste 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 concen-tration at the point of release does not ex-ceed 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.

l 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 L

over which each discharge occurred. Analyti-cal results shall be submitted to the Commis-sion in accordance with Section 4 of these Controls.

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-CHEMISTRY MANUAL PROCEDURE -

CMP-6 3.1 Liauid Effluents (Continued) 3.1.4 The radiation monitors for liquid effluents shall have their operability verified in accordance with the requirements in Table 3, Part A.

3.2 Gaseous Effluentq 3.2.1 Radioactive gaseous waste sampling and activity analyses shall be performed in accordance with Table 2. 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 does not exceed 10 CFR 20 limits for unrestricted areas.

3.2.2 The radiation monitors for gaseous effluents shall have their operability verified in accordance with the requirements in Table 3, Part B.

3.3 ' Lower Limit of Detection (LLD)

The lower limit of detection (LLD) for liquid and gaceous discharges, referenced in Tables 1 and 2 of the Radiological Effluent Controls (Part II), is defined as the smallest concentration of radioactive material in a sample that will yield a not 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

• s y B

• V

• D

• Y

• exp (- Aa t)

Where:

LLD = the lower limit of detection as defined above, p 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 ,

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FORT CALHOUN STATION h PAGE 14 OF 31 CHEMISTRY !!ANUAL PROCEDURE '

CMP-6 3.3 Lower Limit of Detection (LLD) (Continued)

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 Y= the fractional radiochemical yield, when applicable ,

1= 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 ar.d 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 mea-surement 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.

l~

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PAGE 15 OF 31 CHEMISTRY MANUAL-PROCEDURE CMP-6 4.0 BADIOACTIVE LIOUID EFFLUENT REPORTING REOUIREMFHIS 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 requiremente 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, Rcv. 1.

4.1 Liquid Effluent.g 4.1.1 The radiation dose contributions from radio-active materials in liquid effluents released to unrestricted areas shall be determined, in accordance with the ODCM, on a quarterly basis. If the dose contribution, due to the cumulative release of liquid effluents averaged over a calendar quarter, exceeds one-half of the annual design objectives, the following-course of actions shall be taken:

A. Make an investigation to identify the causes for such releases.

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

C. Submit a special report, pursuant to Tech-nical Specification 5.16, within 30 days from the end of the quarter during which the release (s) occurred, identifying the causes and describin' the proposed program of action to reduce such releases to the design levels.

4.1.2 The equipment or subsystem (s) of the liquid radwaste treatment system as identified in the

-ODCM, shall be operable. If the radioactive liquid wastes were discharged without treat-ment by one or more of the pieces of equipment or subsystem (s) identified in the ODCM and it is confirmed that one-half of the annual dose objective will-be exceeded during the~ calendar quarter, a special report, pursuant to Tech-nical' Specification 5.16, shall be prepared and. submitted to the Nuclear. Regulatory Com-mission within 30 days of the end of the quarter during which the equipment or sub-system (s) were inoperable. This report shall include the following information:

A. Identification of equipment or sub-system (s) not operable and reasons for inoperability.

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FORT CALHOUN STATION )s $ PAGE 16 OF 31 CHEMISTRY MANUAL PROCEDURE -

CMP-6 4.1 Liauid Efflu.ents (Continued)

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

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

4.2 Gaseous _ Effluents 4.2.1 The radiation dose contributions from radioac-tive materials in gaseous effluents shall be determined, in accordance with the ODCM, on a quarterly basis. If the dose contribution, due to the cumulative release of gaseous effluents averaged over a calendar quarter exceeds one-half of the annual design objec-tives, the following course of actions shall be taken:

A. Make 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 contri-butions.

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lb r8 JlfJ FORT CALHOUN STATION ll PAGE 17 OF 31 CHEMISTRY MANUAL PROCEDURE CMP-6 4.2 Gaseous Effluents 4.2.2 The equipment or subsystem (s) of the-gaseous radwaste treatment system as identified in the ODCM shall be operable. If the radioactive gaseous wastes were discharged without treat-ment by one or more of the equipment or sub-systems (s) identified in the ODCM and it is confirmed that one-half of the annual dose objective will be exceeded during the calendar quarter, a special report, pursuant to Techni-cal Specification 5.16, shall be prepared and submitted to the Nuclear Regulatory Commission within 30 days of the end of the quarter dur-ing which the equipment or subsystem (s) were inoperable. This report shall include the following information:

A. Identification of equipment or sub-system (s) not operable and reason for inoperability.

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

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

4.3 Semi-Annual Report A report covering the operation of the Fort Calhoun

' Station during the previous six months shall be sub-mitted withinH60 days after January 1 and July 1 of each year per the requirements of 10CFR 50.36a.

The radioactive effluent release report shall include a summary of the quantities of radioactive liquid and gaseous 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 meteorclogical conditions-concurrent with the release of gaseous effluents during each quarter as outlined.in Regulatory Guide-1.21,

~ Revision 1.

The radioactive effluent release report shall include an assessme.t of radiation doses from the radioactive liquid and gaseous effluents released from the unit during each calendar quarter-as outlined in Regulatory Guide 1.21, Revision 1. The asses sment of radiation doses shall be performed in accorc ance with calcula-tional methodology of the Regulatcsy Guide 1.109, Revision 1.

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FORT CALHOUN STATION /$ PAGE 18 OF 31 CHEMISTRY MANUAL PROCEDURE - 1b CMP-6 4.3 Semi-Annual Report The radioactive effluent release report shall include any changes to the Process Control Program (PCP) or to the Offsite Dose Calculation Manual (ODCM) made during the reporting period. These changes can be initiated either by the licensee (implementation: subject to review by the PRC) or by the Nuclear Regulatory Com-mission (implementation: subject to their applicabil-ity to the Fort Calhoun Station design, review by the PRC and followed bi a review by the SARC). A level of detail commensurate to the sig:.ifiesnce of the change will be provided.

4.4 Annual F7 port The Annual Radiological Environmental Operating Report for the previous one year of operation sha). be sub-mitted prior to Mai 1 of.each year. This _eport contains the data gathered from the radio:ogical environmental monitoring program. The content of the report shall include:

4.4.1 Summarized and tabulated results of the radiological 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.

4.4.2 Interpretations and statistical evaluation of ,

the results, including an assessment of the observed impacts of the plant operation and environment.

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

4.4.4 The results of land use survey required by Part II, Section 5.1.4.

4.4.5 The results of specific activity analysis in '

which the primary coolant exceeded the limits of Technical Specification 2.1.3. . The j following information shall be included:

4.4.5.1 Reactor power history starting 48 l

hours prior to the first sample in which the limit was exceeded; 1

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-CHEMISTRY MANUAL PROCEDURE

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pAoE 19 Or 31 CMP-6 4.4 Annual Reppti (Continued) 4.4.5 4.4.5.1 A. Results of the last isotopic analysis for radioiodine per-formed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radio-iodine activity was reduced to less than the limit. Each result should include date and time of sampling and the radio-iodine concentrations; B. Purification system flow h'istory starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; C. Graph of the I-131 concentration and one other radioiodine iso-tope concentration in micro-Curies per gram.as a function of time for the duration of the specific activity above the steady-state-level; and D. The time duration when the-specific activity of the primary coolant exceeded the radiciodine limit.

4.5 Epn-Routine Report 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 is-attributable to_ plant operation, a written report shall_be submitted to the Nuclear Regulatory Commis-sion within 30 days from the end of-the quarter.

L I- The report _shall~ include an' evaluation of any release conditions, environmental factors, or other aspects necessary to explain the anomalous result.

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~PAGE 20 OF 31 '

1 lf'CP l

CHEMISTRY-MANUAL' PROCEDURE: 0 - J CMP-6 I 5.0- RADIOLOGICAL ENVIRONMENTAL MONITORING REOUIREMENTS ,

The' requirements set forth11n this Section will provide reasonable assurance that radioactive liquid and gaseous

effluent releases to the environment in and around Fort Calhoun Station are monitored and that any deviation of ,

radiationilevels above background will be identified. ,

5.1.1 The radiological environmental monitoring program shall_be conducted according to Table 4. No changes shall be made to the ODCM which might reduce the '

effectiveness of the program. Analytical results of this 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 4.4).

5.1~.2 If the_ level of radioactivity, from calculated doses, in the Semiannual Report leads to.a higher exposure

=

pathway to-individuals, this pathway shall be added to the Radiological Environmental Monitoring Program.

5.1.3 If.the level of radioactivity in an environmental sampling.mediur exceeds the reporting level specified in1 Table 7, a Non-routine Report shall be prepared and

-submitted-to the Nuclear Regulatory Commission _in a Non-routine Report (Part II, Section 4.5). The detection ca7 abilities of the equipment used_for the analysis of Environmental Samples must meet the requireinents of Table 6 for Lower Level of Detection (LLD).

5.1.4 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, andithe 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-4.4). The survey'shall be conducted under the following conditions:

A. Within a one-mile radius from the plant site, enumeration by' door-to-door or equivalent counting techniques.

l D. Within-a five-mile radius, enumeration by g using referenced information from county l agricultural agents or other reliable sources.

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• FORT CALilOUlf STATIOtt , r dg ," "p PAGE 21 OF 31 -

" CMP-6 CllEMISTRY MAliUAL PROCEDURE 5.1.4 (Continued)

D. If it is learned from this sucvoy that milk animals are present at a location which yields a calculated dose greater than from previously sampled location (s), the new location (s) shall '

be added to the monitoring program. The nam-pling locatzon(s) having the lowest calculated dose may then be dropped from ti- monitoring program at the end of the grazinj and/or grow-

, ing season during which the survey was conduc-ted and the new location is then added to the monitoring program. Also, any location (s) from which milk can no longer be obtained may be dropped and replaced if practicabic from the monitoring program and the 11uclear Regula-tory Commission shall be notified in the Annual Radiological Environmenta) Operating Report (Part II, Section 4.4).

C. Radiological Environmental Sampling locations and the media that is utilized for analysis are presented in Table S.

5.1.5 Analyses shall be performed on radioactive materials as part of an Interlaboratory Comparison Program that has been approved by the Nuclear Regulatory Commis~

sion. The results of these analyses shall be included in the Annual Radiological Environmental Operating Report.

5.1.6 Deviations from the monitoring program, presented in this section and detailed in Table 4, are permitted if specimens are unobtainable due to hazardous condi-tions, seasonal unavailability, malfur.ction of equip-ment, or if a person discontinues participation in the program and other legitimate reasone. If the equip-ment malfunctions, corrective actiono will be complete as soon as practicable. If a person no longer supplies samples, a replacement will be made. All deviations from the sampling schedule will be described in the Annual Radiological Environmental Operating Report, pursuant to cart II, Section 4.4.

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[ l g p g c, lb dd hl J3 FORT CALHOUN STATION PAGE 23 OF 31 I CHEMISTRY MANUAL PROCEDURE CMP-6 TABtt 1 Padloective ticuid Weste layling and Analysis A. Monitor & Hotel Weste f arika Releases Lower Limit of Type of Detection D)

$nnpling frequercy Activity Analysis (SCl/ml) tech Batch Principal2 jap)

Emitters ( 5.0 E 07 l 131(2) 1.0 t 06 Monthly from One Batch Dissog(Noble cases Gema 1.0 E 05 Emitters)

Monthly Cory.osite(I) h3 1.0 t 05 Cross e 1.0 t 07 Quarterly Conposite(I) tr 89, $r 00 $.0 E 08 B. Steen GmerLtor Bloisinsi Lower Limit of Type of Detection (p8 D)

Sanpling Fnquency Activity Analysis (ktl/ml)L Weekly Conposite(I)

Principe}33ganrie imitters5 5.0 E 07 l 131(5) 1.0 E 06 Monthly Dissolved Noble Cases (Game 1.0 E 05 Emitters)

Monthly Conposite(I) H3 1.0 E-05 C*ots a 1.0 E 07 Quarterly Conpoulte(I) $r 89, Sr 90 5,0 E 08 l

l l

l FC/ CMP /01 051892

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I FORT CALil0UN STATIOli  ![ jj lh }/ h PAGE 23 0F 31 i CllEMISTRY MANUAL PROCEDURE CMP-6 .

1ABLE 2 f.pdloact ve Q.gg,eous Weste lanolina arxf Analysis 8

A. Gas Decay tank Releases tower Limit of Type of Detection D)

Sampling Fregency Activity Analysis (sCt/mt)

Prior to each Principa}'Qame release Emitterst ) 1.0 E 04 B. Centeltomt Purge Releases or Cmtaltamt Pressure Relief Lirie Releases Lower Limit of frpe of Ostection 'gD )

sam ling Frequency Activity Analysis (sti/ml)

• Prlor to esch Principal' game release imitters 1.0 E 04 Prior to each release H3 1.0 E 06 C. Condmser Air Ejector Release

• tower Limit of type of Detection D)

Sam ling Frequency Activity Analysis (sti/mt)

Monthly (6) Tritita (M 3) h.0E06 Monthly Principa ame gE mitters 1.0 E 04 D. Atatillery Building Exhaust Stack and L.boratory arid Rahste Building Exhaust Stxk Lewer Limit of Type of Detection gD)

Sampling frequency (8) Activity Analysis (AC1/ml)

Weekly (Charcoat samte) 1 131 1.0 E 12 Weekly Principa uma l

l (Particulates) Emitters , 1-131 1.0 E 11 I and Particulates with half ttves t than eight days.

Monthly Com osite Cross a 1.0 E 11 f Quarterly Cceposite l (Particulates) br-89, St 90 1.0 E 11 FC/ CMP /01 OS1892 L

1

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CHEMISTRY MANUAL PROCEDURE ~ h~~ h' PAGE 24 OF 31 CMP-6 1 AEL E S 1 ard 2 (Continued)

WOTCS:

(1) LLD is defined in section 3.3, Part 1.

(2)

Gross Radioactivity is defined as the determination of r&dioactivity levels radionuclide identification and Individual isotopte quantification.

without reg ard to bg.cific G) ihe principal gamme emit'ars for which the LLD specification arpti radiorwelidest Mn 54, Fe 39, Co 58, co 60, Ind?, Mo 99, ts 134, ts- Ces escia lvelyend

, Co 14), areCe the144 following (4)

The principal radionuctides gentna emitters for which the LLD speelfication applies exclusively are the f ll Kr 87, Kr-88, Xe 133, re 133m, Xe 135, and Xe 138 f or gaseouso emissions owing and Mn 54 Co-60, 2n-65, Mo 99, Ca 134, Co 137, Ce 141, Ce 144 f or particulate emissions .

