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Rev 9 to CAP-0002, Off-Site Dose Calculation Manual
	ML20203H735
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Site:	Rancho Seco
Issue date:	02/10/1997
From:	; SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:	;
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ML20203H704	List: ML20203H700; ML20203H713; ML20203H723; ML20203H735; ML20203H750;
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	CAP-0002, CAP-2, NUDOCS 9803030314
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ATTAC W NT 2 MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP-0002 PROCEDURES MANUAL REVISION: 9 OFF SITE DOSE CALCULATION MANUAL PAGE: 1 of 74

_ TITLE:

LEAD DEPARTMENT: EFFECTIVE DATE:

RADIATION PROTE.CTIONICHEMISTRY_ 02-10-97 SCOPE OF REVISION:

1. Changed default flow rate for the ABGLV release pathway to 31,000 cfm;

2. Changed the total gaseous efiluent flow to 152,740 cfm to reflect 1. above;

3. Added DQ 96 0055 as a reference for the new flow rate;

4. Minor editorial corrections.

THIS PROCEDURE IS ISSUED POR INFORMATION ONLY AND M1ALL NOT BE USED FOR WORK OR DESION. _ _

R PDR _

MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE: OFF SITE DOSE CALCULATION MANUAL PAGE: 2 of 74 TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE.......................................................,...........................................................4 2.0 SCOPE.......................................................................................................................4

1.0 REFERENCES

/COhihilThlENT DOCUhiENTS ........ .... ....... ............................... ..... .............. 4

.0DEFINITlONS.................................................................................................................6 5.0 RE S P O N S I B I L i T1 E S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

6. 0 P R OC E D U R E . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 6.1 O c n e r al Co n sid era t io n s. . . . . . . . . . . . . .. . . .. . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . - . . . . . . . . . . . . . . . . . . . .

6.2 Liquid hionit or Set point s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . .. . 12 63 hiaximum Emuent Concentrations in Liquid Emuents ... ..... .................. ........ ..... ............ I 3 6.4 Liquid Do se Calcuir t io ns . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15 6.5 Liquid Dose P roj ec tion s . . . .. . . . .. . . . . .. . . . . . . .. . .. . . . . . . . .. . . . . . . . .. . ... . . . . . . . . . . . . . . . . . . . . . . . . . . 16 6.6 G a seou s h io nit or S et point s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17 6.7 hlaximum Emuent Concentrations (hiECs)in Gascous Emuents.... ... .... ...... . . ........ .. .. 20 6.8 Do se Rat e Calculatio n s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ................21 6.9 Ai r Do se C alcul at i o n s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . - . . . . . .

6.10 Organ Dose Calculations for Gaseous Emuents...... ....... ....... . ..... ... .. .. .. .. . .... .. .... . 23 6.I1 Gas Dose Projections . ....... . ............................................... ......................25 6.12 Fuel Cycle Dose, ... .. . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . , . . . . . . . . . ......25 6.I3 EPA Reporting Requirements.. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 26 6.14 Technical Requirement s. . .......... . .... . .. .. ... .. . .. . . . ..... .... . . . . . . . . . . . , . . . . . . . . . . . .. .. 26

6. 1 5 R e p o rt s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 0 7.0 RECOkDS.,,.. ..........,,...............................................................................41 i

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MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP-0002 )

PROCEDURES MANUAL REVISION: 9 TITLE: OFF SITE DOSE CALCULATION MANUAL PAGE: 3 of 74 IAlli,E OF CONTENTS (Continued)

SECTION l%OE ATTACilMENTS

.41 I LIQUID EFFLULWT FLOW DIAGRAM. . . . .. ... . . . .

2 GASEOUS EFFLUENT FLOW DIAGRAM. . . . , . . .. . . . .43 3 DOSE FACTOR PARAMETERS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .44 4 ATMOSPilERIC DISPERSION AND DEPOSITION PARAMETERS. . . 47 48 5 SITE HOUNDARY FOR GASEOUS EFFLUENTS .

6 SITE DOUNDARY FOR LIQUID EFFLUENTS... . . . .49 7 lilSTORICAL LIQUID SOURCE TERMS .. . . . . .. .50

.51 LIQUID MONITOR DETECTOR EFFICIENCIES. . . .

8 ... .

9 ORGAN DOSE FACTORS FOR LIQUID EFFLUENTS., .. . . . . . .52 10 GASEOUS MONITOR DETECTOR EFFICIENCIES .. .. . .56 11 DOSE FACTORS FOR NOBLE GASES AND DAUGilTERS . . .57 12 ORGAN DOSE FACTORS FOR GASEOUS EFFLUENTS . .. .58 13 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION . . .60 14 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS. . . . . . . . . . . . .. . .61

!$ .62 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM . ..

16 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION. .66 17 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS. .. . . .. , . .69 18 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM. .. ,. 71

, .74 19 ODCM REVISION REVIEW REQUIREMENTS. ... . .

MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE: OFF SITE DOSE CALCULATION MANUAL PAGE: 4 of 74 LQ PURPOSE The OIT site Dose Calculation Manual (ODCM) contains the methodology and parameters used in the calculation of off site doses due to radioactive gaseous and liquid e0luents. Also, the ODCM contains the methodology for determining c01uent monitoring instrumentation alarni/ trip setpoints. Methods are described for assessing compliance with the Technical Requirements in the ODCM as they apply to 10 CFR Parts 20.1301 and 20.1302,10 CFR Part 50, Appendix 1, and 40 CFR 190.10a for liquid and gaseous ellluents. Additionally, the ODCM contains the Technical Requirements which provide the Speci0 cations, Applicabilitie., Actions, and Surveillance Requirements.

2.0 SfDPE This procedure functions as a manual that provides the basis for development of detailed implementing procedures that address dose calculations for liquid / gaseous releases and monitor setpoints. Additionally, this manual provides the Technical Requirements that govern releases of liquid and gaseous radioactive releases off site.

3A BEEEREECESLCOMMITAIERUKLCUMENIS 3.l . C iLitalenLDminic1111 3.1.1 Code of Federal Regulations, Title 10, Chapter 1, Pans 20,5016a and Part 50, Appendix I 3.1.2 Rancho Seco Permanently Defueled Technical Speci0 cations (PDTS) 3.1..I EPA 40 CFR Parts 302,355 Reporting Requirements

'.l.4 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Plant Operations 3J RefcausgJhcunicals 3.2.1 USNRC Regulatory Guide 1.109, Rev. I, Calculation of Annual Doses to Man from Reutine Releases of Reactor E0luents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1, October 1977 3.2.2 W. C. Burke, et. al., Freparation of Radiological E01uent Technical Speci0 cations for Nuclear Power Plants, NUREG 0133, USNRC:NRR, October 1978 3.2.3 ORNL, User's Manual for LADTAP 11, NUREG/CR 1276, May 1980 3.2.4 D. L. Strange, et al., LADTAP II, Technical Reference and User Guide, NUREG/CR-4013, Pacinc Northwest Laboratory, April 1986 3.2.5 Eckeiman, K. F., et. al., User's Guide to G ASPAR Code, NUREG 0597, USNRC:NRR, June 1980,in RSIC CCC 463

MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE: ,OFF-SITE DOSE CALCULAflON MANUAL PAGE: 5 of 74 32f USNRC Regulatory Guide I t il Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Ellluents in Routine Releases from Light Water Cooled Reactors 32.7 USNRC Regulatory Guide 1.21, Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Efiluents from Light Water Cooled Nuclear Power Plants 3.2.8 USNRC Regulatory Guide 4.1, Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants 3.2.9 REIMS Software Life Cycle Documents (Software Requirement Specification, Design Documera, Acceptance Test Plan) 3 2.10 USNRC & Pacific Northwest Laboratory, TDMC Computer Code / Data Collections, XOQD0Q 82, Radiological Assessment Code System Meteorological Evaluation of Routine Elliuent Releases at Nuclear Power Stations 3.2.11 1992 Rancho Seco Land Use Census 3.2.12 RSNGS USAR Chapters 11.1 11.5 3.2.13 RSNGS P&lD Drawing M 563, M 551, M 552, M 503 3.2.14 Pacific Northwest Laboratory, XOQD0Q: Computer Program for the Meteorological Evaluation of Routine Efiluent Releases at Nuclear Power Stations 3.2.15 Congel, F. J., Methods for Demonstrating LWR Compliance with the EPA Uranium Fuel Cycle Standard (40 CFR Part 190), NUREG 0543, USNRC:NRR, February 1980 l

3.2.16 USNRC Generic Letter,89 01, Dated January 31,1989.

3.2.17 Rancho Seco REMP Manual 3 2.18 Engineering Calculation Z-RDM 10279, Interim On site Storage (10S) Building Efiluent Radiation Monitor (Rl5106) Setpoint Determination 3.2.19 PDQ 92-063 3.2 20 RP 3121.14, Occupational Radiation Exposure Limits and Extensions 944- 3.2.21 DQ 96 0055, AllGLV flow rate measured above default value

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MANUAL. CHEMISTRY ADMINISTRATIVE NUMBER: CAP 0002 PROCEDURES MANUAL REVISION: 9 TITLE: OFF SITE DOSE CALCULATION MANUAL PAGE: 6 of 74 10 DEElElILQNS 4.1_ . Member of the Public Mgmber of thc_Public means any individual except when that individual is receiving an occupational dose.

12 .. .OccupAlionall101C Dscypalignal Dos . means the dose received by an individual in the course of employment in which the individual's assigned duties involve exposuie to radiation and/or to radioactive material from licensed and unlicensed sources of radiation, whether in the possession of the licensee or other person. Occupational dose does not include dose received from background radiation, as a patient from medica! practices, from voluntasy panicipation in medical research programs, or as a member of the public.

43 Public Dose Euhlic.Dnc means the dose received by a hiemhetof_1b Public from exposure to radiation and/or radioactive material released by a licensee, or to any other source of radiation under the control of a licensee. It does not include occupational dose or doses received from background radiation, as a patient from medical practices, or from voluntary participation in medical research programs.

4.4 lhidddcale A Listidlktch Release for 10 CFR 50 Appendix 1 considerations is a transfer of a discrete volume of radioactive liquid from a RHUT to a retantion basin. A Liquid Batch Release for 10 CFR 20 considerations is a transfer of a discrete volume of radioact i ve liquid from a reten: ion basin to the Waste Water discharge canal (the Environmental Release Point).

A Galcontihichlehus is the discharge of gaseous radioactive wastes of discrete volume.

Batch releases for the gaseous pathway are no longer planned.

4.5 Continuous Release A continuous radioactive gaseous release is the discharge of gaseous wastes of a nondiscrete volume from a system that may have an input flow during the release. These include the Auxiliary Building Stack (ABS), Auxiliary Building Grade Level Vent (ABGLV), and continuing Reactor Building purges.

Continuous radioactive liquid releases are not planned to be made from Rancho Seco Nuclear Generating Station (RSNGS),

4.6. Default RJdionuclide Mis A historical mixture of radionuelides that may be used to determine menitor setpoints.

MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE: OFF-SITE DOSE CALCULATION MANUAL PA.GE: 7 of 74 4.7- Dih1 ion Flow The volume or volume rate of tluid (liquid or gas) which is add;d to a radiological release stream for the purpose of decreasing the instantaneous concentration of the stream.

4.8 Mnimum Exposed 11]ypathetical) Individual The MuirnumlixamtdlndbidpJd is characterized as " maximum" with regard to food consumption, occupancy, and other usage or exposure pathway parameters in the vicinity of Rancho Seco that would represent an indivmual with habits greater than usually expected for the average of the population in general.

Maximum dose factor parameters will be determined using site specific data from the Land Use Census. Ifinformation needed to determine a parameter is not available, RG 1.109 parameters will be used All dose factor parameters used are listed in Attschment 3.

4.9 RSNGS Rancho Seco Nuclear Generating Station.

110 Site Boundgics The Site Boundaries are defined by the drawings in Attachments 5 and 6.

ill Nuisancs.fallnwys (1) Secondary system gaseous pathways where the calculated dose totals contribute less than 5% of the annual limits and de not need to be tracked for dose calculationa; purposes unless secondary activity reaches a predetermined Action Level.

(2) Sources of trace levels of radioactivity in liquid efiluents where the calculated dose totals contribute less than 1% of the annual limits and do not need to be tracked for dose calculational purposes. Trace levels are defined to be less than IE-8 pM/mi for the nuclides typically released from RSNGS. Examples include the oily water separator, plant etlluent inlet, and storm drains 4 12 Unplaungd.lklcals The unexpected release of radioactive matech.ls to unrestricted areas in gaseous and liquid efiluent. All unplanned releases shall be discussed in the Annual Radiological Ellluent Release Report (ARERR) to the NRC.

4.13 Miscellancmtdclcalc Release pathways which are considered planned but are not defined explicitly with monitoring requirements in this procedure. These pathways contribute a relatively small percentage (<5%)

to the annual dose limits but shall be tracked for ellluent activity accounting and dose

MANUAL: : CHEMISTRY ADMINISTRATIVE NUMBER: CAP-0002 1 PROCEDURES MANUAL I REVISlON: _9 -

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TITLE: OFF-SITE DOSE CALCULATION MANUAL PAGE: _ 8 of 74 -

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' calculation purposes Miscellareous releases shall not be reported in the ARERR'as abnormal

- or unplanned releases. The IOS Building is an example of a Miscellaneous Release.

i 54.14 Safety Factor (SF)

A number greater than unity used in calculations to introduce greater conservatism (larger.

- margin of safety) to otTset various uncerta:-9s in instrumentation and methods. Safety factors

'are set by Radiation Protection' Chemistry Supervision based on either analysis or professional i: judgment; Unless otherwise specified, the default value is two (2). i 4.15 Liquid Emuent Radwaste Treatment System (LERTS)

- The Liould Emuent Radwaste Treatment System is a system designed to reduce the quantity of radiosctive materials in liquid emuents by collecting liquid emuent and providing processing for j the purpose of reducing the total radioactivity prior to its release to the environment.

3- 4.16 V3nti_lation Exhaust Treatment System (VETS) i -

l The Ventilation Exhamtltntment System is the Reactor Building Purge Exhaust Filtering System and Auxiliary and Spent Fuel Building Filter Systems. These systems are designed and installed to reduce radioactive material in exhaust gases through HEPA filters for the purpose of l removing particulates from the gaseous exhaust stream prior to the release to the environment

(such a system is not considered to have any effect on noble gas emuents). Engineered Safety Feature (ESP) atmospheric cleanup systems are not considered to be Ventilation Exhaust Treatment System components. ,

L 4.17 Instrument Surveillance (1) Source Check A source check is the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.

- (2) -Channel Test r

- A channel test is the injection of an internal or external test signal into the channel to verify its proper response, including alarm and/or trip initiating action, where applicable.

(3) Instrument Channel Check .

I _

An instrument channel check is a verification of acceptable instrument performance by

; observation ofits behavior and/or state; this verification includes comparison of output and/or state ofindependent channels measuring the same variable.

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- MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP-000' 2 PROCEDURES MANUAL REVISION: 9 TITLE: OFF-SITE DOSE CALCULATION MANUAL PAGE: 9 of 74 (4) Instrument Channel Calibration An instrument channel calibration is a test, and adjustment (if necessary), to establish that the channel output responds with acceptable range and accuracy to known values of the parameter which the channel measures or an accurate simulation of these values. Calibration shall encompass the entire channel, including equipment actuation, alarm, or trip and shall be deemed to include the channel test.

i 4

4.18 Surveillance Intervals 2 The Surveillance Interval may be extended to a maximum of +25% to accommodate operations scheduling. The frequency notation (which follows the name of the Surveillance Intervalin

parenthesis) speci0ed for the performance of Surveillance Requirements shall correspond to the Surveillance Intervals defined below.

(1) Shin (S): A time period covering at least once per twelve (12) hours.

4 (2) Daily (D): A time period spaced to occur at least once per twenty four (24) hours.

(3) Weekly (W): A time period spaced to occur at least once per seven (7) days.

(4) Monthly (M): A time period spaced to occur at least once per thirty one (31) days.

(5) Quarterly (Q): A time period spaced to occur at least once per ninety two (92) days.

(6) Semiannually (SA): A time period spaced to occur at least once per six (6) months.

(7) Annually (A): A time period spaced to occur at least once per twelve (12) months.

(8) Refueling Interval (R); A time period spaced to occur at least once per eighteen (18)

, months.

(9) Each Release (P): This surveillance will be completed prior to each release.

, 4.19 Radiological Emuent Information Management System (REIMS)

. The computer sonware and database that tracks the volume and activity of released radioactive i emuents. In addition, the sonware provides the basis for the permitting process, calculates dose

to man, and summarizes data for inclusion into the ARERR.'

4.20 Onerable/Onerability A component or system is Qar.thls when it is capable'of performing it's intended function within the required range. The component or system shall be considered to have this capability when: (1)it satisfies the Specifications in Section 6.14, (2) it has been tested periodically in accordance with the Surveillance Requirement in Section 6.14 and has met its performance requirements, (3) the system has available its source of power, and (4) its required auxiliaries

a. are maintained available and capable of performing their intended function.

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MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE: OFF SITE DOSE CALCULATION MANUAL - PAGE: 10 of 74 LQ. RESPONSIBILITIES 5.1 Radiation Protection / Chemistry Suoerintendent it is the responsibility of the RP/ Chem Superintendent for the following:

1) ODChi Revisions and Reporting the Revisions in the Annual Radioactive Emuent Release Report (ARERR)

2) ARERR Preparation and Submittal

3) RElhtS Database

4) LADTAP, GASPAR, and XOQDOQ Computer Program Verifications and Changes ,

d 5.2 PRC The PRC is responsible for reviewing and accepting all changes to the ODChi with approval by the Plant hianager per Permanently Defueled Technical Specifications.

ftQ PROCEDURii 6.1 General Consid_erations (Ll.1 Liquid Emuent Pathways Attachment I provides a simplified diagram of the liquid emuent produced by RSNGS. The liquid emuent discharge of RSNGS forms the headwaters of Clay Creek.

Dilution of the liquid emuent occurs off site at the confluence of Clay and Hadselville Creeks, and of Hadselville and Laguna Creeks, an.d at the confluence of Laguna Creek and the Cosumnes River.

Planned radioactive liquid releases are directed through the A or B RHUTs to give reasonable assurance of compliance with 10 CFR 50 Appendix 1 prior to their discharge to the retention basins (North or South). Prior to discharge from the retention basins to the plant emuent (off-site), the discharge rate from the retention basins and the amount of dilution from Folsom Sov'h Canal are controlled to ensure compliance with the concentration requirements in 10 CFR 20, 6.1.2 Gaseous Emuent Pathways Airborne radioactive material in the various rooms and systems at RSNGS is routed and discharged in airborne emuent as illustrated schematically in Attachment T The figure shows the functional arrangements of these streams, treatment and controls, radioactivity monitoring points, and emuent release points.

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l j MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP-0002 PROCEDURES MANUAL l L REVISION: 9 ;

l TITLEi OFF SITE DOSE CALCULATION MANUAL PAGE: 11 of 74 Potential release pathways other than those specified in Attachment 2 have been identified.

These release pathways are classified as NUISANCE pathways and include the following:

1) Auxiliary Boiler Vents / Reliefs -

2) hiiscellaneous Secondary System Steam Discharges j 3) Tank Atmospheric Vents l

3 Past experience has shown that the above release pathways do not contribute to the dose totals because of the small quantities released and the low concentration of radioactive i

materials. Therefore, Action Levels may be established for the secondary system q concentrations of radioactive material to trigger when the above routine gaseous emuent i releases shall be evaluated for off site dose impact The Action Levels shall be based on j levels that could contribute more than 5% to the most restrictive yearly dose limit. Action

' Levels shall be maintained through RSNGS piocedures.

l

. Unplanned releases shall be evaluated on a case by case basis.

The Interim On site Storage (IOS) Building is a miscellaneous release.

l 6.1.3 hieteorological Data

, The atmospheric dispersion (X/Q) and deposition (D/Q) factors used in calculations involving airborne emuent are conservative default values. The default X/Q value is 1.0E-4

sec/m', and the default D/Q value is 1,0E-6 m 2 These factors should be used to determine j monitor setpoints, assess compliance with the gaseous emuent requirements in Section 6.14, and calculate the gaseous emuent dose reported in the ARERR.

Attachment 4 contains dispersion and deposition factors calculated using actual meteorological data. These factors should not be used for dose calculations. They are

presented for historicalinformation only. The factors are based on a 10-year annual average of meteorological data taken from January 1978 to December 1987. The raw data was I converted to X/Q and D/Q factors using the XOQ: OQ computer program.

614- Boundaries

' The Site Boundary for Gaseous Emuents as shown in Attachment 5 is for all calculations -

, involving gaseous emeents. The Site Boundary for Liquid Emuents as shown in Attachment 6 is for all calculations invohing liquid emuents. (Although the RHUTs are used as the dose

, accountabihty points for liquid emuents, the dose is considered to be received downstream of the boundary.)

6.1 5 ' 40 CFR 190 Comoliance t ' For the purposes of assessing compliance with 40 CFR 190,- the hfEhfBER OF THE

- PUBLIC which received the most exposure may be determined using actual food 1 m e r- r-w -

w --m-e y- wM

l MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP-0002 PROCEDURES MANUAL - 1 REVISION: 9 '

TITLE: ~ OFF SITE DOSE CALCULATION MANUAL - - PAGE: 12 of 74 -

consumption, actual occupancy rates, and dilution off site from additional converging streams (verses assumptions used for a HYPOTIIETICAL hiAXIMUM EXPOSED INDIVIDUAL based on Land Use Census data)J 61.6 Computers vs Manual Calculations Computer systems such as REIMS should be used for calculations in order to minimize error ;

and hasten the release process. However, in the event computers are not available for calculations, manual pre release calculations should be done based on the most historically restrictive receptor.

. 6.2 Liould Monitor Setooints The High alarm setpoint for the Retention Basin Emuent Discharge Monitor (R15017A)is based upon preventing the limits of the Specification in Step 6,14.2 from being exceeded. When the high alarm level is reached, any emuent discharges in progress are terminated or diverted to the Retention Basins.

A SAFETY FACTOR is included in the setpoint calculations to incorporate a margin of conservatism.

When a batch release is not occurring or the calculated setpoint is so low that it will cause spurious alarms, the monitor setpoint should be set close to background without causing spurious alarms or as determined by Radiation Protection / Chemistry Supenision.

The conversion factor and setpoint calculations should be performed based on the same radionuclide mix.

6.2.1 - Conversion Factors for F 1017A

- Provided here is the methodology to determine the conversion factor of counts per minute to microcuries per cubic centimeter for the Retention Basin Ellluent Discharge Monitor (R15017A). The conversion factor is based on the monitor's emeiency for each nuclide and the abundance of the nuclide. The mix ofisotopes used may be based on the historical mix provided in Attachment 7, current mix in the batch release, or as determined by Radiation Protection / Chemistry Supenision. The mix fraction shall be based on gamma emitting isotopes only.

The following equation shall be used to determine the conversion factor for R15017A:

.i CF - [(f, x E,)

Where:

CF = pCi/cc per cpm

MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE: OFF-SITE DOSE CALCULATION MANUAL PAGE: 13 of 74 f4 = Fraction of nuclide i to total activity of historical mix (Attachment 7) or batch mix Ei = Detector emeiency for nuclide 1(cpm 4tCi/cc) Attachment 8 6 2.2 High Alarm Setooint for R15017A (uCi/ml)

[Cg '

8 High Alarm (pCi/ ml) = y , + Cbkgd Ci SF X [ MECp s

Where:

C, = The concentration of gamma-emitting nuclide g in pCi/ml.

Ci = The concentration of nuclide iin pCi/ml. This term includes non-gamma emitters MECi = The MEC of radionuclide i from Appendix B to 10 CFR Part 20, Table 2, Column 2, in pCi/ml. The class with the most restrictive Emuent Concentration will be used for each isotope.

SF =

A SAFETY FACTOR which may be applied to incorporate a margin of conservatism (SF 2 l). (Default = 2)

Ca, =

The background reading of the monitor (pCi/ml).

6.3 Maximum Emuent Concentrations in Liquid Emuents The Maximum Efiluent Concentration Fraction is calculated to determine compliance with 10 CFR 20 requirements and the Specification in Step 6.14.2. Radioactive liquid emuent discharges normally originate in the RHUTs and are discharged into a retention basin. Samples are collected and analyzed from each retention basin prior to discharge to ensure that compliance with the Specification in Step 6.14.2 can be achieved.