, FE-59, Co-58, (5)

A weekly grab senple and analyses program including gansna isctopic identification turbine building supp effluent when the steam generator blowdown sater corposite an lwill be initiated for the concentration is greater than 1.0 E-06 microcurle/ milliliter. a ysis indicates the 1 131 (6)

Required only wher.

microcurle/millitt s .

steam gene , tor blowdown radioactivity for tritita (f able 311 section B) exceeds M M (7)

To be representative of the everage quantities and concentrations of radioactive m t saeples should be collected in proportion to the rate of flow of the effluent streama erials in liquid effluents, sanples average taken offluent for the release. corposite should be mixed in order for .the Prior to analyses, conposite all sanple ve of the to be representa (S)

These aamples are continuously collected during the release of radiuoctive effl uents. However, releases are senples are collected using auxiliary senpling equipent.attowed to econtinue at for periods of u l

FC/ CMP /01 051892

? f* m FORT CALHOUN STATION hi C PAGE 25 OF 31 CHEMISTRY MANUAL PROCEDURE S.il:.Ud ((dJ~ [{ CMP-6 TA6Lt 3 Radiation and Environmental .onitors Operability RenJirenents Daily Monthly Quarterly $ource Check

$our Chamel Refueling Prior Chanreg) Checkg) Func. Test (3) Calibration (') Releaseg)

A. Ligald Hanitors Check (

PM 054 A/B x(') x x x x RM 055/55A 0) - X X X Dall) Monthly Quarterly Source Check Cha Sourg Channet Refueling Priorjp B. Gaseous Mtnitors CheckgI CheckLgI Func. Test (3) Calibration (') Release)

RM 043 x x x x -

RM 057 x x - X x x x x x RM 062/51(6)

Month ly Annual Operatjyns Airflow C. Envirrowitt. Manities check- ) Calibratien(0)

RM 035

• 039 x x WOTES:

(1) Docunentation is provided by signof f on OP $b5HIFT 0001.

(2) Docunentation is provided by signof f on IC ST RM 0050.

(3) Documentation is provided by signof f on IC ST-RM-0050.

(*) Doctrnentation is provided by conpletion of appropriate calibration procedure. Air or (iquid flowrote calibrations sust be included for RM-054 A/B and RM 043, RM 057, and RM 062/51.

(5) Documentation is provided by signof f on applicable Release Permit form f6) RM 051 will be substituted f or RM 062 when it is sanpling the Ausiliary Building Ventilation Stack.

(7) Docunentation is provided by signof f on IC 51 RM 0100.

(S) Dmanentation is provided by conpletion cf calibration procedure (9) Visual flowd.cck daily FC/ CMP /01 051892

t r, t1 FORT CALilOUN STATION ci i;- ,l l 'O PAGE 26 OF 31 CilF.MISTRY MANUAL PROCEDURE

!E C i,l!,? h; CMP-6 1ABLE 4 Radiological Envirorrental Monitoring Program Exposure Pathway and/or Sanple Cottection $lte(i) Types of Analysis (2) frequency

1. t erect Radiatim A. Ten ikD indicator stations, Cama 1sotopic Quarterly one control station, total of 11.

B. An inner ring of 16 stations, Game dose during site Replaced one in each meteorological Area and General Emer- Annually sector in the general area of gencies only, the site boundary and within 2.5 miles.

C. An outer ring of 16 stations, Gama dose during alte Replaced i in each meteorological Area and General Emer- Annually sector located outside of the gencies onty.

Inner rl~ hut no more dis-tant t' A A, < imaP / %

miles.

2. hie Monitoring A. Indicatto g g,p rt i) filt for Gross Veekly Bets )

1. 3 stations in t;e gentist area of the $lt: Bou Klary, 2) Charcoal for 1 131 Weekly

2. City of Blair 3) (llter f or Cama Quarterly Isotopic conposite of wkty, fitre.

B. One background station Some as A. above

3. Water A. Misoouri River at nearest Gansna Isotopic, H 3 Monthly com-downstream d. inking water posite for intake. Gama Isoto-pic Analysis B. Missouri River downstream Quarterly near the mixing zone. conposi t e f or H 3 Analysis C. Missouri River up.tream of plant inteke (background).

4. Milk (') A. Nearest famity cow when Ganina Isotopic and 1 131 Seminonthly ava able or one dairy farm grating sea-within 5 miles, son (May to October)

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

(Background)

5. Fish A. Four fish sanptes within Gama Isotopic Once per vicinity of plant discharge. season (May to October)

B. One background senple up-stream of plant discharge.

6. Sedimmt One sapple f rom downstream erea Gansna Isetopic Semiannual ly on the station side of the Missouri River.

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FORT CALilOUli STATION Li ;> (( r PAGE 27 OF 31 CilEMISTRY MA!1UAL PROCEDURE Fi  ; h + /:,\ [i ;h i CMP-6 TABLE 4 (Continued)

Radiological Envirorrnental Monitoring Program Esposure Pathway and/or Sanple Collection $lte(l) Types of Analysis (2) Frequency I

7. Vegetables or A. One sanple outside of $ Gama Isotopic Once per food ProdLxta miles. (Bac k gro'Jnd) season (May to Octoter)

8. One sanple in the highest exposure pathway.

$)

Notes (1) See inble 6 of this Manual for required detection limits.

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

(3) When a gross beta count indicates radioactivity greater than iE 12 SCl/mi or 1 pCl/m', a gansna spectret analyste will be performed.

r4, When milk sanples are not available, a broad leaf vegetation or pasture grass sompte shall be collected, when avaltable.

FC/ CMP /01 051892

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FORT CALHCUN STOTION PCGE 3o C7 31 CHEMSTRY BAtWUCL PRCCEEURE Ch8P4 I TABLE 6 Detection capabilities fer Environmental Sancte Anatysis(1)(2)(3)

Lower Limit of Detectiert (LLD)

Gross Sarote t>ni t s Beta 1,6L-3 Mn-54 Fe-59 C=-58. 60 Zn-65 2r-05 4b-95 t-131 Cs-134 Cs-137 Ba-140 Water Pci/L -- 2.0E+C3 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 Pci/kg' -- --

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

1.3E+02 1.5E+02 --

(wet) 1 Milk Pci/L -- -- -- -- -- -- -- --

1.0E+00 1.5E+01 1.8E+01 1.5E+01 Air Pci/m 3 1.0E-02 -- -- -- -- -- - --

7.0E-02 -- -- --

Particu-tate or Gases Sediment Pci/kg -- -- -- -- -- -- -- -- -

1.5E+02 1.EE+02 --

(dry)

(_

Grass or Pci/kg -- - -- -- -- -- -- --

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

Broad Leaf twet) %oi i

vegetation /

vegetables l t==,

] p 3

1'  % ,j i

r3

W (1) This list does not mean that only these nuclides ars to be consideced. Other peaks that see identifiable as plant effluents, togethee with those i of the above nuclides, shalt also be anatyred and reported in the Amust Radiological Envirorinental Survaittance Report pursuant to controt 5.1.b.

(2) Required detection capabilities for thennotiminescent dosimeters used for envirarwental measurements shall be in accordance with the reconvienda-tions of Regulatory Guide 4.13.

(3) The LLD is defined, for purposes of these specifications, as the smeltest correntration or radioactive materiet in a sancte that wilt yield a net j count, above system backgreurd. that will be detes.ted with 95% precability witts only 5% procability of falsely concluding that a blank observation i l represents a "real" signal.

For a particular measurement system, whi-h sney include radiochemical separation-4.66 s3 LLD

• E - V - 2.22E+06 - Y - exp(-AOt) l TABLE 7 l 2

FC/C,iffa4 CMP / 01 051892 t

FAGE 31 OF 31

.. FORT CALHOU STt. TION' CMP-6 CHCl!5TRY MA UAL PRN1E Reortino levels for Radioactivity Concentrations in Environmental Samtes il)

Sarole Units M-3 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 kb-95 1-131 ts-134 Cs-137 Ba-1t-0 Water Pci/L 2.0E+0i- 1.0E+03 4.0E+02 1.0E+03 3.0E+02 3.0E+02 4.0E+02 &.0E+02 2.0E+00 3.0E+01 5.0E+01 2.0E+02 Fish- Pel/kg --

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

1.0E+03 2.0E+03 --

(wet)

Mitk Pci/L -- -- -- -- -- -- -- --

3.0E+00 6.0E+01 7.0E+01 3.0E+02 Air Pci/m3 -- -- -- -- -- -- -- --

9.0E-01 -- -- --

Particulate or Cases Grass or Pci/kg -- -- -- -- -- -- -- --

1.0E+02 1.0E+03 2.0E+03 --

Broad Leaf (wet) i Vegetation /

Vegetables I.__ -

GT C~ G i'

CW'

+J

.n J

(1) A non-routine report shalt be subnitted =Aen more than one of the radionuclides Listed above are detected in de sanpling medium ord:

4 1

C reentration (1) + Concentration (2) + - - -- t 1.0 Reporting Levet (1) Reporting Levet (2)

When radionuclides cther.than tMse listed above are detected and are the result of plant ef fluents, ti.is report shall be sutstitted if the poten-tial amuel dose to a sienter of the general pthlic is equal to or geester than the dose objectives of Radiologient Ef fluent Centrol Section 1.1 and 1.2. Tais report is not required if the measured level of radioactivity was net the result of ptant effluents; however, in such an event, the condition shall be reported and described in the i.must Radiological Environmentat Operating Report.

2 FC/ CMP /01 4

7 t. p FORT CALHOUN STAT 1011 CHEMISTRY MANUAL PROCEDURE .-

j d //]

IU i'O l 5 i PAGE 1 OF 29 CMP-6 PART III RADIOLOGICAL EFFLUENT RADIATION MONITOR ChLCULATIONS FC/ CMP /01 051892

"O <

lp  ? h, FORT CALHOUN STATION a[j bgo t(. ull l: PAGE 2 OF 29 CHEMISTRY MANUAL PROCEDURE M d CMP-6 1.0 EFFLUENT MONITOR SETPOINTS 1.1 Liauld Effluentg 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 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 circulating water pump intakes d'uring winter months.

The varying dilution flowrate is accounted for in the dilution calculations for monitor tank and stream generation releases.

Alarm setpoints shall be established for the liquid effluent monitoring instrumentation to ensure that the concentration of radioactive material released in liquid effluents to unrestricted areas shall be less than the concentrations specified in 10 CFR 20, Appendix B, Table 2, Column 2.

Cs-137 is the most abundant radionuclide in 11guld efflunnt streams and is used to calibrate the liquid effluent monitors.

FC/ CMP /01 051892 l

_ ~ ~ . , . = -

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

+

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a FORT CALHOUN STATION

~

h ~h fj [p PAGE 3 OF 29 CHEMISTRY MANUAL PROCEDURE CMP-6 1.2 Licuid Effluent Radiation Monitors 1.2.1 Steam Generator Blowdown Monitors (RM-054A and B)

These process radiation detectors nionitor the flow through the steam generator blowdown lines and automatically close the blowdown isolation valves if the monitor high alarm setpoint is reached. Thu high alarm setpoint calculations are based on I controlling the discharge at 10 CFR 20 limits of 1.0E-07 #C1/ml for unrestricted areas.

The following calculations for maximum concentration. and 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 ja calculated as follows:

(1. 0E-07 pCl/ml) (X,)

Y, Where:

1.0E-07 pC1/ml = 10 CFR 20 Limit for unidentified radionuclides at site discharge (I-129, Ra-226 and Ra-228 are not present).

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 (pci/ml).

FC/ CMP /01 051892

b 1

.

I o i >m FORT CALHOUN STATION CHEMISTRY HANUAL PROCEDURE IJ [y[ f h' PAGE 4 OF 29 CMP-6 1.2.1 Steam Generator Blowdown Monitors (RM-054A and B) (Continued)

The high alarm setpoint (CPM) =

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

Where:

.85 = Correction factor for instrument meter error.

Sp = Detector sensitivity factor (CPM /pCi/ml). (Sensitivity based on Cs-137).

A, = Maximum allowable blowdown line accivity (pCi/ml).

B = Background (CPM).

Setpoints may be recalculated based on adjusted 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.

1.2.2 Overboard Discharge Header Monitor (RM-055 or RM-055A)

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 discharge tunnel. The concentration of activity at discharge is controlled below the 10 CFR 20 limit of 1.0E-07 pCi/ml for unrestricted areas for unidentified isotopes by the high alarm setpoint which closes the overboard flow control valve.

The following calculations for maximum concentration and alarm setpoints are valid when Monitor Tank discharge is the only liquid <

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

i FC/ CMP /01 051892

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

t r 1 to FORT CALHOUN STATION f)' 9 PAGE S OF 39 i CHEMISTRY MANUAL PROCEDURE 1 I -

CMP-6 1.2.2 Overboard Discharge Header Monitor (RM-055 or RM-055A) (Continutd) l The maximum _ allowable concentration in the overboard discharge header ist (1.0E-07 pCl/ml) (X,)

Y, Where:

1.0E-07 pLi/ml = 10 CFR 20 Limit for unidentified radionuclides at site discharge (I-129, Ra-226 and Ra-228 are not present).

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, = Maximum monitor tank dischargo flow rate (gpm). (Normal monitor tank maximum flow is 50 gpm. Other flow rates may be used, as required.)

A, = Maximum allowable activity in discharge header (pci/ml).

FC/ CMP /01 051892-

T' () P';

EP FORT CAL 110Ull STATION g> g-)  ; PAGE 6 OF 29

,~f a

l CMP-6 CllEMISTRY MANUAL PROCEDURE t 1.2.? Overboard Discharge ficador Monitor (RM-055 or RM-OSSA) (Continued)

The high alarm setpoint (CPM) =

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

Wheret

.85 = Correction factor for instrument meter error.

S,i = Detector sensitivity factor (CPM /pci/ml). (Sensitivity based on Co-137).

A, = Maximum allowable concentration ,

in discharge header (pCi/ml).

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, m

FC/ CMP /01 051892

FORT CALHOUN STATION 't , Il

[I jlj /70 O PAGE 7 OF 29 CHEMISTRY MANUAL PROCEDURE ej f Jh d CMP-6 1.3 Gaseous Effluents The gaseous effluent monitoring instrumentation for controlling and monitoring normal radioactive material i

releases in accordance with 10 CFR 20, appendix B, Table 2, Column i limits for unrestricted areas ,

(sec Figure 1), are summarized as follows: t A. Angiliary Buildina - The Auxiliary Building Exhaust Stack receives discharges from the waste gas decay tanks, contain-ment purgo, containment vent systems and the auxiliary building ventilation system.

Effluents are monitored by RM-062, a noble gas activity monitor. Additionally, noble ,

gas activity monitor, RM-051, provides redundant back-up monitoring capabilities to the RM-062 monitor. Iodine monitoring and sampling capabilities are provided by RM-060. Particulate monitoring is provided by RM-061. Redundant particulate monitoring is provided by RM-050. Ven-tilation_ Isolation 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 Process-ing_Buildina (LRWPB) - Noble gas, iodine, and particulate monitoring is provided by Radiation Monitors RM-043, RM-042, and RM-041, respectively. These radiation monitors do 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 solpoint on RM-057 will activate isolation of main steam to the Auxiliary

! Steam System.

i-p A gaseous radioactive wacte flow diagram with the applicable, associated radiation monitoring instru-mentation and controls is presented as Figure 4. The gaseous waste disposal system is presented in Figure 1 5. A detailed discussion of the gaseous effluent treatment system is presented in Section 2.2.

l l

FC/ CMP /01 051892 1

Fl j'; '

FORT CALHOUN STATION IJ tl7[ PAGE 8 0F 39 Ljg b C!!EMISTRY MANUAL PROCEDURE -

CMP-6 1.4 GAggg31s EfflutDt Radiation Monitors 1.4.1 Au.v.ilfary Building Exhaust Stack Particulate Monitors (,1M-061/RM-050)

Either of these monitors may be used to measure airborne particulate activity in the exhaust stack. The detector is located adjacent to a section of moveable filter paper ca e capstan drive. The monitor alarm setpoint is based on 10 CFR 20 limits of 1.0 E-10 pC1/cc at the site boundary.