In addition, calculations to determine the minimum dilution water flow rate and maximum retention basin discharge flow rate to ensure compliance are provided in this section. Any combination of minimum dilution flow rate and maximum discharge flow rate which satisfy the Specification is acceptable.

63.1 Maximum Emuent Concentration Fraction (MECF)

Lompliance with the Specification in Step 6.14.2 is anticipated when the MECF is less than or equal to 1,0. The MECF is calculated as follows:

l

- MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE: OFF-SITE DOSE CALCULATION MANUAL PAGE: - 14 of 74 e e F, Ci MECF = Z

_ i ( MECv . F. + F, Where:

MECF = The calculated fraction of Maximum Emuent Concentration in the radioactive liquid emuent discharged beyond the Site Boundary for Liquid Emuents (see Attachment 6).

= The concentration (prior to dilution) of radionuclide lin the batch of Ci liquid emuent in pCi/ml.

MECi= The MEC of radionuclide i from Appendix B to 10 CFR Part 20, Table 2, Column 2, in pCi/ml. The class with the most restrictive Emuent Concentration will be used for each isotope.

F, =

Discharge flow rate; the flow rate of the radioactive liquid batch release from the retention basin to the Waste Water Discharge Canal (Plant Emuent)in gpm,

=

F. The total available dilution water (Plant Emuent) flow rate at the time of discharge of the radioactive liquid emuent in gpm.

[ _ _ _ _ _ _ _ _ _ S3F _((,C, _@_E_C,y_mu st be 2 1.0 I 6.3 2 - Minimum. Dilution Water Flow Rate (Fum)

The minimum dilution water (Plant Emuent) flow rate (F .;o) is calculated as follows:

r ,3 Ci Ft = F,x y

SF xi,{ MECih Where:

F, =

A fixed emuent discharge flow (gpm)(as required by specific release restrictions),

SF = A factor which may be applied tt :orporate a margin of conservatism (SF 21).

l

, e- - - - - - - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE: OFF-SITE DOSE CALCULATION MANUAL PAGE: 15 of 74 NOTE l i

i SF x IfC/MECd must be 21 6.3 3 Maximum E1119snt Discharge Flow Rate (F,m,d The maximum ellluent discharge flow rate (F )is calculated as follows:

F, "r - -

SF x T f'Ci 3

_ B MECv.

Where:

F. = A fixed dilution water flow rate (gpm) (as required by specific release restrictions).

6.4 Liqui @ose Calculatinns This section provides the methodology to demonstrate compliance with the Specification in Step 6.14.3.

Site specific organ dose factors for liquid efiluents have been determined for the MAXIMUM EXPOSED INDIVIDUAL and are listed in Attachment 9. Dose factors (A;j,p) were derived using equations and methods in Regulatory Guide 1.109, Rev. I and LADTAP. The dose factor parameters used are listed in Attachment 3. As previously stated, site specific parameters should be used based on the Land Use Census in lieu of the values provided in RG 1.109 whenever possible.

The exposure pathways included in the Aij,p are those identified by the Land Use Census. The pathways considered for inclusion are:

. fresh water fish a fresh water invertebrate e river shoreline deposits e milk from cows that eat fresh or stored forage irrigated with Clay Creek water e meat from cows that eat fresh or stored forage irrigated with Clay Creek water

vegetation

(!.4.1 Liquid Efiluent Dose Equation

(((QxAipp)

D-F

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

t I

MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP-0002 PROCEDURES MANUAL REVISION: 9 ,

TITLE: OFF-SITE DOSE CALCULATION MANUAL PAGE: 16 of 74 i l

Where:

D.3

= Annual calculated dose (50 year dose commitment) to the organ (or total body)) of a maximally exposed individual of age group a (mrem /yr);

Q, = Activity ofisotope I released during the year (Ci/yr).

A,j., = Site specific dose factor for an organ (or total body)) for a person of age group a via pathwayp due to isotope f (mrem ff/Ci sec).

F = Annual average discharge volumetric flow rate (efiluent water plus dilution water)in ff/sec.

Because the dose rate varies linearly with activity release rate, the dose for a shorter period of time (mrem) may be calculated by substituting the activity released (Ci) during that period for Q,in the above equation, llowever, volumetric flow rates should not be averaged over a period less than a calendar quarter. More conservative flow rates are acceptable.

6.5 LiquitU203.hojettim .

31-day dose projections are calculated to show compliance with the Specification in Step 6.14,4. Quarterly and Annual dose projections are calculated in compliance with the Specification in Step 6.14.11.

The following equations shall be used:

31-Day Projection:

D,y = 31 x D'Y t y, Quarterly Projection:

D *'

Dpo, = 91.3 x t,

o Yearly Projection:

Y' Dpy, = 365.25 x t v, Where:

D,n- = 31-day dose projection.

. Dv, =

Cumulative annual dose to date.

tv, = Number of days into the year.

D, =

Quarterly dose cmiection.

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

MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP-0002

PROCEDURES MANUAL I REVISION: 9 TITLE: OFF SITE DOSE CALCULATION MANUAL PAGE: 17 of 74 Dou

= Cumulative quanerly dose to date.

tow

= Number of days into the quarter, 4

D,n = Annual dose projection.

i 6.6 Gaseous Monitor Setooints This step dces not apply to the IOS Building vent monitor (R15106). The calculations used to

! determine the setpoints for this monitor are contained in Reference 3.2.18.

The Gaseous Emuent Radiation Monitors have the capability to monitor gaseous emuents over three general ranges (high, middle and low) using four channels. In the permanently defueled mode, the middle and high ranges (Channels 2 and 3) are no longer necessary, and are no longer used or maintained, Channels 1 and 4 both operate in the low range and are the monitor 7

channels which are considered in this procedure.

f The Specification in Step 6.14.5 states that the gaseous emuent monitors shall have their alarm / trip setpoints set to ensure the limits of the Specification in Step 6.14.6 are not exceeded.

The conservative default atmospheric dispersion (X/Q) factor from Step 6.1.3 is used.

Compliance with the dose rate limits for noble gases specified in Step 6.14.6 is demonstrated by setting each gaseous emuent monitor alarm / trip setpoint so that an alarm / trip will occur at or

before the dose rate limit is reached.

A S AFETY FACTOR is included in the setpoint calculations to incorporate a margin of conservatism.

Maximum design flow rates for each release point will be used to calculate setpoints.

6.6.1 Conversion Factors for R15044. R15045. and R15546A Provided here is the methodology to determine the conversion factor of counts per minute to microcuries per cubic centimeter for the Auxiliary Building Stack Monitor (R15045),

Reactor Building Stack Monitor (R15044), and the Auxiliary Building Grade Level Vent Monitor (R15546A). The conversion factor is based on the monitor's emeiency of detection for each nuclide and the mix of the nuclide. The mix ofisotopes used should be based on Kr.

85, but may be based on the current mix in the continuous release, or as determined by Radiation Protection / Chemistry Supervision. The mix used for setpoint calculations and conversion factor calculations should be the same, w N T e- 7 m'- - - +

MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP-0002 PROCEDURES MANUAL REVISION: 9-TITLE: OFF-SITE DOSE CALCULATION MANUAL PAGE:- 18 of 74 The following equation shall be used to determine the conversion factor for R15044, R15045 and R15546A:

.i CF = [(fi x Ei)

.i .

Where:

CF_

= pCi/cc per cpm f, = Fraction of nuclide i to total activity of the mix used Ei = Detector emeiency for nuclide i, in epm per pCi/cc, Attachment 10 6.6.2 Gaseous Emuent Flow Rates Flow rates used in routine gaseous emuent calculations for the pathways listed below are conservative default values. These flow rates should be used to determine monitor setpoints, assess compliance with the gaseous emuent requirements in Section 6.14, and calculate the gaseous emuent dose reported in the ARERR, Gaseous emuent release points and maximum design flow rates used at RSNGS are as follows:

Reactor Building Stack 74,000 CFhi Auxii.ary Building Stack 47,740 CFht 9-c+ - Auxiliary Building Grade Level Vent 31,000 CFM Interim On site Storage Building Ventilation

8,050 CFhi

The Interim On-site Storage (IOS) Building is not subject to continuous discharges of radioactivity Because of the infrequer of a radioactive release, assessment will be done on each release according to administrative procedures.

6.63 De:ermination of Partition Factor (PJ The Specification in Step 6.14.6 applies to the entire site, not just one vent or monitor, Consequently, the total release rate must be partitioned among the three major vents (ABS, L ABGLV, RBS). For routine operations, the partition factor may tv calculated by assuming that the emuent concentration is the same for all pathways and usag a ratio of flow rates.

9-o The total volume flow rate for all three vents is 152,740 CFht. Therefore:

74,000 CFhi p ,

= 0.49 152,740 CFht

_._.7..~_....._._.___._

4 F

MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP-0002__ -

l

- PROCEDURES MANUAL- l

REVISION: 9-TITLEf- OFF-SITE DOSE CALCULATION MANUAL - PAGE: 19 of 74 9-+ 47,740 CFM

.p ,

=! 0.31 j

152,740 CFM 31,000 CFM s

PabWv = 152,740 CFM

= 0.20

.a

. Radiation Protection / Chemistry Supervision may elect to use a different set of partition -

, factors based on plant conditions. However, the sum of all the partition factors for the site '

must be less than or equal to unity (1).

'6.6.4' Channel 4 Noble Gas Setooint for R15044. R15045. and R15546A in uCi/sec A

3000 x Py a ECi 3

My = , + Bkgd SF x (X/Q) x 1 Ci x (Li + 1.1 x Mi)

- t.

Where:

My = Monitor setpoint for vent v (i.e., RBS, ABS, or ABGLV)in pCi/sec 3000 = Step 6.14.6 Specification limit for skin dose rate in mrem /yr P, = Partition factor for vent'v, dimensionless, which distributes the total site release rate among the three vents Ci = Concentration ofisotope lin gaseous effluent in Ci/cc. The mix ofisotopes

' used may be based on Kr-85, the current mix, or as determined by Radiation Protection / Chemistry Supervision.

= Safety Factor, dimensionless, (SF 2 l)

_SF.

)

= ' A conservative default atmospheric dispersion factor for a ground level X/Q release to a:ector at or beyond the S_ite Boundary for Gaseous Efiluents in sec/m', The default value in Step 6.l'3 will be used. .

Li = : A factor converting gamma radiation from noble gas radionuclide i to skin idose (mrem-m'/pCi-yr).f See Attachment Ilc

- Mi = _ A factor converting gamma radiation from noble gas radionuclide I to air dose

-(mrad-m'/pCi-yr)c See' Attachment 11; w

~' *

. Bkgd = ~ Monitor background reading in pCi/see m

%, , ,.ii. -n., e- y. v ,--wv, -,,.,.-=..,,--w -v .---.m-

MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP-0002

PROCEDURES MANUAL REVISION: 9 TITLE: OcF-SITE DOSE CALCULATION MANUAL PAGE: 20 of 74 -

6.6.5 Channel I Noble Gas Setooint for R15044. R15045. and R15546A in uCi/cc

= MR' + Bkgd MCv 472 x F, Where:

MC, = Monitor setpoint for vent v based on concentration in pCi/cc MR, = Monitor setpoint for vent v based on release rate in pCi/sec excluding the background term. That is, M, _ Bkgd F, = Maximum design volumetric flow rate for vent v in CFM as indicated in Step 6.6.2.

472 = 28317 ml/ff

1 min /60 sec Bkgd = Monitor background reading in pCi/cc

____q i i

! Channel 1 does not cause any automatic terminations or l

'.ayL t

d ib,1,e_a.lagms ,, _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ;'

6.7 Maximum Efilgent Concentrations (MECs)in Gaseous Efiluents In order to demonstrate compliance with 10 CFR 20.1301, which requires that the total MEC l fraction not exceed I when averaged over an entire year, the calculation is included in the i

Annual Radioactive Efiluent Release Repon. In addition, a four hour reporting requirement exists when the total MEC fraction exceeds 20 when averaged over one hour per 10 CFR 50.72. The following provides guidance on how to perform this calculation.

Maximum Efiluent Concentration Fraction (MECF) Equation

< C' 3 x F x 4.72E -4 x X / Q x TR MECF = T' TsMECv Where:

= The concentration of nuclide lin mci /cc.

Ci F = Maximum design volumetric flow rate in CFM as indicated in 6.6.2.

4

X/Q = - A conservative default atmospheric dispersion factor for a ground level release to a sector at or beyond the Site Boundary for Gaseous Efiluents in sec/m'. The default value in Step 6.1.3 will be used.

MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE: OFF-SITE DOSE CALCULATION MANUAL PAGE: 21 of 74 MECi = The MEC for nuclide i from Appendix B to 10 CFR Part 20, Table 2, Column 2 (pCi/cc). The class with the most restrictive Emuent Concentration will be used for each isotope.

TR = If the time of release is less than one hour, then this value is the duration of the transient in minutes divided by sixty. Otherwise, the Time Ratio (TR) is one. Dimensionless.

4.72E-4 = The conversion factor in min *m'/sec*fl'.

6.8 Dose Rate Calculations Compliance with the dose rate limits for noble cases in the Specification in Step 6.14 6 is demonstrated by setting each gaseous emuent monitor alarm setpoint so that an alarm will occur at or before either dose rate limit Specification in Step 6.14.6 is reached. In addition, the Specification in Step 6.14.6 provides a maximum limit on organ dose rate equivalent beyond the Site Boundary for Gaseous Emuents from tritium and all radioactive materials in particulate form with half-lives greater than 8 days. Compliance is determined by calculating the organ dose rate for the MAXIMUM EXPOSED INDIVIDUAL for the inhalation pathway only.

The dose rate due to noble gas is evaluated as follows:

Total Body; bis = (X / Q) x ELQ,i x Ki)

Y i Skin:

6 = (X / Q) x ZE 0,i x (Li + 1 lMi) y i Where:

= The total body dose rate from noble gases (mrem /yr)

D$

= The skin dose rate from noble gases (mrenv'yr)

D.

=

X/Q A conservative default atmospheric dispersion factor for a ground level release to a sector at or beyond the Site Boundary for Gaseous Emuents in sec/m'. The default value in Step 6.1.3 will be used.

= The release rate of noble gas radionuclide i from emuent vent v during the Qvi time of the release ( Ci/sec)

= A factor converting time integrated, ground-level concentration of noble gas Ki 3

radionuclide i to total body dose from its gamma radiation (mrem-m /pCi-yr).

See Attachment 11.

_ . _ . ~ _ . _ _ _ _ . . _ _ _ . _ . . . _ _ _ _ _ . . . _ _ . . _ . _ . _ . _ _ . _

1 MANUALL CHEMISTRY ADMINISTRATIVE NUMBER: CAP-0002 PROCEDURES MANUAL !

REVISION: 9 l TITLE: OFF-SITE DOSE CALCULATION MANUAL PAGE: 22 of 74 -

Li = A factor converting gamma radiation from noble gas radionuclide I to skin

. dose (mrem m'/ Ci yr). See Attachment 11.

- Mi = A factor converting gamma radiation from noble gas radionuclide i to air dose (mrad m'/pCi yr). See Attachment 11.

1.1 = A factor converting air dose from gamma radiation to skin dose equivalent (mrem / mrad)

The orpi dose rate resulting from inhalation is calculated with the equation:

Organ:

60g = (X / Q) x (((Qvi x Raji) v i Where

DO; = The dose commitment rate to organ) of a person in age group n (mrem /yr)

R.ji = The factor to convert air concenti:stion of radionuclide i to organj dose

commitment rate of a person in age group a exposed by inhalation '

(mrem m'/pCi-yr). See Attachment 12.

f Q,5 = The release rate of radionuclide I(not including Noble Gas nuclides), via

emuent vent v during the time of the release (pCi/sec)

Exposure to dose rate factors, R.j;, for inhalation are derived by using equation 13 in RG 1.109, Rev.1. Tables E-5, E-7, E 8, E-9, and E 10 are assumed to represent the Maximum Exposed Individual in the equation to derive R.j;.

Q9 Air Dose Calculations The Surveillance Requirement in Step 6.14.7 requires cumulative dose to air from radioactive efiluent noble gans to be determined in order to assess compliance with the Specification i_n Step 6.14.7. The air dose is evaluated in the sector of the maximum exposure at or beyond the Site Boundary for Gaseous Elliuent.

Air dose from noble gas gamma radiation is calculated cumulatively with the equation:

Dg - 3.17E-8 x [ (X/ Q) x (((Qyni x Mi)

v. I n .

Air' dose from noble gas beta radiation is calculated cumulatively with the equation:

L Db - 3.17E.8 x - [ (X/Q) x (((Qyni x Ni)

v _ i-n .

P 1

. MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: - CAP-0002 a PROCEDURES MANUAL _ .

j

- REVISION: 9- i

?

TITLE: OFF-SITE DOSE CALCULATION MANUAL PAGE: 23 of 74 Where: }

D, = The noble gas gamma dose to air (mrad)

= The noble gas beta dose to air (mrad)

Di X/Q = A conservative default atmospheric dispersion factor for a ground level release to a sector at or beyond the Site Boundary for Gaseous E01uents in sec/m'. The default value in Step 6.1.3 will be used.

Mi = A factor converting ground level concentration to gamma radiation from noble gas radionuclide i to air dose (mrad m'/pCl yr) ,

Ni = A factor converting ground level concentration to beta r:diation from noble- 4 gas radionuclide i to air dose (mrad m'/pCi yr) <

Q,,w = The quantity of each noble gas radionucl:de i in batch n released via efliuent stream v( Ci) 3.17E-8 = 1 yr/3.156E+7 see

~

Factors Mi and Ni are 10' pCi/pCi times the values in RG 1.109, Rev.1, Table B-1, Columns 4

- and 2, respectively. The computer codes GASPAR and REIMS may be used to perform these calculations.

6.10 Organ Dose Calculations for GaRon5E@nents The Surveillance Requirement in Step 6.14.8 requires the radiation dose or dose commitment to the Maximum Exposed (1-lypothetical) Individual accumulated from exposure to tritium and radioactive materials in particulate form having half lives greater than 8.0 days, that originate in efiluent air, be determined at least every month. The radiation dose or dose commitment accumulated during a calendar quarter and a year may not exceed values stated in the -

Specification in Step 6.14.8.

A person may be exposed to efiluent radioactive material of this type in air by inhalation or -

- indirectly via environmental pathways that involve deposition onto vegetation and the ground.

- The exposure pathways evaluated will include the following:

1

'p' Exposure Pathivav I Air -inhalation -

=2- Deposition onto ground - irradiation I' 3 Deposition onto vegetation - ingestion 4 Deposition onto forage - cow - milk - ingestion

~

5 . Deposition onto forage - meat animal - meat - ingestion 6 Deposition onto forage - goat - milk - ingestion

~

, ,~r _ -

._.c , -- . _ . . -

MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE: OFF-SITE DOSE CALCULATION MANUAL . PAGE: 24 of 74 The equation used to calculate the dose commitment to the Maximum Exposed (Hypothetical)

Individual from radionuclides other than tritium is: ,

l - D4 = [ (X / Q), x [MQ,; x R.jip)

P'l V i -

+[ P2 (D / Q ), x 7,,,,,, MQ,i x R.;;p )

v i .

l -

Where:

p = 1, i.e., air-inhalation, in the first term, and p = 2,3,4,5, and 6 in the second term of the equation i excludes H 3 4

D.; = The dose commitment to organ) of a person in age group a (mrem).

= The quantity of each radionuclide I, in particulate form having a half life Qw greater than 8.0 days, in air discharged via emuent stream v (pCi)

X/Q = A conservative default atmospheric dispersion factor for a ground level release to a sector at or beyond the Site Boundary for Gaseous Emuents in

- sec/m'. The default value in Step 6.1.3 will be used.

D/Q = A conservative default deposition factor. A Factor converting a ground level d

or building wake discharge in air to deposition on land (m ). The D/Q value in Step 6.1.3 will be used.

R.jip = A factor converting time integrated concentration of radionuclide lin air or deposited on vegetation and/or ground to radiation dose commitment to organ), including total body, of a person in age group a who is exposed via pathwayp.

When p=1, representing air-inhalation, R.j;, has units of mrem-m'/pCi-yr When p=2,3,4,5 or 6 in the second term of the equation above, representing pathways involving deposition, R.;;p has units of mrem m2-sec/yr-pCi When the radionuclide is H-3, R.j;p has units of miem-m'/pCi-yr.

Tritium is assumed not to _ deposit onto vegetation or the ground. Hence, the concentration in vegetation is assumed to be related to the local atmospheric concentratica as described in RG 1.109, Rev.1, Appendix C. The dose commitment to the Maximum Exposed (Hypothetical)

Individual from tritium in gasee :s emuent is calculated with the equation:

MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE: OFF-SITE DOSE CALCULATION MANUAL PAGE: 25 of 74 D.) = 3.17E - 8 < [ (X / Q), x [(Qw x R.jir, P. V -

Where:

p = 1, 3,4, 5, and 6 iincludes !! 3 only X/Q = A conservative default atmospheric dispersion factor for a ground level release to a sector at or beyond the Site Boundary for Gaseous Efiluents in sec/m'. The default value in Step 6.1.3 will be used.

3.17E-8 = years /sec Other terms as dermed above.

Dose factors R.;,, for RSNGS are derived using the equations and methods in RG 1.109, Rev.1, Appendix C. Values of parameters in RG 1.109, Rev.1, Table E-5 are assumed to represent the Maximum Exposed (Hypothetical) Individual unless Land Use Census data justify a different value. Any different values from default values will bejustified and added as a table to the ODCM. Values of other parameters recommended in RG 1.109, Rev.1, including those recommended in the absence of site specific data, are used in the equations to derive the dose factors. (GASPAR or REIMS may be used to perform the calculations.)

(3.11 Gas Dose Proicctions 31-Day Dose projections are calculated to show compliance with Step 6.14.9. Quarterly and Annual dose projections are calculated in compliance with the Specification in Step 6.14.11.

The dose projection equations are the same as used for liquid per Step 6.5.

6.12 Fuel Cvels.J101c if a calculated dose exceeds twice the limit of the Specification in Step 6.14.3,6.14.7,6.14.8, or a level in Table 3 of the REMP Manual is exceeded, an assessment of compliance with the Specification in Step 6.14.10 must be made.

Liquid dose calculations shall be made using the general methcdology of Step 6.4. Gas dose calculations shall be made using the general methodology of Steps 6.9 and 6.10. These methodologies are to be used as a guide and strict adherence is not required because the Fuel Cycle Dose Calculation is done to determine the actual dose received, not a hypothetical maximum. Therefore, parameters such as dilution beyond the site boundarf and residential shielding may be factored into the calculation.

The total body and organ doses shall be the result of summing the individual contributions from liquid, gas, and direct radiation sources for the e4Tected Member of the Public.

MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP-0002

~ PROCEDURES MAWUAL REVISION: 9 TITLE: OFF-SITE DOSE CALCULATION MANUAL' PAGE: 26 of 74 Irradiation. i.e., exposure to An external sc,arce of radiation, directly from the RSNGS nonnally ;

will be evaiuated with the ad of environmental dosimetry such as thermoluminescent dosimetry (TLD) or portat le ion chamber (PIC) measuiements.

6 13 EPA ReportinMJagiirements If a calculated dose exceeds the Specification limit of Step 6.14.2,6.14.3,6.14.6,6.14.7, or 6.14.8, an assessment of compliance with 40 CFR Parts 302 and 355, Reportable Quantity Adjustment - Radionuclides, must be made.

This involves determining the maximum quantity of radionuclides released in a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period and comparing the quantities to the values listed in 40 CFR 302 Appendix B. The " sum of the ratios" method shall be used to determine compliance. If the " sum of the ratios" is greater than

- one, the National Response Center shall be notified.

Since Rancho Seco's systems and procedures are set up to normally operate within the above limits, this condition is not expected to occur, therefore, specific implementation procedures to determine compliance are not required.

6.14 Technical Requirements 6 14.1 Liquid Efiluent Monitoring instrumentation Specifications:

The radioactive liquid efiluent monitoring instrumentation channels shown in Attachment 13 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Step 6.14.2 are not exceeded. The alarm / trip setpoints of these channels shall be determined in accordance with Step 6.2. l Applicability:

During releases via the retention basin efiluent discharge.

Action:

i) With a radioactive liquid efiluent monitoring instrumentation channel alarm / trip setpoint less conservative than a value which will ensure that the limits of Step 6.14.2 are met, immediately suspend the release of radioactive ellluents monitored by the afrected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.

2) With less than the minimum number of radioactive liquid efiluent monitoring 9 instrumentation channels OPERABLE, take the Action shown on Attachment 13.

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

MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP-0002 -

PROCEDURES MANUAL REVISION: 9 TITLE: OFF-SITE DOSE CALCULATION MANUAL PAGE: 27 of 74 Syrvsliance Requirements:

1) The maimum setpoint shall be determined in accordance with methodology as described in Step 6.2 and shall be recorded on the release permits.

1 2) Each radioactive liq'iid emuent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the INSTRUMENT CHANNEL CHECK, SOURCE j CIIECK, INSTRUMENT CHANNEL CALIBRATION, AND CHANNEL TEST at the ,

frequencies shown in Attachment 14.

i

3) Records shall be maintained in accordance with the Process Standards of all radioactive liquid emuent monitoring instrumentation alarm / trip setpoints. Maximum setpoints and calculations shall be available for review to ensure that the limits of Step 6.14.2 are met.

Bases.

During continuing operations leading to decontamination and decommissioning of the site, radioactively contaminated water will be processed, as necessary, to remove the activity according to the Process Control Program (PCP). After being processed as necessary, the water may be transferred to the 'A' and 'B' Regenerant Holdup Tanks (RHUTs). Pathways for water to reach the RHUTs are shown in Attachment 1, Liquid Emuent Flow Diagram.

Administrative controls provide reasonable assurance that any waste water that is radioactive is processed through the RHUTs prior to their release.

Water which is in the 'A' and 'B' RHUTs is transferred to the North or South Retention Basin. The water in a Retention Basin is released off site as a batch release. These releases are monitored by the Retention Basin Emuent Discharge Monitor.

)

Radioactive liquid emuent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid emuents during actual or potential releases of radioactive liquid emuents. The alarm / trip setpoints for these instruments shall be calculated in accordance with the methodology contained in this manual to ensure that the alarm / trip will occur prior to exceeding the limits of Step 6.14.2. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

6.14.2 Maximum Emuent Concentrations in Liquid FJllants Specifications:

The concentration of radioactive material released in liquid emuents at any time beyond the Site Boundary for Liquid Emuents (see Attachment 6) shall be limited to the concentrations specified in Appendix B to 10 CFR Part 20, Table 2, Column 2.

MANUAL: . CHEMISTRY ADMINISTRATIVE NUMBER: CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE: OFF-SITE DOSE CALCULATION MANUAL PAGE: 28 of 74 ApplicabililI This is applicable at all times.

AtliOLL With the concentration of radioactive material released from the site to areas beyond the Site Boundary for Liquid Emuents exceeding the above Specifications, immediately restore concentration within the required limits and report the event in the next Annual Radioactive Emuent Release Report.

Silmillance RequirementE The concentration of radioactive material at any time in liquid emuents released from the site to areas beyond the Site Boundary for Liquid Emuents shall be continuously monitored in accordance with Attachment 13.

The liquid emuent continuous monitor having provisions for automatic termination ofliquid releases, as listed in Attachment 13, shall be used to limit the concentration of radioactive material released at any time from the site to areas beyond the Site Boundary for Liquid Emuents to the limits given in the above Specificctions.

The radioactivity concentration of each Retention Basin to be discharged shall be determined prior to release by sampling and analysis in accordance with Attachment 15, Item A. The results of Retention Basin pre-release sample analyses shall be used with the calculational methods described in Step 6.3 to ensure that the concentration at the point of release is within the limits of the above Specification.

Da11 This Specification is provided to ensure that the concentration of radioactive materials released in liquid waste emuents from the site to areas beyond the Site Boundary For Liquid Emuents (see Attachment 6) will be less than the concentration levels specified in Appendix B to 10 CFR Part 20, Table 2. Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will resuh in exposures within the limits of 10 CFR Part 20.1301 to a hiEhiBER OF THE PUBLIC.

There are no continuous releases of radioactive materialin liquid emuents from the plant. All radioactive liquid emuent releases from the plant are by batch method.

6.14.3 Liquid Dose Calculations Specifications:

The dose or dose commitment to a hiAXIhiUhi EXPOSED (HYPOTHETICAL)

INDIVIDUAL from radioactive materials in liquid emuents released beyond the Site Boundary for Liquid Emuents (see Attachment 6) shall be limited to:

t MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE: OFF-SITE DOSE CALCULATION MANUAL PAGE: 29 of 74 _

1) Less than or equal to 1.5 mrem to the total body and to less than or equal to 5.0 mrem to any organ during any calendar quarter; and,

2) Less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ during any calendar year.

AppJicabihtv.

At all times.

ActioE With the calculated dose or dose commitment from the rele se of radioactive materials in liquid emuents exceeding any of the above Specifications, prepare and submit to the Commission within 30 days a Special Report. This Report will identify the cause(s) for exceeding the limit (s) and define the corrective actions to be taken to reduce the releases of radioactive material in liquid emuents and the propc ed corrective actions to be taken to assure that subsequent releases will be in compliance with the above Specifications.

Surveillance Requirements:

Cumulative dose assessments associated with the release of radioactive liquid efiluent shall be determined by sampling and analysis in accordance with Attachment 15, item B or item C, and calculations performed in accordance with the methodology described in Step 6.4 at the following frequencies:

1) Prior to the initiation of a release of radioactive liquid emuent from the A or B RIIUT; and,

2) Upon verification of monthly composite analysis results for radioactive liquid efiluent released from the A and B RHUTs.

A dose tracking system and administrative dose limits shall be established and maintained.

With the 31-day dose projection in excer.t of the limits in Step 6.14.4, adjust liquid efiluent operating parameters to give reasonable assurance of compliance with the dose limits of this Specification (10 CFR 50, Appendix 1 dose guidelines) and maintain radioactive liquid releases as low as is reasonably achievable.

Bases.

ODCM Step 6.14.3 is provided to implement the requirements of Sections ll.A, III. A, and IV.A of Appendix 1,10 CFR Part 50. This step implements the guides set forth in Section II. A of 10 CFR 50, Appendix 1. The Action statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of 10 CFR 50, Appendix I to assure that the releases of radioactive material in liquid efiluents will be kept "as low as is reasonably achievable " The dose calculation methodology in this manual implement the requirements in Section Ill. A of 10 CFR 50, Appendix 1 that confomiance

MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE: OFF-SITE DOSE CALCULATION MANUAL PAGE: 30 of 74 with the guides of 10 CFR 50, Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in this manual for

, calculating the doses due to the actual release rates of radioactive materials in liquid efiluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor EfIluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1," Revision 1, October 1977 and Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Efiluents from Accidental and Routine Reactor Releases for the Purpose ofimplementing Appendix 1," April 1977. There is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in finished drinking water that are in excess of the requirements of 40 CFR 141.

The Lower Limits of Detection established in Attachment 15, item B are based on an estimated maximum annual efIluent outflow of 2 million gallons with a minimum annual average flow rate in the plant efiluent stream of 6,000 gallons per minute. The RHUT pre-release and monthly composite Lower Limits of Detection equate to an oft-site dose ofless than 10 percent of the 10 CFR 50, Appendix I guidelines. These Lower Limits of Detection, along with the dose tracking system, give reasonable assurance that the dose limits prescribed in ODCM Step 6.14.3 (the 10 CFR 50, Appendix I dose guidelines) will be met.

6 14.4 Liquid Etlluent Radwute Treatment Sprideations:

The LIQUID EFFLUENT RADWASTE TREATMENT SYSTEM shall be OPERABLE.

The appropriate portions of the system shall be used to reduce the quantity of radioactive materials in liquid ellluents prior to their discharge when projected doses due to the liquid elliuent beyond the Site Bouncary for Liquid Efiluents (see Attachment 6), when averaged over 31 days, would exceed 0.25 mrem to the total body or 0.83 mrem to any organ (8.33%

of the 10 CFR 50, Appendix 1 annual guidelines).

Applicability:

At all times, tkl10E With the LIQUID EFFLUENT RADWASTE TREATMENT SYSTEM inoperable for more than 31 days or with radioactive liquid waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days a Special Report which includes the following information:

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

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

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

Suiveillansc_ Requirements:

- Doses due to liquid releases to areas beyond the Site Boundary for Liquid Emuents shall be projected prior to each RHUT release in accordance with the methodology described in Step 6.5 when LIQUID EFFLUENT RADWASTE TREATMENT SYSTEMS are not being fully ,

1 utilized. The installed LIQUID EFFLUENT RADWASTE TREATMENT SYSTEM shall be considered OPERABLE by meeting the Specifications in Steps 6.14.2 and 6.14.3.

01Let The OPERADILITY of the LIQUID EFFLUENT RADWASTE TREATMENT SYSTEM ensures that this system will be available for use whenever liquid emuents require treatment pior to release to the environment. The requirement that the appropriate portions of this

- system be used, when specified, provides reasonable assurance that the releases of radioactive materials in liquid efiluents are maintained "as low as is reasonably achievable."

This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section II.D of Appendix I to 10 CFR 50. The specified limits governing the use of appropriate portions of the LIQUID EFFLUENT RADWASTE TREATMENT SYSTEM are the dose design objectives set forth in Section II.A of Appendix 1,10 CFR Part 50, for liquid effluents.

6.14.5 Gaseous Emuent Monitoring instrumentation Specifications:

The radioactive gaseous efiluent monitoring instrumentation channels shown in Attachment 16 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Step _

6.14.6 are not exceededi The alarm / trip setpoints of these channels shall be determined in accordance with the methodology contained in this procedure. Continuous samples of the gaseous emuent for radioactive particulate material shall be taken as indicated in Attachment 16.-

- Applicability:

-This is applicable at all times.

Action:-

_ 1) Withla radioactive gaseous efiluent monitoring instrumentation channel alarm / trip setpoint less conservative than a value which will ensure that the limits of Step 6.14.6 are met, immediately suspend the rC- of radioactive gaseous elliuents monitored by the affected ,

. channel,- _or declare the channel inoperable, or change the setpoint so it is acceptably conservative.

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2) With less than the minimum number of radioactive gaseous efiluent monitoring instrumentation channels OPERABLE, take the Action shown in Attachment 16. Exert best efforts to return the instrument to OPERABLE status within 30 days and if unsuccessful, explain in the next Annual Radioactive Efiluent Release Report why the inoperability was not corrected in a timely manner.

Surveillanedsguirements:

The maximum setpoints shall be determined by procedures implementing the methodology presented in this procedure and shall be recorded on release permits.

Each gaseous efiluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the INSTRUMENT CHANNEL CHECK, sol'RCE CHECK, INSTRUMENT CHANNEL CAllBRATION, AND CHANNEL TEST at th, frequencies shown in Attachment 17.

Records shall be maintained in accordance with the Process Standards of all radioactive gaseous emuent monitoring instrument alarm / trip setpoints Maximum setpoints and setpoint calculations shall be available for review to ensure that the limits of Step 6.14.6 are met.

Blfis The radioactive gaseous etlluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous efiluents during actual or potential releases of radioactive gaseous emuents. The alarm / trip setpoints for these instmments, except for the Interim On-site Storage (IOS) Building vent monitor (R15106),

shall be calculated in accordance with the methodology contained in this manual to ensure that the alarm / trip will occur prior to exceeding the limits of ODCM Step 6.14.6. The monitor setpoints for R15106 are set statistically high enough above background to pievent spurious alarms, yet stop potential radioactive releases when detected (Reference 3.2.18).

The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60,63, and 64 of Appendix A to 10 CFR Part 50.

The IOS Building has a ventilation system which provides protection against radioactive airborne releases. Operation of the ventilation system produces a negative pressure in the building. During operation, the ventilation exhaust flow is continuously monitored for particulate activity. Upon an alarm, the exhaust duct closes and the supp.; and exhaust fans stop, minimizing any chance of an airborne release. Although no planned airborne radioactive releases are anticipated from this pathway, the ventilation exhaust monitor is included in Attachment 16.

Fuel Storage Building exhaust is directed to the Auxiliary Building Stack where the exhaust is filtered and monitored for any activity prior to release to the atmosphere.

l MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE: OFF-SITE DOSE CALCULATION MANUAL PAGE: 33 of 74 6.14.6 Gaseous Dose Rates Specifications:

The dose rate due to radioactive materials released in gaseous emuents from the site to areas at or beyond the Site Boundary for Gaseous Emuents (see Attachment 5) shall be limited to the following values:

1) The dose rate limit for noble gases shall be less than or equal to 500 mrem /yr to the total body and less than or equal to 3000 mrem /yr to the skin; and,

2) The dose rate limit for tritium and for all radioactive materials in particulate form with half-lives greater than 8 days shall be less than or equal to 1500 mrem /yr to any organ.