The following calculations for maximum release rate and alarm setpoint are valid when the Auxiliary Building Exhaust Stack is the only gaseous release pathway. For simultaneous gaseous-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 particulates is calculated as follows:

(1. 0E-10 pcl/cc) x (1. 0E+06 cc/m3 ) = 2. 0E+01 p Cl/sec (5. 0E-06 sec/m )3 Where:

1.0E-10 #Ci/cc = 10 CFR 20 Limit at site boundary for unidentified isotopes.

5.0E-06 sec/m8 = Annual average dispersion factor at the site boundary.

1.0E+06 cc/m8 = Constant of unit conversion.

The high alarm setpoint (CPM):

( 2 . 0 E4u-a (S,.) ( F,) ( T)

Setpoint = .85 ( +B)

(Fy)

FC/ CMP /01 051892 L

f 'A 7 ta FORT CALHOUN STATION CHEMISTRY MANUAL PROCEDURE

~[L

' 'f L PAGE 9 OF 39 CMP-6 1.4.1 Auxiliary Building Exhaust Stack Particulate Monitors (RM-061/RM-050) (Continued)

Where:

.85 = Correction for instrument meter error.

Sp = Detector sensitivity factor (CPM /yC1). (Sensitivity based on Cs-137).

F, = Monitor sample flow rate (SCFM).

T = Effective monitor response time (sec). .

F, = Auxiliary Building Exhaust stack flow rate (SCFM). (Default maximum flow rate is 122500 cfm for 3 Aurl lary Building exhaust fans and 2 containment purge fans in operation. 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 b3 identified, prior to exceeding the alarm setpoint.

FC/ CMP /01 051892

p ru FORT CALHOUN STATION CHEMISTRY MANUAL PROCEDURE

'f]

u , Tj [R

'Jg /]f '[ PAGE 10 OF 30 CMP-6 1.4.2 Auxiliary Building Exhaust Stack Gaseous Activity Monitors (RM-062/RM-051)

Either of these monitors may ba-used to measure gaseous activity in the exhaust stack.

The gav is monitored after passing through a 7 articulate filter. The monitor controls gaseous activity releases so that the 10 CFR 20 limit for the unrestricted areas of 3.0E-07 yCi/cc, based upon Xo-133, is not exceeded. The Ventilation Isolation Actuation Signal is initiated when the high alarm setpoint is reached.

The following calculations for maximum release rate and alarm setpoint are valid when Auxiliary Building Exhaust Stack is the only gaseous release pathway. For simultaneous gaseous releases from Auxiliary Building Exhaust Stack, condenser off-gas and the LRWPB Exhaust Stack, refer to Section 1.3.2.

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

(3. 0E-07 pCl/cc) x (1. 0E+06 cc/m ) = 6. 0E+04 pCl/sec 3

(5. 0E-06 sec/m ) 3 Where:

3.0E-07 yCi/cc = 10 CFR 20 Limit at site boundary (based upon Xe-133).

5.0E-06 sec/m3 = Annual average dispersion factor at the site boundary.

1.0E+06 cc/m3 = Constant of unit conversion.

The high alarm setpoint (CPM):

(6. 00E+ 04 ) (S,) (60)

Setpoint = . 85 ( +B) l l

FC/ CMP /01 051892

. _ ~ . . - . . =. -

FORT CALHOUN STATION bl PAGE 11 OF 29 CHEMISTRY MANUAL PROCEDURE wh Jb N1.J] O CMP-6 1.4.2 Auxiliary Building Exhaust Stack Gaseous Activity Monitors (RM-062/RM-051) (Continued)

Where:

.85 = Correction for instrument motor error.

Sp = Detector sensitivity factor (CPM / yC1/cc). (Sensitivity based on Xe-133) 60 = Conversion (seconds to minutes).

28317 = Conversion factor (ft* to cc).

F, a 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.

FC/ CMP /01 -051892

FORT CAIJIOUN STATION M f PAGE la OF 29 CHEMISTRY MANUAL PROCEDURE []l .][j i J CMP-6 1.4.3 Auxiliary Building Exhaust Stack Iodine Monitor (RM-060)

RM-060 conitors the gaseous waste discharged from the exhaust stack for Iodine-131 activity by continuously counting a charcoal cartridge and pre-filter through which a sample of exhaust stack air is passing at a known rate.

The monitor alarm setpoint is based on the 10 CFR 20 limit for Iodine-131 at the site boundary.

The following calculations for maximum release rate and alarm setpoint are valid when Auxiliary Building Exhaust Stack is the only gaseous release pathway. .For simultaneous gaseous 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 iodine is calculated as follows:

(1. 0E-10 pCi/cc) x (1. 0E+06 cc/m3 ) = 2. 0E+0i pCl/sec (5. 0E-06 sec/m )3 Where:

1.0E-10 #Ci/cc = 10 CFR 20 Limi at site boundary (based upon I-131).

5.0E-06 sec/m8 = Annual average dispersion factor at site boundary.

1.0E+06 cc/m8 = Constant of unit conversion.

The high alarm setpoint (CPM):

(2.0E401) (Sp ) (F,) ( T) (E)

+B)

Setpoint = . 85 l y FC/ CMP /01 051892

'O q ~j t - 3 U'

$ k PAGE 13 OF 29 FORT CALHOUN STATION l

,% . CHEMISTRY MANUAL PROCEDURE i I I - CMP-6 1.4.3 Auxiliary Building Exhaust Stack Iodine Monitor (RM-060) (Continued)

Where:

.85 = Correction for instrument meter error.

Sp = Detector sensitivity factor (CPM /pci). (Sensitivity based on I-131)

F, = Monitor sampic flow rate (SCFM).

T = Effective monitor response time (sec).

F, = Auxiliary Building Exhaust stack flow rats iSCFM). (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.) )

E = Charcoal filter collection efficiency.

B = Background (CPM).

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

'l L

DFC/ CMP /01- 051892-

FORT CALHOUN STATION CHEMISTRY MANUAL PROCEDURE fl b ]b - ( ..

PAGE 14 CF 29 CMP-6

1. 4 . 4 - 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 for unrestricted areas of 3.0E-07 #Ci/cc, based upon Xe-133, is not exceeded.

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

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

( 3 . 0 E- 07 p Cl / ce' x ( 1. 0 B+ 06 cc/m 3 ) = 0 . 0 E+ 04 pCl/sec (5.0E-06 sec/m ) 3 Where:

3.0E-07 pCi/cc = 10 CFR 20 Limit at site boundary (based upon Xo-133).

5.0E-06 sec/m3 = Annual average dispersion factor at the site boundary.

1.0E+06 cc/m8 = Constant of unit l conversion.

l The high alarm sctpoint (CPM):

(6.00E604) (Sp) (60)

Se tpoin t = . 85 ( +B )

(Fy) (28317) l l

FC/ CMP /01 051892

1

? r c, FORT CALHOUN' STATION 7,

' PAGE 15 OF 29 CHEMISTRY MANUAL PROCEDURE _s h o.'lb'

. I _

CMP-6 1.4.4 Condenser Air Ejector Monitor (RM-057)

(Continued)

Where:

. 85 = Correction for .4 c' iment meter error.

Sp = Detector sensitivity factor (CPM /pci/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 f2ow 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-970. s E

l-l LFC/ CMP /01 051892

\.-

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l FORT CALHOUN STATION / PAGE 16 OF 39 CHEMISTRY MANUAL PROCEDURE .s 3b ] _ CMP-6 1 1.4.5 Laboratory and Radioactive Waste Processing Building (LRWPB) Exhaust Stack Particulate Monitor (RM-041)

This monitor is used to measure airborne particulate activity in the LRWPB exhaust stack. The detector is located adjacent to a removable filter paper. The monitor alarm setpoint is based on 10 CFR 20 limits of 1.0E-10 #C1/cc at the site boundary.

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

The maximum allowable re2 ease rate for stack particulates is calculated as follows:

(1. 0E-10 pcl/cc) x (1.0E+06 cc/m 3) = 2. 0E+01 pCl/sec (5.0E-06 sec/m ) 3 Where

-1.0E-10 pC1/cc = 10 CFR 20 Limits at site boundary for unidentified isotopes.

5.0E-06 sec/m3 = Annual average dispersion factor at the s}te boundary.

1.0E+06 cc/m> = Constarit of unit conversion.

The high alarm setpoint (CPM):

( 2 . 0E+ 01) (S p ) (F) ( T)

Se tpoin t = . 85 l +B]

(Fy)

FC/ CMP /01 051892

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

I-- 7 c3 PAGE 17 OF 39 FORT CALHOUN STATION CHEMISTRY MANUAI, PROCEDURE f . J h

CMP-6 1.4.5 Labcratory and Radioactive Waste Processing Building (LRWPB) Exhaust Stack Particulate Monitor (RM-041) (Continued)

Where:

.85 = Correction for instrument meter error.

Sy = Detector sensitivity factor (CPM /pCi). (Sensitivity based on Cs-137).

F, = Monitor sample flow rate (SCFM).

T = Effective monitor response time (sec).

F, = LRWPB Exhaust stack flow rate ,

(SCFM). (Default maximum 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 alarm setpoint so that significant increases in activity will be identified, prior to exceeding the alarm setpoint.

This monitor alarms in the Control Room.

There are no automatic control functions associated with the actuation of the alarm.

FC/ CMP /01 051892

FORT CALHOUN STATION.

CHEMISTRY MANUAL PROCEDURE fff as JL v1 ,

I'

-PAGE 18 OF 39 CMP-6 1,4.6 Laboratory and nadioactive Waste Processing Building Exhaust Stack Iodine Monitor (RM-042)

RM-042 monitors the gaseous waste discharged from the LRWPB for Iodine-131 activity by continuously counting a charcoal filter cartridge through which a sample of LRWPB exhaust air is passing at a known rate.

The morsitor alarm setpoint is based on the 10 CFR 20 ?imit for Iodine-131 at the site boundary.

The following calculations for maximum release rate and alarm setpoint are valid when LRWPB Exhaust Stack is the only gaseous release pathway. For simultaneous gaseous 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 iodine is calculated as follows:

(1.0E-10 pCi/cc) x (1.0B+06cc/m ) r 2,0E+01 pCl/sec l

(5.0E-06 sec/m ) 3 Where:

1.0E-10 pCi/cc = 10 CFR 20 Limit at site boundary (t-sed upon I-131).

5.0E-06 sec/m 3 = Annual average dispersion factor at the site boundary.

-1.0E+06 cc/mi = Constant of unit conversion.

The high alarm setpoint (CPM):

( 2 . 0 E+ 01) ( S,.) (F) (T) (E) +B1 Setpoinc .85 l (Fy) 1 FC/ CMP /01 051891

" ' -x rs -

' FORT CALHOUN STATION [j $ b ,,_ PAGE 19 OF 39 CHEMISTRY MANUAL PROCEDURE 1'dlb ~

d CMP-6

1. 4 . 6 - Laboratory and Radioactive Waste Processing Building Exhaust Stack Iodine Monitor (RM-042).

(Continued)

Where:

.85 = Correction for instrument meter error.

Sp = Detector sensitj ;'y factor (CPM /pci) . (SensD tity based on I-131)

F, = Monitor sample flow rate (SCFM).

T = Effective monitor response time (sec).

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

E = Charcoal filter collection efficiency.

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.

l This monitor alarms in the Control Room.

There are no automatic control functions associated with the actuation of the alarm.

Il l-l L

l l

FC/ CMP /01 051892

? ra FORT CALHOUN STATION J , A PAGe 20 OF o.e CHEMISTRY MANUAL PROCEDURE -

CMP-6 1.4.7 Laboratory and Radioactive Waste Processing Building Exhaust Stack Noble Gas Monitor (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 site boundary.

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

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

-(3 0E-07 pCl/cc) x (1. 0E+06 'c/m3 ) = 6.0E+04 pCi/sec (5.0E-06 sec/m ) 3 Where:

3.0E-07 pCi/cc = 10 CFR 20 Limit at site boundary (based upon Xe-133).

5.0E-06 sec/m3 = Annual average dispersion factor at the site boundary.

1.0E+06 cc/m3 = Constant of unit

' conversion.

The high alarm setpoint (CPM):

(6 . 00 E+ 04 ) (Sg ) (60)

Se tpoln c = . 8 5

[ +B)

(Fy) (28317) i FC/ CMP /01 051892

FORT CALHOUN STATION CHEMISTRY MANUAL PROCEDURE .__,

kjlj iM h [5 _

PAGE 21 OF 29 CMP-6 1.4.7 Laboratory and Radioactive Waste Processing Building Exhaust Stack Noble Gas Monitor (RM-043) (Continued)

Where:

.85 = Correction for instrument meter error.

Sp = Detector sensitivity factor.

(CPM /pCi/cc). (Sensitivity based on XE-133) 60 = Conversion'(seconds to minutes).

28317 = Conversion factor (ft* 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).

This monitor alarms in the Control Room.

There are no automatic control functions associated with the actuation of the alarm.

T W

FC/ CMP /01 051892

~' c7 0

FORT CALHOUN STATION h $ PAGE 22 OF 29 CHEMISTRY MANUAL PROCEDURE ~' A -

CMP-6 1.5 Simultaneous Release Pathways 1.5.1 Liquid Release Pathways The liquid radiation monitors (RM054A and B, RM055, and RM055A) control liquid releases so that 10 CFR 20 limits of 1.0E-07 pCi/ml for unidentified isotopes in unrestricted areas are not exceeded. There are two liquid release pathuays that contribute to the con-centration at discharge to unrestricted areas.

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 unre-stricted area concentration limits are not exceeded.

The calculations for the alarm setpoints for the liquid effluent monitets will be adjusted as follows:

A, = K, A, + K1 A 1

K, (1. 0E-07 p Ci/< ~ ' (X,) K -(1. 0E-07 pCi/ml) (X,)

1

• Y1 Y,

Where:

A, = 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)

Ai= Maximum allowable concentration in Monitor Tank Discharge Line (pCi/ml)

K, = Proportionality constant for' Steam Generator (See Table 1)

Ki= Proportionality constant for Monitor Tank (See Table 1) l X, = Total dilution flov in Disch..rge l Tunnel (GPM) l FC/ CMP /01 051892

}'

FORT CALHOUN STATION d JU 'f,,,PAGE23OF29 CHEMISTRY MANUAL PROCEDURE CMP-6 f 1.5.1 Liquid Release Pathways (Continued)

Where:

Y, = Steam Generator Blowdown flowrate (GPM)

Yi= Monitor Tank Discharge flowrate (GPM)

The High Alarm Setpoint for Steam Generator Blowdown monitors, RM054A and B, will then be:

Alarm Setpoint (CPM) = . 8 5 ( K, S,,, A, + B,1 ---

The High Alarm Setpoint for Monitor Tank Discharge monitors, RM055 and 55A, will then be:

Alarm Setpoint (CPM) =.85 ( K1 S,,, A +B) 1 t Where:

Sr. = Detector Sensitivity factor for RM054A/B, CPM /(pCi/ml), based on Cs-137.

Sri = Detector Sensitivity factor for RM055/55A, CPM /(pCi/ml), based on Cs-137.