Apolicability:

This is applicable at all times.

4 Action:

With the dose rate (s) exceeding the above limits, immediately restore the release rate to within the limit (s) specified and report the event in the next Annual Radioactive Emuent >

Release Report.

Surveillance RequiremenJE The noble gas emuent continuous monitors, as listed in Attachment 16, shall use monitor setpoints to limit the dose rate in unrestricted areas to the limits in the above Specification.

In the event a noble gas emuent exceeds the setpoint ofits monitor, an assessment of compliance with the Specification above shall be made in accordance with the methodology ccntained in this manual.

The relere ;aie of radioactive materials, other than noble gases, in gaseous emuents shall be

- determined by obtaining represen:ative samples and performing analyses in accordance with the sampling analyses program specified in Attachment 18.

The dose rate due to tritium and all radioactive material in particulate form with half lives greater than 8 days, released in gaseous emuents, shall be determined to be within the limits ,

of this Specification by using the results of the sampling and analysis program specified in Attachment 18 and the methodology described in Step 6.8.

DJt1CL Step 6.14.6 is provided to ensure that the dose rate from gaseous emuents due to immersion or inhalation at any time at the Site Boundary for Gaseous Emuents (see Attachment 5) will

- be within the annual dose limits of 10 CFR Part 20 for MEMBERS OF THE PUBLIC. The i H

- _ - _ _ - _ _ _ _a

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MANUAL: - CHEMISTRY ADMINISTRATIVE NUMBER: - CAP-0002.

PROCEDURES MANUAL REVISION: 9 TITLE: OFF.SlTE DOSE CALCULATION MANUAL PAGE: 34 of 74 annual dose limits are the doses associated with the cor.centrations of Appendix B to 10 CFR q- Part 20. Table 2, Column 1. These limits provide reasonable assurance that radioactive O material discharged in gaseous emuents will not result in the exposure of an individual at or c beyond the Site Boundary for Gaseous Emuents to annual average concentrations exceeding:

the dose rate equivalent, on which the limits specified in Appendix B, Table 2 of 10 CFR Part 20 were deri' :d. For individuals who may at times be within the Site Boundary for Gaseous .

Emuents, the occupancy of the individual will be sumciently low to compensate for any

- increase in the atmospheric diffusion factor above that for the boundary. The specified

release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the Site Boundary for Gaseous Emuents to less than or equal to 500 mrem /yr to the total body or to less than or equal to 3,000 mrem /yr to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose 4

rate above background to a person of any age group via the inhalation pathway to less than or equal to 1,500 mrem /yr. ,

6.14.7 Gamma and Bela Air Dms

Specifications

The air dose due to noble gases released in gaseous emuents to areas at or beyond the Site Boundary for Gaseous Emuents (see Attachment 5) shall be limited to the following:

+ 1) During any calendar quarter, to less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation; and,

2) During any calendar year, to less than or equal to 10 mrad for gamme. radiation and to less a than or equal to 20 mrad for beta radiation.

Applicability; This is applicable at all times.

Action.

.With tl,e calculated air dose from radioactive noble gases in gaseous emuents exceeding any of the above limits, prepare and submit to the Commission within 30 days a Special Report.

This Report will identify the cause(s) for exceeding the limit (s) and define the corrective action (s) taken to reduce the release of rad:oactive noble gases on gaseous emuents, and the corrective action (s) to be taken to assure that subsequent releases will be in compliance with the above limits?

Surveillance Reauirements' Cumulative air dose contributions for the current calendar quarter and calendar year shall be determined in accordance with the methodology in Step 6.9 at least monthly.

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Step 6.14.7 is provided to implement the requirements of Sections 11.11, Ill. A, and IV. A of Appendix 1,10 CFR Part 50 This step implements the guides set forth in Section ll.B of Appendix 1. The Action statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV. A of Appendix ! to assure that the releases of radioactive material in gaseous ellMnts will be kept "as low as is reasonably achievable."

The Surveillance Requirements implement the requirements in Section Ill.A of Appendix I that conformance with the guides of Appendix 1 be shown by calculational procedures based on models and data such that the a:tual exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated The dose calculations established in this manual for calculating the doses due to the actual release rates of radioactive noble gases in gaseous efiluents are consistent with the methodology provided in Regulatory Guide i 109. " Calculation of Annual Doses to Man from Routine Releases of Reactor Efiluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1," Revision 1, October 1977 and Regulatory Guide 1.111. " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Elliuents in Routine Releases from 1.ight Water Cooled Reactors," Revision 1, July 1977. The equations in this manual provide for determining that the air doses at the Site lloundary for Gaseous Ellluents (see Attachment 5) are based upon the historical average atmospheric conditions (L14 6 Casto3 L0tganDme Specifications; The dose or dose commitment to a MAXIMUM EXp0 SED (llYp0TilETICAL)

INDIVIDUAL from tritium and radioactive materials in particulate form with half lives greater than eight days in gaseous ellluents released to areas at or beyond the Site lloundary for Gascons Elliuents (see Attachment 5) shall be limited to the following:

1) During any calendar quarter, to less than or equal to 7.5 mrem to any organ; and,

2) During any calendar yeat to less than or equal to 15 mrem to any organ.

AppliGhility;

-This is applicable at til times N N rn With the calculated dose or dose commitmen: from the release of tritium and radioactive materials in particulate form with half-lives greater than eight days in gaseous efiluents exceeding any of the above limits, prepare and submit to the Commission within 30 days a Special Report. This Report will identify the cause(s) for exceeding the limit and d: fine the corrective actions to be taken to reduce the releases and the proposed corrective actian(s) to I

MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP 0002 PROCEDURES MANUAL REVISION. 9 TITLE: OFF. SITE DOSE CALCULATION MANUAL PAGE: 36 of 74 be taken to assure that subsequent releases will be in compliance with the above annual limits.

SuntillansdtquitsmentE Cumulative dose contributions for the current calendar quarter and calendar year r:riod shall be determined in accordance with the methodology described in Step 6.10 at least monthly.

IIAME Step 6.14.8 is provided to implement the requirements of Sections ll.C, III. A and IV. A of Appendix 1,10 CFR Pan 50. The Speci0 cations are the guides set forth in Section ll.C of 10 CFR 50, Appendix 1. The Action statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV. A of to CFR 50, Appendix 1 to assure that the releases of radioactive materials in gaseous emuents will be kept "as low as is reasonably achievable." The calculational methods speciued in the Surveillance Requirements implement the requirements in Section Ill. A of 10 CFR 50, Appendix ! that conformance with the guides of 10 CFR 50, Appendix 1 be shown by calculational procedures based on models and data, such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated For individuals who may at times be within the Site Boundary for Gaseous Emuents, the occupancy of the individual will be sumciently low to compensate for any increase in the atmospheric dispersion factor above that for the boundary.

The calculational methods for calculating the doses due to the actual release rates of the subject materials are consistent with the methodohgy provided in Regulatory Guide 1.109,

" Calculating of Annual Doses to Man from Routine Releases of Reactor Emuents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1, Revision 1, October 1977 and Regulatory Guide 1.111," Methods for Estimating Atmospheric Transport and Dispersion of Gaseaus Emuents in Routine Releases from Light Water-Cooled Reactors,"

Revision 1, July 1977. These equations also provide for estimating doses based upon the historical average atmospheric conditions.

The release rate speciucations for radioactive materials in particulate form are dependent on the existing radionuclide pathways to man in areas at or beyond the Site Boundary for Gaseous Emuents (see Attachment 5). The pathways which were examined in the development of these calculations are: (1)individualinhalation of airborne radionuclides,(2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and (4) deposition on the ground with subsequent exposure of man.

MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE: OFF SITE DOSE CALCULATION MANUAL PAGE: 37 of 74 6.14 9 Ventilalienhhau1LTJialmenLSyltem Speriftcalient The VENTILATION EXilAUST TREATMENT SYSTEM shall be OPERABLE. The installed VENTILATION EXilAUST TREATMENT SYSTEM shall be considered OPERABLE by meeting the Specifications in Steps 6.14.6,6.14.7, and 6.14.8.

Also, the following two conditions shall not exist simultaneously:

1) Gaseous waste is being discharged without treatment, and,

2) The projected doses due to gaseous elliuent releases from the site (see Attachment 5),

when averaged over 31 days, would exceed 2% of the 10 CFR 50, Appendix I annual dose guidelines (0.3 mrem to any organ, or air doses of 0 2 mrad from gamma radiation or 0.4 mrad from beta radiation).

Applicaldlilm This is applicable at all times ActicE If both parts 1) ard '2) of the Specification are satisfied, prepare and submit to the Commission within 30 days a Special Report pursuant to Technical Specification D6 9.7 which includes the following information:

a. Explanation of why gaseous radwaste was being discharged without treatment, and identification of the equipment or subsystems not OPERABLE and the 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.

SunTillmitelcQuittmtDIE Doses due to gaseous releases to areas at and beyond the Site Boundary for Gaseous Ellluents (see Attachment 5) shall be projected at least once per 31 days in accordance with the methodology and parameters in Step 6.11.

DOP tests will be performed on the llEPA filters in the Ventilation Exhaust Treatment Systems every 18 months, or aller any work has been performed on the IIEPA filter systems which could alter their integrity.

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j Dnn :

l 1 The OPERABILITY of the VENTILATION EXilAUST TREATMENT SYSTEM ensures that the systems are available for use whenever gaseous ellluents require treatment prior to i '

release to the environment. The requirement that the appropriate portions of these systems i

be used, when specified, provides reasonable assurance that the releases of radioactive l j materials in gaseous efiluents are maintained "as low as is reasonably achievable " Step ,

j 6.14.9 implements the requirements of 10 CFR 50.36a, General Design Criterion 60 of !

1 Appendix A to 10 CFR $0, and the design objectives given in Section li.D of Appendix ! to l 10 CFR 50. The specided limits governing the use of appropriate portions of the systems l and the dose design objectives set forth in Sections 11.H and li.C of Appendix 1,10 CFR $0, for gaseous ef0uents.

614.10 FuelCysicJms

! SntcifKniinit The dose or dose commitment to any real MEMBER OF Tile PUBLIC due to releases of radioactive material in gaseous and liquid elliuents and to direct radiation from uranium Ibel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ !*

(except the thyroid, which is limited to less than or equal to 75 mrem)in a calendar year.

ApritcaMily; i

i At all times.

8 l Actin!t l) With the calculated doses from the release of radioactive material in liquid or

gaseous elliuents exceeding twice the limits of Specifications in Steps 6.14.3,6.14.7, ,

6.14.8 or exceeding the reporting levels in Table 3 of the REMP Manual, calculations shall be made including direct radiation contributions (including outside storage tanks, etc.) to determine whether the above specifications have been l

exceeded.

2) If the above limits have been exceeded, prepare and submit to the Commission within 30 days, a Special Report that defines the corrective action to be taken to

reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits This Special Report, as defined in 10 CFR Part 20.2203(a)(4), shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF Tile PUBLIC from uranium fuel cycle sources, including all efiluent pathways and direct radiation,in a calendar year that includes the release (s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations.

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3) If the estimated dose (s) exct, d the above limits, and if the release condition resulting in the violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provision of 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

SMD'CillanCt.lltquirements:

Cumulative dose contributions from liquid and gaseous emuents shall be detennined in accordance with the Step 6.14.3,6.14.7, and 6.14.8 Surveillance Requirements.

Cumulative dose contribt.tions from direct radiation (including outside storage tanks, ete )

shall be determined in accordance with Step 6.12. This requirement is applicable only under the conditions set forth in the above Action statements, llaicE Step 6.14,10 is provided to meet the dose limitations of 40 CFR 190 that have been incorporated into 10 CFR 20 by 46 FR 18525. The specification requires the preparation and submittal of a Special Report whenever the calculated doses from plant radioactive ellluents exceed twice the numerical guides for design objective doses of 10 CFR 50, Appendix ! or exceeds the reporting levels of the Radiological Environmental hionitoring Program. For the Rancho Seco site, it is unlikely that the resultant dose to a h1EhiBER OF Tile PUBLIC will exceed the dose limits of 40 CFR 190 if the plant remains within twice the numerical guides for design objectives of to CFR 50, Appendix 1 and if direct radiation (outside storage tanks, etc.)is kept small. The Special Report will describe a course of action which should resuit in the limitation of the dose to a hiEhiBER OF Tile PUBLIC for a calendar year to within the 40 CFR 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the h1Eh1BER OF Tile PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 5 miles must be considered if the dose to any h1EhillER OF Tile PUBLIC is evaluated to exceed the requirements of 40 CFR 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR 190 have not already been corrected), in accordance with the provisions of 40 CFR 190 is considered to be a timely request and fulfills the requirements of 40 CFR 190 until NRC staff action is completed An individualis not considered a hiEhiBER OF Tile PUBLIC during any period in which he/she is engaged in carrying out any operation which is pan of the uranium fuel cycle.