~

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

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

B, = RM054 A or B background countrate. (CPM)

Bi = RM055 or 55A background countrate. (CPM)

FC/ CMP /01 051892

' 7 c7 7)

! FORT CALHCUN STATION ~' J] PAGE 24 OF 39 CMP-6

~

} CHEMISTRY MANUAL PROCEDURE 1.5.1 Liquid Release Pathways (Continued)

Where:

K. , Ki= Proportionality constants.

See Table I.

1.5.2 Gaseous Release Pathway The gaseous radiation monitors (RM041, RM042, RM043, RM057, RM060, RM061, and RM062) control gaseous releases so that 10 CFR 20 limits of 3.0E-07 pCi/cc for gases and 1.0E-10 pCi/cc for iodines and particulates in unrestricted areas are not exceeded. There are three pathways that contribute to the concentration at site boundary. Titese are the Auxiliary Building Exhaust Stack, Condenser Off-gas, and the LRWPB Exhaust Stack. When rare than one pathway is utilized for radioactive releases, it is necessary to adjust the alarm setpoints given in Section 1.4 to ensure that unre-stricted area concentration limits are not exceeded.

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

The maximum allowable release rates for simultaneous releases is:

\

Conc, Max. Release Ra te = } K R, = }K j i 2.o i.o X/O Where:

R= RM061/RM050 release rate (pCi/sec)

Ri = RM062/RM051 release rate (pC1/sec)

R2 = RM060 release rate (pCi/sec)

R3 = RM057 release rate (pCi/sec)

R4 = RM041 release rate (pCi/sec)

R5 = RM042 release rate (pCi/sec)

R6 = RM043 release rate (pCi/sec)

E, - K 6 = Proportionality constants. See Table 1.

Conc;= Radionuclide concentration for the monitor of interest.

FC/ CMP /01 051892

FORT CALHOUN STATION PAGE 25 OF 29 CHEMISTRY MANUAL PROCEDURE CMP-6 1.5.2 Gaseous Release Pathway (Continued)

The maximum release rate is then:

K,(1. 0E-10 pCi/cc) K (3. 0E-07 Ci/cc) 3 K (1. 0E-10 pCi/cc 2

5. 0E-06 sec/m3 5.0E-06 sec/m 3 5.0E-06 sec/m3 K 3 (3,0E-07 pCi/cc) K, (1. 0 E-10 p Ci / cc) K 3 (1. 0E-10 pCi/cc) 5.0E-06 sec/m 3

5. 0E-06 sec/m 3

5. 05-06 sec/m 3

,Ks (3. OE-07 pCi/cc) ] 1.0E+06 cc = Max. Release Rate -

3 5.0E-06 sec/m 3 m

The alarm setpoints for the gaseous effluent monitors will then be:

RM061/50 = . 85 lKo +B)

E,v RM062/51 = . 85 { K1 Fy (28317 RM060 = . 8 5 lK2

+B)

E v RMO57 = .85 [K +B}

3 (Fy) (28317)

RM041 = . 8 5 lK4 +B3

( Fy)

RM04 2 = . 2 5 [ K, +B]

(Fy)

RM04 3 = . 8 5 [ K6 +B]

(Fy) (28317)

Where:

FC/ CMP /01 051892

? p 7 r7 FORT CALHOUN STATION )" n$ PAGE 26 OF 29 CHEMISTRY MANUAL PROCEDURE j

f- CMP-6 l

1..S.2 Gaseous Release Pathway (Continued) 1

.85 = Correction factor for instrument meter error.

Ko - K6 = Proportionality contents. See Table 1.

Sp = Detector sensitivity factor.

Fs

= Monitor sample flow rate.

T = Effective monitor response time.

E = Charcoal filter collection efficiency.

Fy = Vent stack flowrate. (Condenser off-gas flowrate for RM057, LRWPB Exhaust stack flow rate for RM041/42/43, Auxiliary Building Exhaust Stack flow rate for RM061/50, 62/51 and 60).

B = .tonitor background count rate.

60 = Constant of unit conversion (60 sec/ min).

1 t-FC/ CMP /01 051892

m o 7 ra FORT CALHOUN STATION I

f b PAGE 27 OF 29 1 J _

CMP-6 CHEMISTRY MANUAL PROCEDURE TABLE 1 Proportionally Constants for~ Simultaneous Release Pathways

a. Liquid Effluents Ko + Ki 51 Ko = .30 RM054A/B Ki = .70 RM055/55A

b. Gaseous Effluents 4 F $1 4

Ko = . 0 5 RM061/50 K.=

i .40_ RM062/51 K2 = .35 RM060 K3 = .05 -RM057 K4 = .05 RM041 K5 = .05- RM042 K6 = .05. RM043 NOTE: The constants are based on prior knowledge and may be updated as necessary to provide for plant operations.

i j

I' FC/ CMP /01 051892

T iP FORT CALHOUN STATION Ub d j( U@ '7j PAGE 28 OF 29 CHEMISTRY MANUAL PROCEDURE CMP-6 2.0 RADIOACTIVE WASTE TREATMEriT SYSTEM 2.1 Liould Radwaste Treatment System The major equipment or subsystem (s) of the liquid radwaste treatment system arc comprised of the waste filters,-monitor tanks, and evaporator. This equip-ment, including associated pumps,-valves and piping, j is used in different combinations on an as-needed l basis to process the liquid effluent to provide compliance with the as low as is reasonably achievable philosophy and the applicable section of 10 CFR Part

20. The liquid radwaste treatment system is described in Section 11.1.2 of the USAR. For effluent release points and monitor locations refer to P&ID's 11405-M-100, M-9 and M-8.

A filtration /lon exchange (FIX) system may be utilized for processing liquid radwaste in the event the waste evaporator is not in service. The system consists of a booster pump, charcoal pretreatment filter, and pressure vessels containing 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 l those occasions when considered necessary, otherwise the flows from the low activity fluids may bypass the filters. No credit for decontamination factors (iodines, Cs, Rb, others) was taken for these filters during the Appendix I dose design objective evalua-tion; therefore, the inoperability of these filters does not affect the dose contributions to any indivi-dual in the unrestricted areas via liquid pathways.

The inoperability of waste filters will not be considered a reportable event in accordance with Specification 2.9.1(1)c.

i 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 Specification 2.9.1(1)c l

within 30 days.

L The quantity of radioactive material contained in each l

unprotected outdoor liquid holdup tank shall not i exceed 10 curies, excluding tritium and dissolved or entrained noble gases.

FC/ CMP /01 051892

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

7 r7 Ol 70 b b PAGE 29 OF 29 FORT CALHOUN STATION f CHEMISTRY MANUAL PROCEDURE d 1] m .I - CMP-6 2.2 Gaseous Radwaste Treatment System The waste gases at Fort Calhoun Station are collected in the vont header where the gas compressors take suction, compress the gas and deliver it to one of the four gas decay tanks. The waste gases are treated in these gas decay tanks by holding the gases for radioactivo decay prior to finel controlled release to the environs. In order to prov2de conformance with the dose design objectives, gas decay tanks are nor-mally stored for approximately 30 days, with earlier release allowed to support plant operation onl; and thus achieve decay of short half-life radioactive materials, e.g., I-131, Xe-133. If the radioactive gaseous wastes from the gas decay tanks are discharged without processing in accordance with the above condi-tions, a special report shall be submitted to the Commission pursuant to specification 2.9.1(2)c.

The radioactive effluents from the controlled access area of the auxiliary building are filtered by the HEPA filters in the auxiliary building ventilatLon system. If the radioactive gaseous wastes are Cis-charged without the HEPA filters, a special report shall be submitted to the NRC pursuant to Specifi-cation 2.9.1(2)c.

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 Appendix I dose design evaluation and doses through the gaseous pathways were well below the design objectives. The unavailability of hydrogen purge filters will not be considered a reportable event as per Specification 2.9.1(2)c.

The containment air is processed through at least one of the redundant containment HEPA and charcoal filters in-the Containment air Cooling and Filtering 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 Specification

2. 9.1 ( 2 ) c .

The gaseous 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.

FC/ CMP /01 051892

1

-FORT CALHOUN STATION y 3' 2M PAGE 1 OF 43 CHEMISTRY MANUAL PROCEDURE 1 _i) pj f_ CMP-6 n

PART IV RADIOLOGICAL EFFLUENT MONITORING CALCULATIO?!B FC/ CMP /01 051892

FCRT CALHOUN STATION T id -

PAGE 2 OF 43

.C3EMISTRY MANUAL PROCEDURE fj U

[P C1 CMP-6 1.0 EFFLUENT CONCENTRATION LIMITS - 10 CFR 20-1.1 Liauid Effluent Concentration Limits 1.1.1 10 CFR 20 limits the concentration of radio-active material in liquid effluents (after dilution in the Circulating Water System) to less than the concentrations as specified in Appendix B, Table 2, Column 2 for radionu-clides other than noble gases. Noble gases are limited to a diluted concentration of 2.0E-04 pCi/ml. Gross a3pha activity is limited to 3.0E-08 pCi/ml. Release rates are controlled and radiation monitor alarm set-points are established as addressed above to ensure that these concentration limits are not exceeded. For batch releases (Monitor and Hotel Waste Tanks and Steam Generators) and for continuous releases (Steam Generator Blowdown), the analyses will be performed in ,

accordance with Table 1 of the Radiological Effluent Controls and the concentration of each radionuclide at the point of discharge will be calculated, based on the following equation:

Radionuclide concentration at Site Boundary:

C, f 1" y+t andf]ai / NPC; 1*1 Where:

a.' = concentration at the point of discharge for nuclide, i, in pCi/ml.

C. = . concer.tration of nuclide, i, in the undiluted effluent in pCi/ml.

f' = total undiluted effluent flowrate, in gpm.

F = total dilution water flowrate in gpm.

FC/ CMP /01 051892

C7 PAGE 3 OF 42 FORT CALHOUN STATION 0 g CHEMISTRY MANUAL PROCEDURE }[U ~y)

_, 7t _

CMP-6 1.2 Liould Effluent Concentration Limits (Continued)

MPC, = maximum permissible concentration for nuclide, i, per 10 CFI 20, Appendix B, Table 2, Column 2.

1.3 Gas Effluent Concentration Limits 10 CFR 20 limits the concentration at the site boun-dary, due to noble gas releases, to less than Appendix B, Table 2, Column 1, values for unrestricted areas.

Radiation monitor alarm setpoints are established to ensure that these release limits are not exceeded. In the event a gaseous release from the station result in an alarm setpoint being exceeded, an evaluation of the site boundary concentration resulting from the release will be performed:

To determine the concentration and MPC fraction summa-tion at site boundary, the following equations will be used:

a3 = Ko Og lx/ 0) and 2-1 ) a /MPC s1 s 3 Where:

ai = Concentration of radionuclide, i, at site boundary ,

K, = Constant of unit conversion. (1E-6m 3

/cc)

MPC i = Maximum permissible concentration (10 CFR 20, Appendix B, Table 2, Column 1 value for radionuclide, i)

Q, = The release rate of radionuclides, i, in gaseous effluents from all vent releases (in pCi/sec.)

(x/Q) =

SE-6 sec/m'. For all vent releases.

The highest calculated annual aver-age relative concentration for any area at or beyond the unrestricted area boundary FC/ CMP /01 051892

[ f PAGE 4 OF 42 FORT CALHOUN STATION CMP-6 CHEMISTRY MANUAL PROCEDURE 4 ub s. J 1.2 Gas Effluent Concentration Limits (Continued)

As appropriate, e'multaneous releases from the Auxili-ary Building Vent.Tation Stack, Laboratory and Rad-waste Building Stack and condenser off gas will be considered in evaluating compliance with the release rate limits of 10 CFR 20. Monitor indications (read-ings) may be averaged over a time period not to exceed 15 minutes when determining noble gas release rate based on correlation of the monitor reading and moni-tor sensitivity. Historical annual average dispersion parameters, as presented in Table 3, may be used for evaluating the gasecus efflilent donc rate.

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 LIMITS 2.1 Licuid Effluent Dose Calculations Three pathways for human exposure to liquid releases from FCS to the Missouri River exists: 1) fish, Fish

2) drinking water, and 3) Shoreline depos.ition.

are considered to The be taken from the vicini: of the plant discharge. drinking water for 01v"a is located 19 miles downstraam from FCS. The allution factor for this pathway is derived from the Revised Environmental Report for FCS, (1974), (page 4" -e9 and 4-31) . This report states that during Low-Low river conditions, the concentration at Omaha's water intake will be $14% of the concentration at discharge from FCS. This equates to a dilution factor of 7.14, which is used to calculate the dose to an individual from liquid pathways. All pathways combine to give the dose to an individual in unrestricted areas.

10 CFR 50, App. I restricts the dose to individuals in the unrestricted areas from radioactive materials in liquid effluents from the Fort Calhoun Station to the following limits:

• during any calendar quarter

$1.5 mrem to total body

$5,0 mrem to any organ and FC/ CMP /01 051892

~

FORT CALHOUN STATION CHEMISTRY MANUAL PROCEDURE T i)

J[j g 1]

j C'

PAGE 5 OF 42 CMP-6 f n 2.1 Liould Effluent Dose Calculation (Continued) e during any calendar year 5 3.0 mrem to total body 5 10.0 mrem to any organ The following calculational methods shall be used for determining the dose or dose commitment from liquid effluents.

Epses from Liould Effluent Pathways A. POTABLE WATER

• f" 1 1Oj ,jpjexp ( -kiyt )

R,p3= 1100 D where:

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

U, u is a usage factor that specifies the exposure time or intake rate for an individual of age group a associated with pathway p, in hr/yr, t/yr or kg/

yr. Table 5 M, = is the mixing ratio (reciprocal of the dilution factor) at the point of exposure or the point of withdrawal of drinking water or point of harvest of aquatic food), dimensionless. Table 3 F = is the flow rate of the liquid effluent, in f t 3/

sec.

Qi = is the release rate of nuclide 1, in Ci/yr.

D,,j = is the dose factor specific to a given age group a, radionuclide i, pathway p, and organ j which car. be used to calculate the radiation dose from an inteke of a radionuclide, in mrem /pCi or from exposule to a-given concentration of a radionu-clide in sediment, expressed as a ratio of the dose rate (in mrem /hr) and the areal radionuclide concentration (in pCi/m )2 . Tables 11-14 l A, = is ene radioactive decay constant of nuclide i, in hr d.

l l t, = is the average transit time required for nuclides

! to reach the point of exposure. For internal i

FC/ CMP /01 051892 l

. FORT CALHOUN STATION' T' PAGE 6 OF 43 CHEMISTRY MANUAL PROCEDURE l D

n $ ] ra CMP-6 O J n [

D2ses from Licuid Effluent Pathways (Continued)

-dose, t,= is the total time elapsed between release of the nuclides and ingestion of food or water, in hours. Table 15 1100 = Constant (pCi

• yr * /Ci

• sec

• L)

B. AQUATIC FOODS R,py = 1100 OgB ipD,jpyexp(~Xstp)

'f' 2-1 Where:

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

U, = is a usage factor that specifies the exposure time or intake rate for an individual of age group a associated with pathway p, in hr/yr, t/yr or kg/yr. Table 5 M, = is the mixing ratio (reciprocal of the dilution factor) at the point of exposure or the point of withdrawal of drinking water or point of harvest

.of1 aquatic food), dimensionless. Table 3 F = is the flow rate of the liquid effluent, in 3

, f t /sec.

! Qi = is the release rate of nuclide i, in Ci/yr.

l l B, = is the equilibrium bioaccumulation factor for l nuclide i in pathway p, expressed as the ratio of l the concentration in biota (in Pci/kg) to the radionuclide concentration in water (in Pci/ liter), in liters /kg. Table 2 D,93 = 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 or from exposure to a given concentration of a radionu-clide in sediment, expressed as a ratio of the

. dose rate (in mrem /hr) and the areal radionuclide concentration (in pCi/m )2 . Tables 11-14 A; = .is the radioactive decay constant of nuclide i, in hr d.

FC/ CMP /01 051892 l

FORT CALHOUN STATION CHEMISTRY MANUAL PROCEDURE  ;,

if,QJff f] 9[ PAGE 7 OF 42 CMP-6 Doses from Liauld Effluent Pathways B. AQUATIC FOODS ,

i Where: (con't) t,

= is the average transit time required for nuclides to reach the pojnt of exposure. For internal dose, t, is the total time elapsed between release of the nuclides and ingestion of food or water, in hours. Table 15 1100 = Constant (pCi

• yr

• f t 3 /Ci

• sec

• L)

C. SHORELINE DEPOSITS R,py = 110, 0 0 0 OjTjpD,jpy [exp (- jp A e ) ] [1-exp (-Af t3) }  ;

21 l

Where:

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

U,, = is a usage factor that specifies the exposure time or intake rate for an individual of age group a associate.. with pathway p, in hr/yr, t/yr or kg/yr. Table 5 M, = is the mixing ratio (reciprocal of the dilution factor) at the point of exposure or the point of withdrawal of drinking water or point of harvest of aquatic food), dimensionless. Table 3 F = is the flow rate of the liquid effluent, in f t /sec.

3 Q, = is_the release rate of nuclide i, in Ci/yr.

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

D,y,; = 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 or from exposure.to a given concentration of a radionu-clide in sediment, expressed as a ratio of the dose rate (in mrem /hr) and the areal radionuclide concentration (in pCi/m )2 . Tables 11-14 FC/ CMP /01 051892

a FORT CALHOUN STATZON

b l) f f I'

PAGE 8 OF 42 CMP-6 CHEMISTRY MANUAL PROCEDURE LJ[j n J Doses from Licuid Effluent Pathways C. SHORELINE DEPOSITS Where: (con't)

A; = is the radioactive decay constant of nuclide i, in hr d.

t, = is the average transit time required for nuclides to reach the point of exposure. For internal dose, t, is the total time elapsed between release of the nucli es and ingestion of food or water, in hours. Table 15 t3 =- is the period of time for which sediment or soil is exposed to the contaminated water, in hours.

Table 15 110,000= Constant [(100

• pCi

• yr

• f t )3 / (Ci

• sec

• L)]

2.2 Gaseous Effluent Dose Calculations 2.2.1 Noble Gas 10 CFR 50, App. I, restricts the dose to individuals in the unrestricted areas from radioactive materials in gaseous effluents from the Fort Calhoun Station to the fol-lowing limits:

• During any calendar quarter 55 mrad-gamma air dose

$10 mrad-beta air dose and e During any calendar year slo mrad-gamma air dose

$20 mrad-beta air dose The following general equations shall be used to calculate the gamma-air and beta-air doses:

l I

FC/ CMP /01 051892

FORT CALHOUN STATION 0 PAGE 9 OF 42 f

CHEMISTRY MANUAL: PROCEDURE s J .J] M CMP-6 Doses from Gaseous Effluent Pathways A. Annual Gamma / Beta Air Dose from All Other Noble Gas Releases DY (r,G) or D E(r,9) _ = 3 .17 x 10' Oj (X/O]"(r,6) (DF} or D )

Where:

DF[, DFf = are the gamma and beta air dose factors for a uniform semi-infinite cloud of radionuclide i, in mrad-m 3/pCi -yr. Table 1 D T (r,0) = are the annual gamma and beta air dosen at the or distance r in the section at angle O from the D 8 (r,0) discharge point, in mrad /yr. ,

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

[X/Q] (r,6) = is the annual average gaseous dispersion factor at the distance r in section 0 in sec/m 3. Table 3 3.17x10 4 = is the number of pCi per_Ci divided by the number of seconds per year.

B. Annual Total Body Dose from All Other Noble Gas Releases D{(r,6) = S,. xj ( r,6) DFB, i.1 Where:

DFB, = is the total body dose factor for a semi-infinite cloud of the radionuclide i, which includes the-attenuation of 5 g/cm2 of tissue, in mrem-m 3/pCi-yr.

Table 3 DL (r,0) = is the annual total body dose due to immersion in a semi-infinite cloud at the distance r in sector 9, in mrem /yr.

Xi(r ,6) = is the annual average ground-level concentrati..t.n'of radionuclide i at the distance r in sector 9, an pCi/m 3. Table 3 Se = Shielding Factor. Table 15 i

j FC/ CMP /01 051892 i

i

3 FORT CALHOUN STATTON CHEMISTRY MANUAL PROCEDURE s I D

f7f C7 pAGE 10 OF 42 CMP-6 C. Annual Skin Dose from All Other Noble Gas Releases

.D[(r,9) = 1.11 S,. xj (r,8) DF} + xj(r,9)DFS j J=1 J*1 Where:

DL (r,6) = is the annual skin dose due to immersion in a semi-infinite cloud at the distance r in sector 6, in mrem /yr.

DFQ = is the beta skin dose factor for a semi-infinite i

cloud of radionuclide i in mrem-m /pci-yr.

All other parameters are as defined above.

2.2.2 Radioiodine, Tritium, and Particulates 10 CFR 50, App. I, rectricts the dose to individuals in the unrestricted areas from ladioactive materials in gaseous effluents I

from the Fort Calh(un Station to:

l e During any calendar quarter 57.5 mron to any organ and

• During any enlendar year 515 mron to any organ l The dose to an individual from radiolodines, radioective matecials in particulate form, and radionuclides other than noble gases with halfa ives greater than 8 days in gaseous e'fl'unts released to unrestricted areas (See j F34 Lee 3) should be determined by the follow-ing cyprer.31ons:

NOTE: In all cases, for releases of tritium, uae the dispersion parameter for inhalation (X/Q).

A. Annual Organ Dose from External Irradiation frcm Radio-l activity Deposited on the Ground Plane A.1 The ground plane conccatration of radionuclide i at the location (r,6) with respect to the release point may be determined by:

(r,6) - [1-exp ( A,e 3) )

FC/ CMP /01 051892

L' PAGE 11 OF 42

' FORT CALHO*W STATION li D g 2 CHEMISTRY MANUAL PROCEDURE h f CMP-6 Where:

Cy = is the ground plane concentration of the radionuclide >

i in the sector at angle 0 at the distance r from the release point, in pCi/m Q 3

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

t3 = is the time period over which the accumulation is evaluated, which is 15 years (mid-point of plant operating life). Table 15 6(r,0) i

= is the annual average relative deposition of effluent species i at location (r,0), considering depletion of the plume durino

,nsport, in m-2 Table 3 A, = is the radiological decay constant for nuclide 1, in yr-8 1.0x10 12 = is the number of pCi per Ci A.2 The annual organ dose is then calculated using the following equation:

Df(r,6) = 8760 S, f ((r,9)DFGy 2-1 i Where:

l Cy(r,0). = is the ground plane concentration of radionuclide i at distance r in sector 8, in pCi/m 2, l-l DFG g = is the open-field ground plane dose conversion factor for organ j from radionuclide i, in mrem-l m 2 /pci-hr. Table 15 Dy(r,0) = is the annual dose to the organ j at location

-(r,0), in mrem /yr.

Sp = is the shielding factor that accounts for the dose reduction due to shielding provided by l residential structures during occupancy, dimensionless. Table 15 8760 = is the number o'f hours in a year FC/ CMP /01 051892

v . . ,

FORT CALHOUN STATION [ PAGE 12 OF 42 CHEMISTRY MANUAL PROCEDURE 's Ib _

CMP-6 B. Annual Dose from Inhalation of Radionuclides in Air B.1 The annual average airborne concentration of radionuclide i at the location (r,6) with recpect to the release point may be determined as:

xj(r,0) = 3.17 x 10'Dj [x/O]"(r,0)

Where:

Q 3

= is the release rate of nuclide i to the atmosphere, ir Ci/yr.

X,( r ,6 ) = is the annual average ground-level concentration of nuclide i in air at sector 9 at distance r, in pCi/ m' .

( X /01"( r,0 ) = is the annual average atmosphere dispersion factor, in sec/m3 (see R.G. 1.111). This includes depletion (for radiciodines and particulates) and radioactive decay of the plume. Table 3 3.17x10 4 = 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:

Df(r,6) = R, x, (r,0) DFAjy Where:

D^j ( r ,0 ) = is the-annual dose to organ j of an individual in the age group a, at location (r,G) due to inhalation in mrem /yr.

l-R, = is the annual air intake for individuals in the age group a, in m'/yr. Table 5 DFng = is the inhalation dose factor for radionuclide i, l

l organ j, and age group a, in mrem /pCi l

l C. Annual Dose from' Atmospherically Released Radionuclides in l Food C.1 Concentrations of Airborne Radionuclides in Foods C.1.1 Parameters for Calculating Nuclide Concentra-tions in Forage, Produce, and Leafy Vegetables FC/ CMP /01 051892

m -

c, FORT CALHOUN STATION I;i- U b PAGE 13 OF 42

- CHEMISTRY MANUAL FROCEDURE 29 Id -

CMP-6 For all radiciodines and particulate radionuclides, excludina Tritium and Carbon-14, the concentration of nuclide i in and on vegetation at the location (r,0) is estimated using:

c[(r,(,) , d (r,0) j

1. ~*

#* I d' ~* ' UN I exp (- Aj3e )

Where:

CJ(r ,0) = is the concentration of nuclide i in and on vege-tation at the location (r,0), in Pci/kg.

d;( r ,0 ) = is the deposition rate of nuclide i, in Pci/m2 p/hr.

The deposition rt ' e from the plume is defined by:

(Reg. Guide 1.109, Rev. 1, Page 1.109-26, Equa. C-6) d (r,0) = 1.1 x 10 6,(r,0) j 8

03 Where:

di (r,0) = is the deposition rate of radionuclide i onto ground at location (r,0), in poi /m 2 -hr 6;(r,0) = is the relative deposition of radionuclide i, ccasidering depletion and decay in transit to location (r,0), in m.2 (so, Regulatory Guide 1.111). Table 3 1.1x10 8 = is the number of pCi/Ci (10") divided by the number of hours per year (8760).

Qi = is the release rate of nuclide i to the atmosphere, in Ci/yr.

r =- is the fraction of deposited activity retained on crops, dimensionless. Table 15 Ag = is the effective removal rate constant for radionu-clide i from crops, in hr d, ha=A,+h.

A,= 0.0021/hr. Table 15 l t, = is the time period that crops are exposed to conta-L mination during the growing season, in hours.

Table 15 I

Y, = is the agricultural productivity (yield) in kg (wet 2

weight)/m. Table 15 B,i = is the concentration factor for uptake of radionu-clide i from soil by edible parts of crops, in pCi/

- kg (wet weight) per pci/kg dry soil. Table 4 FC/ CMP /01 051892 L

t

FORT CALHOUN STATION-

~?

il g } 57 PAGE 14 OF 42 CHEMISTRY MANL'AL PROCEDURE [ fj f[ CMP-6 Where: (con't) >

hi = is the radioactive decay constant of nuclide 1, in hr 4 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 15 P. = is the effective " surface density" for soil, in kg 2

(dry soil)/m. Table 15 ta = is the holdup time that represents the time interval between harvest and consumption of the food, in hours. Table 15 For the parnmeters t,, Y,, and tg, different values are used to allow the use of the Equation for different purposes: estimating concentrations in produce consumed-by man; in leafy vegetables

.concumed by man; in forage consumed directly as pasture grass by.

dairy cows, beef _ cattle, or goats; and in forage consumed as stored feed:by dairy cows, beef cattle-or goats.

C.1.2 Parameters for Calculating Nuclide Concentration in

-Milk The Concentration of Radionuclide i, excluding Carbon-14 and Tritium, in the Animal's (Milk Cow, Beef Cow,

~ and Goat) Feed Cf(r,6) = fpf,Cf(r,6) + (1 - f p) C*,7(r,6) + pf (1 - f,) Cf(r,6)

Where:

qlr,0) =. is the concentration of radionuclide i in the animal's feed, in pCi/kg.

Q(r,0) = is the concentration of radionuclide i~on pasture grass (calcula*ad using Equation C-5 with ts=0) , ' in pCi/kg.

'Qtr,0) = is the concentration of radionuclide i in stored feeds (calculated using Equation C-5 with t a=90

-days), in pCi/kg.

t,

= is the-fraction of the year that animals graze on pasture. Table 15 f, = is the fraction of daily feed that is pasture grass when the animal grazes on pasture. Table 15 FC/ CMP /01' 051892

CT) to FORT CALHOUN STATION j $ PAGE 15 OF 42 CHEMISTRY MANUAL PROCEDURE > d}b IL - CMP-6 C.1.3 Parameters for Calculating the Nuclide Ccncentration in Cow and Goat Milk, excluding C-14 and Tritium C (r,6) = F,Cf( r ,8) o, exa ( - A, c f)

Where:

qNr,6) = is the concentration in milk of nuclide i, in pCi/

liter.

qlr,0) = is the concentration of radionuclide i in the animal's feed, in pC1/kg.

F, = is the average fraction of the animal's daily intake of radionuclide i which appears in e s ch liter of milk, in days / liter. Table 4

-Qp = is the amount or feed consumed by the animal per day, in kg/ day. Table 6

- tr = is the average transport. time of the activity from

-the feed into_the milk and to the receptor (a value of 2 days is assumed). Table 15 A, = is the radiological decay constant of nuclide i, in days 4.

C.1.4 Parameters for Calculating the Carbon-14 Concentrations in_ Vegetation Carbon-14 is assumed to be released in oxide "orm (CO or CO 2) . The concentration of Carbon-14 in vs getation 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 surround-ing 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 (taken 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:

FC/ CMP /01 051892

FORT CALHOUN STATION f PAGE 16 OF 42 CHEMISTRY' MANUAL PROCEDURE o j CMP-6 c[4 (r,0; - 3.17 x lo'po1. Ix/o] (r,G) 0.11/0 4 16

= 2. 2 x 10' poi, [x/0) (r,9)

Where:

Ci4 (r,0) = is the concentration of Carbon-14 in vegetation grown at location (r,0), in pCi/kg.

Qn = is the z.nnual release rate of carbon 14, in C1/yr.

3

[x/Q)(r,0)=- - is the atmospheric dispersion factor, in sec/m.

Table 3 p = is the fractional equilibrium ratio, diurnsionless.

P=1 (Reg. Guide 3.109, 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 3

the atmosphere, in g/m.

3.17x10 7 = is cqual to (1. 0 x 10"pCi/C1) (1. 0 x 10 g/kg; (3.15 3

x 10 sec/yr).