/

6.1411 OqancLAunnal Dose Projetdans SnttiEtadent -

The projected dose contributions from liquid and gaseous elliuents for the current calendar quarter and current calendar year shall be calculated according to the methodology in Steps 6.5 and 6.11 at least every 31 days.

MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE: OFF. SITE DOSE CALCULATION MANUAL PAGE: 40 of 74 Applicabilits At all times.

Actiom With the required dose calculations not being performed, best elTort will be exened to perform the calculations once the deficiency has been identified. Corrective actions will be taken and documented to prevent teoccurrence.

Siin'cillanttRestitttttn!)

1) Liquid Emuents Projected dose contobutions shall be determined at least every 31 days

2) Gaseous Emuents Projected dose contributions shall be determined at least every 31 days.

IhssE This step is provided to implement the requirement of Technical Specification D613.a 5.

Dose projections provide a means of determining if current release practices will be within the dose limits of 10 CFR 50, Appendix 1. Calculating projected dose totals every 31 days provides information which can be used to keep emuent releases "as low as is reasonably achievable" Calculations performed during the first 15 days of the calendar year or calendar quarter will result in artificially high dose projections which provide no usable information.

6 15 Rep _ons 6.15.1 Annual Radioactive Emuent Reltne Report (ARERR)

The AIERR covering the activities of the unit during the previous 12 months shall be submitted within 60 days afler January 1 of each year. The report shall include the following:

(1) Summary of the quantities of radioactive liquid and gaseous emuents released from the unit.

(2) Summary of solid waste shipped from the unit.

(3) All unplanned releases of radioactive materials in gaseous and liquid emuents to unrestricted areas shallinclude a description of the event and equipment involved, cause(s), action (s) taken to prevent recurrence, t A consequences.

MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP-0002 PROCEDURES MANUAL REVISION: 9 :

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(4) Dose or dose commitment assessments to ensure compliance with the specifications in l 6.14.3,6.14,7, and 6.14.8. l (5) Complete, legible copy of the entire ODChi and/or REhfP hianual if changes occurred l during the ARERR reporting period. The copy may be part of the ARERR or sent concurrently, t

(6) The ARERR shall also include events described in 6.14.2,6.14.5, and 6.14.6. i 6 15.2 30 Day Repsm The following 30 day reports should be submitted if the criteria are met as stated in the following areas:

(1) 6.14.3 Liquid Dose Calculations (2) 6.14.4 Liquid Dose Projections (3) 6.14.7 Gamma and Beta Air Dose (4) 6.14.8 - Gaseous Organ Dose

($) 6.14.9. Gaseous Dose Projections i (6) 6.14.10 - Fuel Cycle Dose la RECORDS The individual / packaged documents and related correspondence completed as a result of the performance or implementation of this procedure are records. They shall be transmitted to Records hianagement in accordance with RSAP-0601, Nuclear Records hianagement.

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" MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP-0002 PROCEDURc8 MANUAL REVISION: 9 TITLE: OFF SITE DOSE CALCULATION MANUAL PAGE: 42 of 74 LIOUID EFFLUENT FLOW DIAGRAM LlOUID EFFLUENT FLOW DIAGRAM

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. Attachment i Page1ofI

MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE: OFF SITE DOSE CALCULATION MANUAL PAGE: 43 Of 74 GASEOUS EFFLUENT FLOW DIAQlMM GASEOUS EFFLUENT FLOW PATH PLANT YENTS r-3 p v3 g 4-4 d AUX BLDG EXHAUST PLENUM]

-AA A AUX BLDG e COMPACTOR ROOM RsSLDG

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, AUX BLDG e MW EVAP ROOM AUX BLDG 44- - GRADE AREA m EAST / WEST DH GRADE LEVEL! VENT $ 0 COOLER ROOMS VENT [j! 4~

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= HEPA FILTER Attachment 2 Page1of1

f MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP 0002 PROCEDURES MANUAL REVISION: 9 TITLE: OFF. SITE DOSE CALCULATION MANUAL PAGE: 44 of 74 DOSE FACTOR PARAMIITERS CONSUMPTION AND USAGE PARAMETERS PATIIWAY AGE I.109 DEFAULT RSNGS Irrigated Stored Vegetables Adult 520 kg/yr 520 kg/>T Teen 630 kg/>T 630 kg/>T Child 520 kg/yr 520 kg/>T Infant 0 kg/>T 0 kg/>T Irrigated Fresh Vegetables Adult 64 kg/yr ,

64 kglyr Teen 42 kg/yr 42 kg/yr Child 26 kg/yr 26 kglyr Infant 0 kglyr 0 kg/>T Irrigated Milk Adult 310 kg/yr 310 kg/yr Teen 400 kg/yr 400 kglyr Child 330 kglyr 330 kglyr l Infant 330 kglyr 330 kg/>T Irrigated Meat & Poultry Adult 110 kglyr 110 kg/>T Teen 65 kglyr 65 kglyr Child 41 kg/yr 41 kglyr Infant 0 kglyr 0 kglyr Fish Adult 21kglyr 21 kg/yr Teen 16 kg/yr 16 kg/>T Child 6.9 kg/yr 6.9 kg/>T Infant 0 kg/>T 0 kg/yr Other Seafood Invertebrate Adult 5.0 kglyr 6.9 kg/>T (Cray6th) Teen 3.8 kg/yr 5.2 kglyr Child 1.7 kglyr 2.2 kg/yr Infant 0 kglyr 0 kg/yr Algac Adult None 0 kg/yr Teen None 0 kglyr Child None 0 kglyr Infant None 0 kg/yr Water Usage (Drinking Water) Adult 7301/yr 01/yr Teen 5101/yr 01/yr Child $10 t/yr 01/yr Infant - 3301/yr 01/yr Attachment 3 Page1of3

MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP 0002 !

PROCEDURES MANUAL '

REVISION: 9 TITLE: OFF. SITE DOSE CALCULATION MANUAL PAGE: 45 of 74 .

DOSE FACTOR PARAMETERS (Continued) 4 CONSUMPTION AND USAGE PARAMETERS (continued)

PATHWAY ADE 1.109 DEFAULT RSNGS Shoreline Rv;reation Adult 12 hr/yr 200 hr/yr Teen 67 hr/yr 100 hr/yr ,

Child 14 hr/yr 14 hr/yr Infant 0 hr/yr 0ht/yr Swimming Adult Nonc 100 hr/yr :

Teen None 100 hr/yr ,

Child Nonc 14 hr/yr Infant None 0 hr/yr Boating Adult None 0 hr/yr Teen None 0 hr/yr Child None 0 hr/yr Infant None 0 hr/yr -

Inhalation Adult 8000 m' 8000 m' ;

Teen 8000 m' 8000 m' Child 3700 m' 3700 m' Infant 1400 m' 1400 m' .

JERIGATION RATES AND FRAC 110N OF IRRIGATION 1.109 DEFAUI.T RSNGS trrigation Rate 2631/m'/ month 2631/m'/ month ;

Time field has been irrigated prior to crop of - 15 years 15 years interest Fraction of the year field is irrigated None None Fraction of animal water intake not obtained from None 0 the irrigation system -

(irrigated Meat) -

Fraction of animal water intake not obtained from None I the irrigation system (irrigated Milk)

Attachment 3

.Page 2 of 3 i

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MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP M 2 PROCEDURES MANUAL !

REVISION: 9. ;

TITLE: OFF. SITE DOSE CALCULATION MANUAL PAGE: 46 of 74 i F !

QQSE FACTOR PARAhiETERS (Continued) ,

a TRANSIT. TRANSFER. AND llOLDUP TIMES i

1.109 DEFAULT RSNGS [

j frrigated Stored Vegetables 11oldup Time 1440 hrs 1440 hrs ;

j lirigated Fresh Vegetables lloidup Time 24 hrs 24 hr ;

Irrigated Milk Holoup Time 48 hrs 48 hrs

Irrigated Meat iloidup Time 480 hrs 480 hrs

i

. Transit Time From Time Of Sample To Time Of None 72 hrs ,

Release Transit Time To Drinking Water None 0 hr

DILUTIONS 1100 DEEAULT RSNGS All Pathways Nonc 1 (None)

Shore Width Factor 0.2 0.2

MISCELLANEQUS 1.100 DEFAULT BSNGS .

Fraction Of Leafy Vegetables Grown in Garden 1.0 1.0 OfInterest Fraction Of Produce Ingested Grown in Garden 0.76 0.76 OfInterest

-_ Crop Growing Time For Leafy Vegetables 60 Days 30 Days Ingested By Man

- Crop Growing Time For Pasture Grass 30 Days 30 Days 2

Crop Yield For Leafy Vegetalles ingested By 2.0 kg/m 2.0 kg/m Man -

I 0.7 kg/m 2.0 kg/m' Crop Yield For Pasture Grass

]

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Attachment 3 i Page 3 of 3 I

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MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP 0002 PROCEDURES MANUAL REVISION: 9 TITLE: OFF SITE DOSE CALCULATION MANUAL PAGE: 47 of 74 -

ATMOSPl{ERIC DISPERSION AND DEPOjlTION PARAMETERS GASEOUS EFFLUENT PATHWAYS 1994 CONTROLLING LOCATIONS" PATilWAY DjRECTION DISTANCE XLQ' DLO' (sec/m') (m)

Inhalation ENE 1038 M 3.lE 06 --

Ground ENE 1038 M -- 4.8E 08 Vegetation SSW 670 M 1.4E 05 2.8E 08 Cow Milk ENE 1038 M 8.lE 06 4.8E 08 Meat Animal S 195 M 1.2E 04 -

Meat Animal SSE 198 M - 3.4E 07 Goat Milk SSW 2500 M 1.0E 06 1.7E 09 Site Bour.dary NNW 670 M 2.lE-05 --

for Gaseous Elliuents

Based on meteorological data from January 1978 to December 1987.

" Based on 1994 Land Use Census.

L Attachment 4 Page1ofI L

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1 MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE: OFF SITE DOSE CALCULATION MANUAL PAGE: 48 of 74 SITE.IlOUNDAIO'_EQILGASEOUS EEELUENIS

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MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE: OFF SITE DOSE CALCULATION MANUAL PAGE: 49 of 74 SITE fl0UNDARY FOR LIOUlp EFFLUENTS O

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I MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP 4)002 i

PROCEDURES MANUAL REVISION: 9 TITLE: OFF SITE DOSE CALCULATION MANUAL PAGE: 50 of 74 11[SJORICAL LIOUID SOURCE TERMS 1

Of Gamma Emitters Of All Nuclides Cl Relative Relative Relative Relative Nuclide (pCl/ml) % Fraction % Fraction ,

11 3 4.45 E 04 n/a n/a 100.00 1.00 Cs 137 1.23 E 08 100.00 1.00 2.76 E 05 2.76 E 05 TOTAL 4.45 E 04 100.00 1.00 100.00 1.00 i

1 Note Based on Retention Basin Elliuent IIistory of Rancho Seco from January 1,1993 through December 31,1994 l

4 1

l Attachment 7 Pageiof1

i !

MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP 0002 PROCEDURES MANUAL ;

REVISION: 9 i TITLE: OFF SITE DOSE CALCULATION MANUAL PAGE: 51 of 74 LIOUID MONITOR DETECTOR EFFICIENCIES t

R15017A & R15017W !

(Detector Model RD 53)

Elliciency Nuclide epm /pCl/cc MO 99 3.47 E+07 1131 1.90 E+08 l132 4.17 E+08 l133 1.53 E+08 l135 1.74 E+08 ,

CS 134 3.25 E+08 CS 137 1.28 E+08 ,

CR 51 1.85 E+07 MN 54 1.30 E+08 FE 59 1.26 E+08 CO.58 1.85 E+08 CO 60 2.40 E+08 ZN 65 6.49 E+07 SB 124 2.66 E+08 BA 140 _8.98 E+07 LA 140 2.69 E+08 CE141 ,

7.68 E+07 CE 144 1.80 E+07

From Calculation Z RDM 10261 Attachment 8 Page1of1

f MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP 0002 l

, PROCEDURES MANUAL !