C.1.5 Parameters for Calculating Tritium Concentrations in Vegetation The-concentration of tritium in vegetation is calcu-lated from its concentration in the air surrounding the vegetation.- The NRC staff derived the-following equation:

C[(r,9) - 3.17 x 10'o (x/o)-(r,0) r (0.7 5) (0. 5/n)

= 1.2 x 107 0.[x/o] (r,0) /H 7

Where:

Ci(r,0) = is the concentration of Tritium in vegetation grown at location'(r,0), in Pci/kg.

H = is'the absolute humidity of the atmosphere at loca-tion (r,0), in g/m'. H=8 gm/kg.

Q7

~= is the annual release rate of Tritium, in C1/yr.

[x /Q) (r,0) = is'the atmospheric dispersion factor, in sec/m. 3 Table 3 FC/ CMP /01 051892

bl II f

FORT CALHOUH STATION PAGE 17 OF 42 CHEMISTRY MANUAL PROCEDURE I, J0!$ ]J CMP-6 hhntRI. fcon't) 0.5 = is the ratio of tritium concentration in plant water to trit' un concentration in atmospheric water, dimensionless, and 0.75 a is the "raction of total plant mass that is water, dinensionless.

C.2 Annual Dose from Atniospherically Released Radionuclides in Foods The annual dose to organ j of an individual in age group a, resulting from ingf'tlon of all radionuclides in proTuce, milk, and leafy vegetables is given byt Df,(r.G) =fDrJ,,,{t![f,cy( O) 4 (cj(r,0) + t(c[(c,0) + Lit.cj(r.0))

Wheret D$(r,9) = is the annual dose to organ j of an individual in age group a from dietary intake of atmospherically released radionuclides, in Mrom/yr.

DFI g = is the dose conversion factor for the ingestion of nuclide i, organ j, and age group a, in Mrem /Pci.

U;, U* a are the ingestion rates of produce (non-leafy vege-tables, fruits, and grains); milk, meat, and leafy 3

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

All other symbols are as defined in previous 1.109 equations.

Values of F, and f, are 0.76 and 1.0: respectively.

C.2.1 Calculating the Ingested Dose from Leafy and Non-Leafy (produce) Vegetation for Radionuclide i to Each Organ J and Age Group a Where? D[at t,G) - orJ,,, (uit cj(r,0) + U[ty c[( ,0))

D$(r,?) = is the annual dose from the ingestion of nuclide i to organ j of an individual in age group a from dietary intaxe of atmospherically released radio-nuclides in vegetation, in mrem /yr.

DFI j = is the dose _canversion factor for the ingestion of nuclide i, ort;an j , and age group a, in mrem /pCi.

Tables 11-14 4

U;, U; = are the ingestion rates of leafy vegetables and produce (non-leafy vegetables, fruits, and grains),

for individuals in age group a, in kg/yr. Table E FC/ CMP /01 051892

^"

n ca FORT CALHOUM STATION [ 5 PAGE 18 OF 42 Cl!EMISTRY MANUAL PROCEDURE --)I t I _ CMP-6 l

Fheres (con't) l CI = is the concentration of nuclide i in and on leafy  !

vegetation, in pCi/kg.

Cl = is the concentration of nuclide i in and on produce, in pCi/kg.

All other symbols are as previously defined in previous 1.109 equations. '41ues of F, and F, are 0.76 and 1. 0, respectively.

'C.2.2 Calculation Determining the_ Ingested Dose from Cow Milk for Radionuclide 1, excluding Carbon-14 and Tritium, to Organ j and Age Group a.

oj(r,0) ori,,, {t{cy(r,0)}

Where:

D$(r,0) = is the annual dose from the ingestion of nuclide i to organ j of an individual in age group a from dietary intake of atmospherically released radio-nuclides in cow milk, in mrem /yr. ,

DFIp = is the dowt conversion factor for the ingestion of  ;

nuclide i, organ j, and age group a, in mrem /pC1.

Tables 11-14 Uj = is the ingestion rate of cow milk for individuals in age group a, in t/yr. Table 5 CT = is the radionuclide concentration in cow-milk, in pC1/kg.

C.2.3 Calculation Determining the Ingested Dose from Meat for '

Radionuclide J to Organ K and Age Group a o[(r.G) Drr,,,(t(c[(r,0))

Where D$(r,0) = 1s the annual dose from the ingestion of nucliae i to organ j of an individual in age group a, from

! dietary intake of atnaaphorically released radio-nuclides in meat, in mrem /yr.

DFI g = is the dose conversion factor for the ingestion of l nuclide i, organ j, and age group a, in mrem /pci.

Tables 11 U[ = is the ingestion rate of meat for individuals in age group a in kg/yr. Tabic 5 FC/ CMP /01 051892

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

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

30, .

~

CORT CALilOUN STATION 0 ?M PAGE 19 OF 42 CHEMISTRY MANUAL PRotEDURE a ji J CMP-6 Where (con't) t C[ = is the radionuclide concentration in meat, !- .,

[

kg. ,

4 i

I l.

l.

FC/ CMP /Ol'_051392

FORT CALHOUN STATION CHEMISTRY MANUAL PROCEDURE l

a J0

. .d.

[ }a J

PAGE 20 OF 42 CMP-6 TABLE 1 DOSE FACTORS FOR EXPOSURE TO A DEMI-INFINITE CLOUD OF NOBLE GASES 1[pglisto #1 t EEd. B-skin **(Drs.1 3-Air *(DR), y-Bodv**(DEB,),

i KR-83m 2.88E-04 --

1.93E-05 7.56E-08 l 1

KR-85m 1.97E-03 1.46E-03 1.23E-03 1.17E-03 KR-85 1.95E-03 1.34E-03 1.72E-95 1.61E-05 KR-87 1.03E-02 9.73E-03 6.17E-03 5.92E-03 l KR-08 2.93E-03 2.37E-03 1.52E-02 1.47E-02 l KR-89 1.06E-02 1.01E-02 1.-73E-02 1.66*-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 Xe-135 2.46E-03 1.86E-03 1.92E-03 1.81E-03 l

Xe-137 1.27E-02 1.22E-02 1.51E-03 1.42E-03 l 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

o ELad-m' Pci/yr j

do mrem-m' pCi/yr 000 2.88E-04 = 2.88 x 10 4 l

FC/ CMP /01 -051892

I FORT CALHOUN STATION CHEMISTRY MANUAL PROCEDURE T

I l'

0

'y;' ^

b

'f" PAGE al OF 43 CMP-6 I

l TABLE 2 BIOACCUMULATION 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 2.0E-02 2.0E-02 P .0E-05 2.0E-04 CR 2.0E-02 2.0E-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 5.0E-01 4.0E-02 ZN 2.0E-03 1.0E 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 1.0E-01 1.0E-01 TC 1.5E-01 5.0E-00 l RU 1.0E-01 3.0E-02 RH 1.0E-01 3.0E-02 TE 4.0E-02 6.1E-03 I 1.5E-01 5.0E-00 CS 2.1E-03 1.0E-03 l BA 4.JE-01 2.0E-02 l LA 2.5E-01 1.0E-03 l CE 1.0E-00 1.0E-03 l

PR 2.5E-01 1.0E-03 ND 2.5E-01 1.0E-03 l W 1.2E-03 1.0E-01 l NP 1.0E-01 4.0E-02 l

l FC/ CMP /01 0518F2

b l FORT CALilOUN STATION CllEMISTRY MANUAL PROCEDURE ajElJu I I) 1 PAGE 22 OF 42 CMP-6 TABLE 3 CONTROLLING LOCATIONS, PATHWAYS AND ATMOSPHERIC DISPERSION FOR DOBE CALCULATIONS Atmogphgric Dispersion x/Q D/Q controlling (x/Q(r,0)) (6(r,0))

I,,ocation Pathway (s). Jge Group _. 10po / m'). .Ll/JIO.,

Site Noble Gases N/A 5.0E-06 N/A Boundary Direct Exposure Site Inhalation Child 5.0E-06 N/A Boundary Site Gamma-Air N/A 5.0E-06 N/A Boundary Beta-Air Miller Farm

• milk., ground Child 2.5E-06 1.6E-08 0.8 miles plane, meat, SSW inhalation, and vegetation Site Liquid N/A Mixing 7.14 Boundary Ratio, M, FC/ CMP /01 051892

FORT CALHOUN STATION PAGE 33 OF 43 CHEMISTRY MANUAL PROCEDURE f)ID1

._)

f 1 J] r? CMP-6 TA'3LE 4 STADLE ELEMEN't TRAM 3FER DATA B,, F (Cow) F, Element Vea/ Soil Milk (d/h) Meat (d/kg)

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 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 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 Sr 1.7E-02 8.0E-04 6.0E-04 Y 2.6E-03 1.0E-05 4.6E-03 Zr 1.7E-04 5.0E-06 3.4E-02 Nb 9.4E-03 2.5E-03 2.8E-01 Mo 1.2E-01 7.5E-03 8.0E-03 Tc 2.5E-01 2.5E-02 4.0E-01 Ru 5.0E-02 1.0E-06 4.0E-01 Rh 1.3E-01 1.0E-02 1.5E-03

.Ag 1.5E-01 5.0E-02 1.7E-02 To 1.3E+00 1.0E-03 .7E-02 I 2.0E-02 6.0E-03 2.9E 03 Cs 1.0E-02 1.2E-02 4.0E-03 Ba 5.0E-03 4.0E-04 3.2E-03 La 2.5E-03 5.0E-06 2.0E-04 Co 2.5E-03 1.0E-04 1.2E-03 Pr 2.5E-03 5.0E-06 4.73-03 Nd 2.4E-03 5.0E-06 3.3E-03 W 1.8E-02 5.0E-04. 1.3E-03 Np 2.5E-03 5.0E-06 2.0E-04 FC/ CMP /01 051892

)) y7 en FORT CALHOUN STATION i PAGE 24 OF 42 CHEMISTRY MANUAL PROCEDURE

'I -

CMP-6 TABLE 5 RECOMML'NDED VALUES FOR Ug To DE USED FOR THE MAXIMUM EXPOSED INDIVIDUAL IN LIEU OF SITE SPECIFIC DATA Pathway Infant Child Toon 6dult Fruits, vegetables, &

grain (kg/yr) - 520 630 520 Leafy vegetables (kg/yr) -

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

41 65 110 Fish (fresh or salt)

(kg/yr) -

6.9 16 21 Other Seafood (kg/yr) -

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

14 67 12 Inhalation (m$/yr) 1400 3700 8000 8000 l

l TABLE 6 l

ANIMAL CONSUMPTION RATES l

i Op Q4w l

[

Fee or Forage Water I

Animal fKc/ day (wet weich)1 (t/ day) l Milk 50 60 t

Beef Cattle 50 50 t

Goats -6 8 l

FC/ CMP /01 051892

P ' - + u

-FORT CALHOUN STATION (j U

[ h l

PAGE 25 OF 42 CHEMISTRY MANUAL PROCEDURE ls ll J 3 > CMP-6 TABLE 7 INHALATION DOSE FACTORS FOR ADULT (mrem per pC1 Inhaled)

Page 1 of 2 Nuclide Bone Liver T. Body Thyroid Kidney 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 4.26E-07 4.26E-07 4.26E-07 4.26E-07 NA 24 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 - - -

1.08E-05 CR 51 - -

1.25E-08 7.44E-09 2.85E-09 1.80E-06 4.15E-07 MN 54 -

4.95E-06 7.87E-07 -

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

1.55E-10 2.29E-11 -

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

9.01E-06 7.54E-07 FE 59 1.47E-06 3.47E-06 1.32E-06 - -

1.27E-04 2.35E-05 CO 58 -

1.98E-07 2.59E-07 - -

1.16E-04 1.33E-05 CO 60 -

1.44E-06 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 NI 65 1.92E-10 2.62E-11 1.14E-11 - -

7.00E-07 1.54E-06 CU 64 -

1.83E-10 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 ZN 69 4.2?E-12 8.14E-12 5.65E-13 -

5.27E-12 1.15E-07 2.04E-09 i BR 80 - - 3.01E-08 - - -

2.90E-08 BR 84 - -

3.91E-08 - - -

2.05E-13 BR 85 - - 1.60E-09 - - -

LT E-24 RD 86 -

1.69E-05 7.37E-06 - - -

2.08E-06 RB 88 -

4.84E-08 2.41E-08 - - -

4.18E-19 RB 89 -

3.20E-08 2.12E-08 - - -

1.16E-21 SR 89 3.80E-05 -

1.09E-06 - -

1.75E-04 4.37E-05 SR 90 1.24E-02 -

7.62E-04 - -

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

3.13E-10 - -

4.56E-06 2.39E-05 SR 92 8.43E-10 -

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 - -

2.40E-07 1.66E-10 Y 91 5.78E-05 -

1.55E-06 - -

2.13E-04 4.81E-05 ll 92 1.29E-09 -

3.77E-11 - -

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

3.26E-10 - -

6.06E-06 5.27E-00 ZR 95 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-05 MO 99 -

1.51E-08 2.87E-09 -

3.64E-08 1.14E-05 3.10E-05 TC 99M 1.29E-13 3.64E-13 4.63E-12 -

5.52E-12 9.55E-08 5.20E-07 l

l L FC/ CMP /01 051892 1

i

m y -

FORT CALHOUN STATION PAGE 26 OF 42 CHEMISTRY MANUAL PROCEDURE CMP-6 INHALATION DOSE FACTORD FOR ADULT (mrem per pCi Inhaled)

Page 2 of 2 lig g.j M q Bone Liver T. Body Thyroid _Elsin cy. . Luna GI-LLL_

TC 101 5.22E-15 7.52E-15 7.38E-14 - 1.35E-13 4.99E-08 1.36E-21 PU 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-04 6.02E-06 RU 106 8.64E-06 -

1.09E-06 -

1.67E-05 1.1 r 0 3 1.14E-04 AG 110M 1.35E-06 1.25E-06 7.43E-07 -

2.46E-06 a.ike-04 3.78E-05 TE 125M 4.27E-07 1.98E-07 5.84E-08 1.31E-07 1.55E-06 3.92E 0" 8.83E-06 TE 127M 1.58E-06 7.21E-07 1.96E-07 4.11E-07 5.72E-06 1.20E-04 1.87E-05 TB 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 Z 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.E6E-06 1.49E-05 7.66E-06 -

7.85E-07 I 132 1.45E-04 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-06 I 134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 -

1.26E-10 I 135 3.35E-07 8.73E-07 3.21E-07 5.60E-05 1.39E-06 -

6.56E-07 CG 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 .1,38 4.14E-08 7.76E-08 4.05E-08 -

6.00E-09 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-05 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 -

8.75E-15 2.42E-07 1.45E-17 BA 142 3.29E-12 3.38E-15 2.078-13 -

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 PR 144 3.76E-12 1.56E-12 1.91E-13 -

8.81E-13 1.27E-07 2.69E-18 ND 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-05 NP 239 2.87E-08 2.82E-09 1.55E-09 -

8.75E-09 4.70E-06 1.49E-05 l

FC/ CMP /01 051892

FORT CALHOUN STATION h b PAGE 27 OF 42 CHEMISTRY MANUAL PROCEDURE --) '

In CMP-6 TABLE 8 INHALATION DOSE FACTORS FOR TEENAGER (mrem per pCi Inhaled)

Page 1 of 2 11uclide Bone Liver T. Body Thyroid Kidney _ Luna GI-LLI H 3 -

1.59E-07 1.59E-07 1.59E-07 1.59L-07 1.59E-07 1.59E-07 C 14 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 8.95E-06 - - -

1.16E-05 CR 51 - - 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.75E-07 MN 54 -

6.39E-06 1.05E-06 -

1.59E-06 2.48E-04 8.35E-06 _

MN 56 -

2.12E-10 3.15E-11 -

2.24E-10 1.90E-06 7.18E-06 FE 55 4.18E-06 2.98E-06 6.93E-07 - -

1.55E-05 7.99E-07 FE 59 1.99E-06 4.62E-06 1.79E-06 - -

1.91E-04 2.23E-05 CO 58 -

2.59E-07 3.47E-07 - -

1.68E-04 1.19E-05 CO 60 -

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 NI 65 2.73E-10 3.66E-11 1.59E-11 - -

1.17E-06 4.59E-06 CU 64 -

2.54E-10 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 1.55E-04 5.83E-06 ZN 69 6.04E-12 1.15E-11 8.07E-13 -

7.53E-12 1.98E-07 3.56E-08 BR 83 - -

4.30E-08 - - -

LT E-24 BR 84 - - 5.41E-08 - - -

LT E-24 BR 85 - -

2.29E-09 - - -

LT E-24 RB 86 -

2.38E-05 1.05E-05 - - -

2.21E-06 _

RB 88 -

6.82E-08 3.40E-08 - - -

3.65E-15 RB 89 -

4.40E-08 2.91E-08 - - -

4.22E-17 SR 89 5.43E-05 -

1.56E-06 - -

3.02E-04 4.64E-05 SR 90 1.35E-02 -

8.35E-04 - -

2.06E-03 9.56E-05 SR 91 1.10E-08 -

4.39E-10 - -

7.59E-06 3.24E-05 SR 92 1.19E-09 -

5.08E-11 - -

3.43E-06 1.49E-06 Y 90 3.73E-07 -

1.00E-08 - -

3.6bE-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 5.11E-05 Y 92 1.84E-09 -

5.36E-11 - -

3.35E-06 2.06E-05 Y 93 1.69E-08 -

4.65E-10 - -

1.04E-05 7.24E-00 ZR 95 1.82E-05 5.73E-06 3.94E-06 -

8.42E-06 3.36E-04 1.86E-05 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-05 MO 99 -

2.11E-08 4.03E-09 -

5.14E-08 1.92E-05 3.36E-05 TC 99M 1.73E-13 4.83E-13 6.24E-12 -

7.20E-12 1.44E-07 7.66E-07 FC/ CMP /01 051892 l 1

l

p )) 7 ta PAGE 28 OF 42 FORT CALHOUN STATION CHEMISTRY MANUAL PROCEDURE U

~' 'Jg # f- CMP-6 INHALATION DOSE FACTORS FOR TEENA0ER (mrem per pCi Inhaled)

Page 2 of 2 Nuclido Bone Liver _T. Body Ihyroid _Xidney Luna _QI-LLI TC 101 7.40E-15 3.05E-14 1.03E-13 -

1.90E-13 8.34E-08 1.09E-16 RU 103 2.63E-07 -

1.12E-07 -

9.29E-07 9.79E-05 1.36E-05 RU 105 3.40E-11 -

5.42E-11 -

1.76E-10 2.27E-06 1.13E-05 RU 106 1.23E-05 -

1.55E-06 -

2.38E-05 2.01E-03 1.20E-04 AG 310M 1.73E-06 1.64E-06 9.99E-07 -

3.33E-06 8.44E-04 3.41E-05 TE 125M 6.10E-07 2.80E-07 8.34E-08 1.75E-07 -

6.70E-05 9.38E-06 TE 127M 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 TE 127 2.51E-10 1.14E-10 5.52E-11 1.77E-10 9.10E-10 1.40E-06 1.01E-06 TE 129M 1.74E-06 8.23E-07 2.81E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 TE 129 8.87E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-11 4.12E-07 2.02E-08 TE 131M 1.23E-08 7.51E-09 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 2.44E-97 5.61E-05 5.79E-05 1 130 7.80E-07 2.24E-06 8.96E-C7 1.86E-04 3.44E-06 -

1.14E-06 1 131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 -

8.11E-07

'T 132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 -

1.59E-07 I 133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 -

1.29E-06 I 134 1.11E-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 -

2.55E-09 Z 135 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 -

8.69E-07 CS 134 6.28E-05 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 1.51E-05 1.06E-06 CS 138 5.82E-08 1.07E-07 E.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 2.54E-04 2.86E-05 BA 141 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-73 -

3.92E-15 2.39E-07 5.902-20 LA 140 5.99E-08 2.95E-08 7.82E-09 - -

2.68E-05 6.09E-05 LA 142 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 -

1.08E-08 1.63E-05 3.19E-05 CE 144 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 PR 144 5.37E-12 2.20E-12 2.72E-13 -

1.26E-12 2.19E-07 2.94E-14 IH) 147 9.83E-07 1.07E-06 6.41E-08 -

6.28E-07 4.65E-05 2.28E-05 W- 187 1.50E-09 1.22E-09 4.29E-10 - -

5.92E-06 2.21E-05 hP 239 4.23E-08 3.99E-09 2.21E-09 -

1.25E-08 8.11E-06 1.65E-05 FC/ CMP /01 051892

FORT CALilOUN STATION ('

O M Ju [

U L

PAGE 29 OF 42 CMP-6 CllEMISTRY MANUAL PROCEDURE TABLE 9 INHALATION DOSE FACTORS FOR CHILD (mrem per pCi Inhaled)

Page 1 of 2 liuclide Bone Liver _T. Body Thyroid. _Jiidney Luna 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 - - -

1.14E-05 CR 51 - -

4.17E-08 2.31E-08 6.57E-09 4.59E-06 2.93E-07 -

Mll 54 -

1.16E-00 2.57E-06 -

2.71E-06 4.26E-04 6.19E-06 MN 56 -

4.48E-10 8.43E-11 -

4.52E-10 3.55E-06 3.33E-05 FE 55 1.28E-05 6.80E-06 2.10E-06 - -

3.00E-05 7.75E-07 FE 59 5.59E-06 9.04E-06 4.51E-06 - -

3.43E-04 1.91E-05 CO 58 -

4.79E-07 8.55E-07 - -

2.99E-04 9.39E-06 CO 60 -

3.55E-06 6.12E-06 - -

1.91E-03 2.60E-05 NI 63 2.22E-04 1.25E-06 7.56E-06 - -

7.43E-05 1.71E-06 NI 65 8.08E-10 7.99E-11 4.44E-31 - -

2.21E-06 2.27E-05 CU 64 -

5.39E-10 2.90E-10 -

1.63E-09 2.59E-06 9.92E-06 ZN 65 1.15E-05 3.06E-05 1.90E-05 -

1.93E-05 2.69E-04 4.41E-06 ZN 69 1.8]E-11 2.61E-11 2.41E-12 -

1.58E-11 3.94E-07 2.75E-06 BR 83 - -

1.28E-08 - - -

LT E-24 BR 84 - -

1.48E-07 - - - LT E-24 BR 85 - -

6.84E-09 - - -

LT E-24 RB 86 -

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 - - -

5.11E-10 SR 89 1.62E-04 -

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 4.70E-05 SR 92 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 4.97E-05 Y 92 5.50E-09 -

1.57E-10 - -

6.46E-06 6.46E-05 Y 93 5.04E-08 1.13E-05 1.38E-09 - -

2.01E-05 1.05E-04 ZR 95 5.13E-05 1.13E-05 1.00E-05 -

1.61E-05 6.03E-04 1.65E-05 ZR 97 5.07E-06 7.34E-09 4.32E-09 - 1.05E-08 3.06E-05 9.49E-05 ND 95 6.35E-06 2.48E-06 1.77E-06 -

2.33E-06 1.66E-04 1.00E-05 MO 99 -

4.66E-08 1.15E-08 -

1.06E-07 3.66E-05 3.42E-05 TC 99M 4.81E-13 9.41E-13 1.56E-11 -

1.37E-11 2. 57 E- 07 1.30E-06 l

FC/ CMP /01 051892

_ .__ _ __ _ . ___ - _ _ _ ______m

_ _ _ __ m__ __._ _ __ _

n cn FORT CALHOUN STATION l b $ h PAGE 30 OF 42 i

CHEMISTRY MANUAL PROCEDURE l 30 A 3 - CMP-6 I INHALATION DOSE FACTORS FOR CHILD '

(mrem per pCi Inhaled)

Page 2 of 2 Uuclide , Bone Liver T, Body Thyroid Kidney Lunc _GI-LLI TC 101 2.19E-14 2.30E-14 2.91E-13 -

3.92E-13 1.58E-07 4.41E-09 RU 103 7.55E-07 -

2.90E-07 -

1.90E-06 1.79E-04 1.21E-05 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 4.55E-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 l 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-36 8.22E-07 1.71E-06 1.3GE-05 4.76E-04 4.91E-05 l

TE 129 -2.64E-11 9.45E-12 6.44E-12 1.93E-11 6.94E-11 7.93E-07 6.89E-06  :

l 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 7e36E-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 2.28E-06 4.39E-03 2.13E-05 -

7.6PE-07 I 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-06 1 134 1.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 -

2.58E-07 1 135 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 7.29E-08 BA=139 4.98E-10 2.66E-13 1. 4 5 E-11 -

2.33E-13 1.56E-06 1.56E-05 BA 140 2.00E-05 1. 7 5E -0 8 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 6.052 v8 2., 0 4 E-0 8 - -

4.94E-05 6.10E-05 L4 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 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 PR 144 1.61E-11 4.99E-12 8.1^"-13 -

2.64E-12 4.23E-07 5.32E-08 ND 147 2.92E-06 2.36E-06 1e 07 -

1.30E-06 8.87E-05 2.22E-05 W 187 4.41E-09 2.61E-09 1. iE-09 - -

1.11E-05 2.46E-05 NP 239 1.26E-07 9.04E-09 6.35E-09 -

2.63E-08 1.57E-05 1.73E-05 FC/ CMP /01 051892

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

? 7) n ta FORT CALHOUN STATIOl d S \ h PAGE 31 OF 42 CHEMISTRY MANUAL PROCEDURE 3 :U ['d J

.t CMP-6 TABLE 10 INHALATION DOBE FACTORS FOR INFANT (mrem per pCi Inhaled)

Page 1 of 2 Nuc1 L<ig Bone . . L i vg_,, T. Body Thyroid .. Kidney 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 NA 24 1.54E-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 N1 63 2.42E-04 1.46E-05 S.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 ZN 69 3.85E-11 6 . 9.*, ' < 11 5.13E-12 -

2.87E-11 1.05E-06 9.44E-06 BR 83 - -

2.72E-07 - - -

LT E-24 BR 84 - -

2.86E-07 - - -

LT E-24

'BR 05 - -

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 l RB 89 -

2.29E-07 1.47E-07 - - -

4.87E-08 SR 89 2.84E-04 e 8.15E-06 - -

1.45E-03 4.57E-05 l

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 l 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 1.99E-05 1.45E-05 -

2.22E-05 1.25E-03 1.55E-05 ZR.97 1.07E-07. 1.83E-08 8.36E-09 -

1.85E-08 7.88E-05 1.00E-04 NB 95- 1.12E-05 4.59E-06 2.70E-06 -

3.37E-06 3.42E-04 9.05E-06 MO 99 -

1.18E-07 2.31E-08 -

1.89E-07 9.63E-05 3.48E-05 TC 99M 9.98E-13 2.06E-12 2.66E-11 -

2.22E-11 5.79E-07 1.45E-06 FC/ CMP /01 051892

PAGE 32 OF 42 j j ] C)

FORT CALHOUN STATION il 1 CHEMISTRY MANUAL PROCEDURE ~{' CMP-6 3 j INHALATION DOBE FACTORS FOR INFANT (mrem per pCi Inhaled)

Page 2 of 2 Nuclide Bone Livqr_ T Body Thyroid Kidnev __ Lu nc _GI-LLI TC 101 4.65E-14 5.88E-14 5.80E-13 - 6.99E-13 4.17E-07 6.03E-07 RU 103 1.44E-06 - 4.85E-07 -

3.03E-06 3.94E-04 1.15E-05 RU 205 8.74E-10 -

2.93E-10 -

6.42E-10 1.12E-05 3.46E-05 RU 106 6.20E-05 - 7.77E-06 -

7.61E-05 8.26E-03 1.17E-04 AG 110M 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 2.68E-05 9.17E-04 1.95E-05 TE 127 1.59E-09 6.81E-10 3.40E-10 1.32E-09 3.47E-09 7.39E-06 3.74E-05 TE 129M 1.01E-05 4.35E-06 1.59E-06 3.91E-06 2.27E-05 1.20E-03 4.93E-05 TE 129 5.63E-11 2.48E-11 1.34E-11 4.82E-11 1.25E-10 2.14E-06 1.88E-05 TE 131M 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51E-05 TE 131 1.24E-11 5.87E-12 3.57E-12 1.13E-11 2.85E-11 1.47E-06 5.87E-L.

TE 132 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 1 130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 -

1.42E-06 I 131 2.71E-05 3.17E-05 1.40E-05 1.06F-02 3.70E-05 -

7.56E-07 I 132 1.21E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 -

1.36E-06 I 133 9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 -

1.54E-06 1 134 6.58E-07 1.34E-06 4.75E-07 . 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 -

1.31E-06 CS 134 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 9.53E-07 CS 138 3.61E-07 5.58E-07 2.84E-07 -

2.93E-07 4.67E-08 6.26E-07 l BA 139 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 2.74E-05 BA 141 1.32E-10 7.70E-14 3.55E-12 -

4.64E-14 2.12E-06 3.39E-06 BA 142 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-03 3.68E-08 - -

1.20E-04 6.06E-05 LA 142 7.36E-10 2.69E-10 6.46E-11 - -

5.87E 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 3.55E-05 CE 144 2.28E 8.65E-04 1.26E-04 -

3.84E-04 7.03"-03 1.06E-04 PR 143 1.00E 3.74E-06 4.99E-07 -

1.41E-06 3.09E-04 2.66E-05 PR 144 3.42E-11 1.32E-11 1.72E-12 -

4.80E 1.15E-06 3.06E-06 ND 147 5.67E-06 5.81E-06 3.57E-07 -

2.25E-06 2.30E-04 2.23E-05 W 187 9.26E-09 6.44E-09 2.23E-09 - -

2.83E-05 2.54E-05 NP 239 2.65E-07 2.37E-08 1.34E-08 -

4.73E-08 4.25E-05 1.78E-05 FC/ CMP /01 051892

FORT CALHOUN STATION h PAGE 33 OF 42 CHEMISTRY MANUAL PROCEDURE h-d[i jk Ltd[h CMP-6 TALLE 11 INGESTION DOPE FACTORS FOR ADULT (mRea por pCi Ingested)

Page 1 of 2 Nuclide Bone Li ve r __ T. Body Thyroid Kidney __ Lung __ GI-LLI H 3 - 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 C 14 2.84E-06 5.68E-07 5.68E-07 5.6BE-07 5.68E-07 5.68E-07 5.68E-07 NA 24 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 - - -

2.17E-05 CR 51 - -

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 -

1.46E-07 -

3.67E-06 FE 55 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 CO 58 -

7.45E-07 1.67E-06 - - -

1.51E-05 CO-60 - 2.14E-06 4.72E-06 - - -

4.02E-05 NZ 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 -

2.10E-07 -

7.10E-06 ZN'65 4.84E-06 1.54E-05 6.96E-06 -

1.03E-05 -

9.70E-06 ZN 69 1.03E-08 1.97E-08 1.37E-09 -

1.28E-08 -

2.96E-09 BR 83 - -

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 - -

1.45E-03 4.94E-05 SR 90 7.58E-03 - 1.86E-03 - -

8.03E-03 2.19E-04 SR 91 5.67E-06 -

2.29E-07 - -

3.76E-05 2.70E-05 SR 92 2.15E-06 -

9.30E-08 - -

1.70E-05 4.26E-05 Y 90 9.62E-09 -

2.58E-10 - -

1.92E-04 1.02E-04 Y 91M 9.09E-11 - 3.52E-12 - -

1.99E-06 2.67E-10 Y 91' 1.41E-07 - 3.77E-09 - - 1.75E-03 7.76E-05 Y 92- 2.45E-10 -

2.47E-11 - - 1.75E-05 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 MB 95 6.22E-09 3.46E-09 1.86E-09 -

3.42E-09 -

2.10E-05 MO 99 -

4.31E-06 S.20E-07 -

9.76E-06 -

9.99E-06 TC 99M 2.47E-10 6.98E-10 8.89E-09 -

1.06E-08 3.42E-10 4.13E-07

-FC/ CMP /01 051892

FORT CALHOUN STATIOM CHEMISTRY MANUAL PROCEDURE >

h;U n J

PAGE 34 OF 42 CMP-6 INGESTION DOSE FACTORS FOR ADULT (mrem per pCi Ingested)

Page 2 of 2 Nuclido __Dpne . _. Liver T. Body Thyroid Kidney Lunc _ 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-0~ -

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 8.2SE-07 1.73E-06 2.75E-05 -

2.27E-05 TE 127 1.10E-07 3.95E-08 2.38E-08 6.15E-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-05 TE 131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8. 6 3 E--0 8 -

2.79E-09 TE 132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 -

7.71E-05 I 130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 -

1.92E-06

% 131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-Ob -

1.57E-06 I 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-06 I 134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 -

2.51E-10 1 135 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 1.09F-04 7.14E-05 -

3.70E-05 1.23E-05 2.11E-06 CS 138 5.52E-08 1.09L-07 5.40E-08 -

8.01E-08 7.91E-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 I

LA 140 2.50E-09 1.26E-09 3.33E-10 - - -

9.25E-05 LA 142 1.28E-10 5.82E-11 1.45Eo11 - - -

4.25E-07 CE 141 9.36E-09 6.33E-09 7.18E-10 - 2.94E-09 - 2.42E-05 L

l l 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 -

2.13E-09 -

4.03E-05 141 144 3.01E-11 1.25E-11 1.53E-12 -

7.05E-12 -

4.33E-18 l

i MD 147 6.29E-09 7.27E-09 4.35E-10 - 4.25E-09 -

3.49E-05 l W 187 1.03E-07 8.61E-08 3.01E-08 - - -

2.82E-05 NP 239 1.19E-09 1.17E-10 6.45E-11 - 3.65E-10 -

2.40E-05 FC/ CMP /01 051892

l FORT CALHOUN STATION h A PAGE 35 OF 42 CHEMISTRY MANUAL PROCEDURE LS O h; IU i I CMP-6 TABLE 12 INGESTION DOSE FACTORS FOR TEENAGER (wRem per pCi Ingssted)

Page 1 of 2 Nuclide Bone LiveE._ T. Body Thyroid _Xidnel 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 2.300-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 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 56 -

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 '4E-06 - - - 1.34E-05 CO 60 - 2.81E-06 3E-06 - - -

3.66E-05 NI 63 1.77E-04 1.25E-05 t 00E-06 - - -

1.99E-06 HI 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 2N 65 5.76E-06 2.00E-05 9.33E-06 -

1.28E-05 -

8.47E-06 ZN 69 1.47E-08 2.80E-08 1.96E-09 -

1.83E-08 -

5.16E-08 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 P9 89 -

5.50E-08 3.89E-08 - - -

8.43E-17 dR 89 4,40E-04 -

1.26E-05 - - -

5.24E-05 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 Y 90 1.37E-08 -

3.69E-10 - - -

1.13E-04 Y 91M 1.29E-10 -

4.93E-12 - - -

6.09E-09 Y 9] 2.01E-07 -

5.39E-09 - - -

8.24E-05 Y 92 1.21E-09 -

3.50E-11 - - - 3.32E-05 i Y- 93 2.68E-09 - 7.40E-11 - - -

8.50E-05 l 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 NB 95. 6.22E-09 3.46E-09 1.86E-09 -

3.42E-09 -

2.10E-05 MO 99 - 4.31E-06 8.20E-07 -

9.76E-06 -

9.99E-96 TC 99M 2.47E-10 6.98E-10 8.89E-09 -

1.06E-08 3.42E-10 4.13E-07

-FC/ CMP /01 051892

FORT CALHOUN STATION PAGE 36 0F 42 CilEMISTRY MANUAL PROCEDURE l?Ih lUU UdUhAI' J CMP-6 INGESTION DOSE FACTORS FOR TEENAGER (mrem per pCi Ingested)

Pago 2 of 2 Nuclido Bone Liver T. Body Thyroid Kidney Luna 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 1.4bE-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 6.773-06 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./1E-08 1.32E-07 -

2.37E-08 TE 131M 1.73E-06 8.46E-07 7.05E-07 1. "a 4 E-0 6 8.57E-06 - 8.40E-05 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 1.80E-06 1.57E-G5 -

7.71E-05 2 130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 -

1.92E-06 I 131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 - 1.57E-06 I 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-06 I 134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 -

2.51E-10 1 135 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 1.09E-07 5.40E-08 -

8.01E-08 7.91E-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 PR 144 3.01E-11 1.25E-11 1.53E-12 - 7.05E-12 - 4.33E-18 ND 147 6.29E-09 7.27E-09 4.35E-10 - 4.25E-09 - 3.49E-05 W 187 1.03E-07 8.61E-09 3.01E-08 - - -

2.82E-05 NP 239 1.19E-09 1.17E-10 6.45E-11 -

3.65E-10 -

2.40E-05 FC/ CMP /01 051892

~

FORT CALHOUN STATION PAGE 37 OF 63 CHEMISTRY MANUAL PROCEDURE l[)I l'

i) 1h\ @

,Id H CMP-6 TABLE 13 INGESTION DOSE FACTORS FOR CHILD (mrem per pCi Ingested)

Page 1 of 2 Hgclide Bone Liver T. Body Thyroid Kidney Luno GI-LLI H 3 - 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 C 34 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 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 ZN 69 4.38E-08 6.33E-08 5.85E-09 -

3.84E-08 -

3.99E-06 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-65 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 NB 95 2.2SE-08 8.76E-09 6.26E-09 -

8.23E-09 -

1.62E-05 MO 99 - 1.33E-05 3.29E-06 -

2.84E-05 -

1.10E-05 TC 99M 9.23E-10 1.81E-09 3.00E-08 -

2.63E-08 9.19E-10 1.03E-06 FC/ CMP /01 051892

[ PAGE 38 OF 42 FORT CALHOUN STATION

[v. h {F '7 CMP-6 CHEMISTRY MANUAL PROCEDURE [. fj ]  ;

INGESTION DOSE FACTORS FOR CHILD (mrem 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 3.92E-10 3.56F-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 -

1.45E-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 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 3.26E-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 TE 129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 -

8.34E-06 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-06 Z 132 8.00E-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 -

1.73E-06 I 133 5.92E-06 7.32E-06 2.77E-06 3.36E-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 3.11E-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 i

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 5.58E-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 2.94L-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

( 4.24E-05

! PR 143 3.93E-08 1.18E-08 1.95E-09 -

6.39E-09 -

PR 144 1.29E-10 3.99E-11 6.49E-12 -

2.11E-11 -

8.59E-08 ND 147 2.79E-08 2.26E-08 1.75E-09 -

1.24E-08 -

3.58E-05 W 187 4.29E-07 2.54E-07 1.14E-07 - - -

3.57E-05 l

NP 239 5.25E-09 3.77E-10 2.65E-10 -

1.09E-09 -

2.79E-05 i

L FC/ CMP /01 051892

FORT CALHOUN STATION CHEMISTRY MANUAL PROCEDURE h\

l' .T J PAGE 39 OF 42 CMP-6 TABLE 14 INGESTION DOBE FACTORB FOR INFANT (mrem per pCi Ingested)

Page 1 of 2

_L Body Thyroid Kid.ney__ Luna GI-LLI linclide Bone _ Liver 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 S.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 NA 24 1.01E-05 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 - - - 2.30E-05 CR 51 - -

1.41E-08 9.20E-09 2.01E-09 1.7 E-08 4.11E-07 MN 54 - 1.99E-05 4.51E-06 - 4.41E-06 - 7.31E-06 MN 56 -

8.18E-07 1.41E-07 - 7.03E-07 -

7.43E-05 FE 55 1.39E-05 8.98E-06 2.40E-06 - -

4.36E-06 1.14E-06 FE 59 3.08E-05 5.38E-05 2.12E-05 - -

1.59E-05 2.57E-05 CO 58 - 3.60E-06 8.98E-06 - - -

8.97E-06 CO 60 -

1.08E-05 2.55E-05 - - -

2.57E-05 NI 63 6.34E-04 3.92E-05 2.20E-05 - - -

1.95E-06 NI 65 4.70E-06 5.32E-07 2.42E-07 - - -

4.05E-05 CU 64 - 6.09E-07 2.82E-07 -

1.03E-06 -

1.25E-05 ZN 65 1.84E-05 6.31E-05 2.91E-05 -

3.06E-05 -

5.33E-05 ZN 69 9.33E-08 1.68E-07 1.25E-08 -

6.98E-08 -

1.37E-05 BR 83 - -

3.63E-07 - - -

LT E-24 BR 84 - -

3.82E-07 - - -

LT E-24 o BR 85 - -

1.94E-08 - - -

LT E-24 RB 86 -

1.70E-04 8.40E-05 - - -

4.35E-06 RB 88 -

4.98E-07 2.73E-07 - - -- 4.85E-07 RB 89 -

2.86E-07 1.97E-07 - - - 9. 7 4 E- 08 SR 89 2.51E-03 -

7.20E-05 - - -

5.16E-05 SR 90 1.85E-02 - 4.71E-03 - - -

2.31E-04 SR 91 5.00E-05 -

1.81E-06 - - -

5.92E-05 SR 92 1.92E-05 - 7.13E-07 - - -

2.07E-04 Y 90 8.69E-08 -

2.33E-09 - - -

1.20E-04 Y 91M 8.10E-10 -

2.76E-11 - - -

2.70E-06 Y 91 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 - - -

1.92E-04 ZR 95 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 NB 95 4.20E-08 1.73E-08 1.00E-08 -

1.24E-08 -

1.46E-05 MO 99 -

3.40E-05 6.63E-06 -

5.08E-05 -

1.12E-05 TC 99M 1.92E-09 3.96E-09 5.10E-08 -

4.26E-08 2.07E-09 1.15E-06 l

FC/ CMP /01 051892

l FORT CALHOUN STATION Ib C7 PAGE 40 OF 42 CHEMISTRY MANUAL PROCEDURE du 00) jd gaf\ ((2 CMP-6 INGESTION DOSE FACTOR 8 FOR INFANT (mrem per pC1 Ingested)

Page 2 of 2 Nuclidg Bone Liver T.Bodv_ Thyroid Kidney Lung GI-LLI_

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 RU 105 1.36E-07 - 4.58E-08 -

1.00E-06 -

5.41E-05 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 TE 129M 1.00E-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 -

5.97E-05 TE 129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 -

2.27E-05 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 I 131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 -

1.51E-06 I 132 1.66E-06 3.37E-06 1.20E-06 1.58.-04 3.76E-06 -

2.73E-06 I 133 1.25E-05 1.82E-05 5.33E-06 3.313-03 2.14E-05 -

3.08E*06 1 134 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 7.0?E-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 -

1.11E-08 -

4.29E-05 PR 144 2.74E-10 1.06E-10 1.38E-11 -

3.84E-11 -

4.93E-06 HD 147 5.53E-08 5.68E-08 3.48E-09 -

2.. 18 -

3.60E-05

" 187 9.03E-07 6.28E-07 2.17E-07 - -

3.69E-05 LP 239 1.11E-08 9.93E-10 5.61E-10 -

1.98E-09 -

2.87E-05 FC/ CMP /01 051892

FORT CALHOUN STATION  ? i)  ? C~) PAGE 41 OF 42 CHEMISTRY MANUAL PROCEDURE Jj f CMP-6 TABLE 15 RECOMMENDED VALUES FOR OTHER PARAMETERS Page 1 of 2 Parameter Symbol Definition Values f, Fraction of produce ingested grown in garden 0.76 of interest.

f, Fraction of leafy vegetables grown in garden 1.0 of interest.

P Effective surface density of soil (assumes a 240 kg/m2 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) 0.2 (for other particulates)

Sp Attenuation factor accounting for shielding 0.7 (for maximum provided by residential structures. individuale) 0.5 (for general population) t3 Period of long-term buildup for activity in 1. 31 x 10' hr sediment or soil (nominally 15 yr).

t, Period of crop, leafy vegetable, or pasture 720 hra (30 days, grass exposure during growing season. for grass-cow-milk-man path-way)

! 1440 hrs (60 days for crop /

vegetation-man I pathway) tr Transport time from animal feed-milk-man 2 days (for max.

provided by residential structures. individual) l 4 days (for gen.

population) t3 Time delay between harvest of vegetation or crops and ingestion.

1) For ingestion of forage by animals Zero (for pasture grass) 2160 hr (90 days for stored feed)

RECOMMEND 2D VALUES FOR OTHER PARAMETERS FC/ CMP /01 051892 i

m --

~ -

FORT CALHOUH STATION 7?

i 7 c7 PAGE 42 OF 42 CHEMISTRY MANUAL PROCEDURE a

) ]- J h

CMP-6 Page 2 of 2 Parameter

_Sy., Sol Definition Values

11) For ingestion of crops by man 24 hr (1 day, for leafy vege-tables & max.

individual) feed) 1440 hr (60 days for produce &

maximum in-dividual) 336 hr (14 days for general population) t, Environmental transit time, release to recep- 12 hr (for max.

tor (add time from release to exposure point individual) to ninimums shown for distribution) 24 hr (for gen.

population) 24 hr (for max.

individual) 168 hr (7 days for population sport-fish doses) 240 hr (30 days for population commercial fish doses) t, Average time from slaughter of meat-animal to 20 days consumption, Y.f Agricultural producitivity by unit area (mea- 0.7 kg/m2 (for sured in wet weight) grass-cew-milk p

man pathway) 2.0 kg/m3 (for produce or leafy vegeta-bles ingested j by man)

A,- Rate constant for removal of activity on plant 0.0023 hr'1 or leaf' surfaces by weathering (corresponds to a 14-day half-life) 1 l'

l

.FC/ CMP /01 051892 1

. : .- . -. . . . .- - . n