REVISION: 9 !

TITLE: OFF SITE DOSE CALCULATION MANUAL PAGE: 52 of 74 s

i !

ORGAN DOSE FACTORS FOR L:OUID EFFLUENTS ?

i W L FA M A TAlettl Atil

Aal t

Units .te trem/ht per #1/ml mellee We it.esy t .r alttut "fr* 0. oSt eW"i.pe fiTJit T"jiTesi""T"gentJisodi""T@T

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C6.nl 8,095e00 3.ctleeg 0.09Be00 6.96te90 4.36te00 1 06teet 4 468,03 etM4 9.t3te02 1.364e0% 6.30$e64 0.23te02 9.90te04 0.f38*02 3.01B+04 j ees 66 0,008 00 2.135-04 3.968 06 0,00s.00 3.103 04 0,00t*00 6.798-03 ft.lb 1.198 04 0,19 teel 4.tlle03 1.298 04 1.198 64 4.bote03 4.69te03

ft49 1.47t*04 3,428*04 4.328804 1.17te02 1. tite 02 9.495e03 1.14t*0%

N 40 f.360e02 9.968e02 8.938 03 f.36te02 f.36te03 f.36te02 1.llte04 4 60 1.248e04 1.668*04 f.028e06 8.26te64 3.288e04 1.26te04 1.13B+04 N1 61 3.42840% '.37t*04 8.4%t804 0.00te09 9.008600 0.00te00 4.egte03 h! el 8.668-04 4.828 04 0138 0% 0.00te00 0.00te00 0.008e00 2.068 03 CV-64 0.904 01 5 028 04 3.1?t+01 9.908 02 1 64te60 9.908 02 $.244 08 d CN*66

614804 1.42te04 1.10te06 4.488e02 1.628*06 4.44te02 8.6fte06 4

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pt.e5 66 06 6.446*04 1.218e0% 6.625e04 6,46te00 6.468 00 6.468400 2.398*04 66 se 0.008800 3.00te00 0,00te00 ' O,00t*00 0.00te00 0.005e00 0.00te00 70-09 0.00geng 0.0ete00 0,005 00 0,008e00 0.00t*90 0.00te00 0.00t*00 36 09 2.Dit*06 4.218-02 n.?lle03 6.268 02 6.2l8 02 6.268 04 3.228*04

$4 90 L118e06 6.168 03 1.614e06 6.164-t,3 6.168-03 4.168-03 3.268*0%

) st-tl 0 665 00 1.468 01 3.408-01 1.438 04 4.198 01 1 198 06 f.624*04

$$ 02 $.964-03 0.00$e00 2.%88 04 8.00le00 0.000 00 0,00t*00 3.198 01 i Y 60 3.468eno 4.948-02 1.628 01 6.948 01 6.648-02 6.948 04 3.518e04 i Y elm 0.000e00 0.00$e00 0.00te00 0.00te00 0,00te00 0.00$e00 0.00$e00 V ti 4.64te02 6.828 01 6.998e00 6,028-01 6.628 01 6.8)t+0! t,014 06 Y #2 4.T18 05 4,248 06 4.628 06 4.f48 04 4.248-04 4.248 06 2.24t+04

. V 93 8.161 02 1.61t+02 1.638-02 1.618 02 1.618 03 1.688 02 1.135 0) 89 9% 1.428 92 1.645 02 1.62te02 4.6ste02 8.668+02 1.66te02 2.618e04 24-91 9.018 01 9.988 38 9.925-01 9.928-01 0.038-04 9.t28 04 3,24te02 ht ti n.165*32 3,2 ? t o72 2.l?t 02 t,628e01 3.248 02 p.tJte01 1.44te06 Mn99 1.2'Be00 !.04tec2 l.991 08 4.2?te00 4,41t*02 1 2'te00 1.034e02 TC 69M 9.218 04 . 038 03 4.548 03 1.18t+04 % 166-03 0.648 04 1.808 01

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NP 239 1.105*00 166tWJ 1,668*o0 5.ittWo 1.)tte00 1,%$5e00 2.926*0)

Attachment 9 Page1of4

4 MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP 0002 PROCEDURES MANUAL i

- REVISION: 9 TITLE: OFF SITE DOSE CALCULATION MANUAL PAGE: 53 of 74 7 QRGAN DOSE FACTORS FOR LIOUID EFFLUEN'[S (Continued) e tiost FACTok TABLE: A(!! - toen ;

Units are erem/h2 t.e# pCL/e1 1

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F 32 4.44te09 $ 1491,6 1.128e06 6.38t.02 6.318 02 6.318 02 3.73te06 e

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t.49 4.668*04 1.648604 1.404e04 1.00$*02 e 09te02 1.168e04 8.6)$+04

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. EN.6$ 0.00te00 0.00Le00 0.00te00 0.004e06 0.00te00 6.00te00 0.00te0"

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$4 90 1,40te06 6.168 03- 1 998e04 6,468 03 4,168 0) 4.168-03 3.968e06 statt 6.118e00 1,166 01 3.198 01 1.148 OL 1.14&.04 1.168 01 2.66tett 89 42 6.668 08 0.000epe 2.378-04 0.00t*00 0.308e00 0.004e00 4.428 04 Y.90 3.168e00 4.018 02 4.618-01 6.I'8 02 6.4't.02 6.918 02 2,98te04 V-TIM 0.00te00 0.008e00 9.00te00 0.006 00 0.008*00 0.006e00 0.008e00 Y.tl 2.44te02 1.108 01 4.918800 3.198-04 3.988-01 1.108 01 1.0lte0%

Y.92 8.644-06 4.208 04 4 llt 64 4.208 06 4.208 04 4.208 06 3.368 01 f*ti 2.438 02 1.674 02 1.698 0! 4.%18-02 8.l't.02 4.698 02 1.10t*02 Il-tl l.10te02 9.6tt+08 9.348*01 8,62 teel 3.038*02 4.628een 2.428e04 18*97 9.418 01 9.378 0' 9.314 01 9.968-01 9.388-01 9.368 01 2.638e02 NS-96 4.13te02 f.Ilt+02 1.168e02 4.46te01 2.?lte02 4.46te01 8.028e06 96* t t 6.364 01 4.828e02 S.Itte04 1.468 01 9.4?te02 4.368 01 1.738e02 i TC stM 6.644 04 8.ljt-e) 6.368 01 6.988-04 9.204 03 9.408 04 2.418 01 10 401 0.00$e00 0.00t*00 9.00$e00 0,00te00 0.000+00 9.00te00 0.00le00

W.103 6.948*02 3dit*01 2.916e02 3,llteel 1.98 teel 3.618*0) 4.64te04

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. 4 6 8,*

1 1 134 v.128*02 1.368 epa 1.33B+02 3.618e05 2.33te03 1.068e04 02 00 !

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$A 836 0.00te00 0.00te00 0.00Be00 0.00t*00 0.00t*00 4.00t*00 2.944-06

~

6 A 14 0 n.34 teel 1.648401 1.63te02 9.418 00 1.288+01 1.4ste04 4,233e03 BA 141 0.008*00 0.0nte00 0.00se00 0.004+^0 0.00te00 0.006 00 0.00se00 DA l42 0.004e00 0.00te00 0,ecte00 0.00t*20 0,00t*00 0.00te00 0.00te00 tk l4 8 h J0te00 2.0t&e00 1.44te00 n.HBen n.s$te00 1.065 00 1.218 04

'A.142 0.005600 9.00te00- 4.00te00 0.008603 0.00te00 0.30te00 2.jtt,0%

C8-141 1.ette01 1.30te01 6.06t*90 6.196*0J 4.848*00 %.1%4*00 .2.25Le04 04-148 - 1.195e00 4.40t*02 1.6tte00 latte00 1.efte00 1.19t 00 4.418 eel (5-144 1.20t+03 6.80$ eel 9.418e01 2.126*01 1 13te02 2.12te01 2.978 05 9 9 14 ) ~ T.964*S0 3 lete00 3 978 01 0.095e00 1.0%$e00 0.00Ee00 2.628e64 F 6 14 4 . 0,00te00 0.00$e00 0.008e00 0.00te00 0.005 00 0.005 00 0.00t+00 NDel47 1.925*00 8.l?te00 2.428e00 2.418,00 6.928*09 2.458e00 2.06te04 t W It1 ~ 2. lite 61 1.19te01 1.11t+00 1.268+00 1.268*00 1.26te00 4.llte03 Nt.219' l.10$e00 1.36te00 1 3t$e00 1.348 00 1. Hie 00 1.34te00 2.415e0)

Attachment 9 Page 2 of 4

MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP 0002 PROCEDURES MANUAL REVISION: 9 TITLE: OFF SITE DOSE CALCULATION MANUAL PAGE: 54 of 74 ORGAN DOSE FACTORS FOR LIOUID EFFLUENTS (Continued)

DOSE TAC'f0R TABl.El A(1) - Child Units ate prem/h per pC1/n1 r

& % G.. i.e 0.rd.%.ps, T.M. 2. .0..,rE!.!!.7,rM. 1. ..rd. 4.i 0.i,hrfM...Tr 0$

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ri...

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4. 93 .006 00 4.098 04 .. 1. .it. . . I 0.004 00 1 7 60 1.02...

4.7 t.002 9.4ti 03 1.248 01 9. 0..2.. 0 3 . 00

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00 8.23 0 1

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3 1.068 07 2.20 03 5.438... l 3.20$.03 f.70. 03 2.208. 3 1.248 02 Y..96 4.32 0i 2.111 01 1.11. 04 3.458 06 1.11. 01 4. 38 04 3.-91 f 1.40 01 4.12 01 2 1.11.c1. 1 8 315 01 1.338 01 i 3 18 01 1.901 02 0i N#.86 4.208 02 f.0 1.498 0.i .2S 1.94 . 2 .268 00 3.10 06 Wh 99 7...B.02 li.01 . 90i 00 02 .908 02 .0.2 VC.99M .4.34 905. 0402 1.64. 04 i.135. 1.40 0207 9.118 06 9. t .03 1.608. 034.338 04 3.1 8 01 t2 101 0.00 00 0.008 00 0.00 00 0.004 00 . 004 00 0.005 00 0.00t.00 RU .10 3 8. 28 03 4.928 00 3.965 02 3.518 03 4.928 00 f. 38 04 80+406 8.638 0% 4.923. 0. 1.133 02 2.135 06 . 368 41 RJ.80 4.3.ti..0403 f. 1 .

3.4 4,608. 04 3.9 .01 2. 2.63. 1 06 ! 4.298 04 2.0?t 01 4.948 0n AG.llDM 1.198 03 4.2 8.01 ) 1.04 1.4.. 02 2.225 03 1.4.. 02 1.324 0 ti.12tM 3.04. 04 0.M 03 4.0..8 03 03 .64. 03 . 135-02 938-02 2.948.4 6 75 127M 9.308 04 2.60 04 1.10. 04 2.22 04 2. 63 0% 4.108 03 1.638 04 18 121 . 648 61 2.41. 01 1.92.-01 . 195..! 2.$4. 00 2.208 06 3.46 01 ft.129M 1. 95 04 3.058 04 1.908 3,42. 04 1.211 0% 3.0.t.00 1.338 06 18 129 8 00 0.00 00 0.00 04 00 0.00 00 . 004 00 0.003 00 1.145 0.

ti.131M 0.00.5 l.4 036.135 01 02 1 06. 01 4.6 8 04 1.2 8 01 2.0.t.04 18 131 0.00 00 0. 5.4...0 00 0.00. 00 0.00t.00 0.008 00 ti.832 0. 00 00 3..It*03 4.8 8 03 1.2. 0.008.03 001.35. 04 4.308-04 3. 38 04 1 130 . .3168 03 4.#' 01 1.198 03 1 90 01 1.43. 01 .0 8 431 8 03 2.078 01 .1.4 62..

5 03 00 .t48 0n 3.408 03 1.618 00 1. 25 00 1 132 2.0. 8 00

2. ct-04 4. 2.205 04 2.228 02 1.325 04 0.003 00 %...l.02 1.0 4 04 - 9.668 01 1.4 5 41 15 04 1 133 . 4..lt.0% %..,745 4i.01 f.& 04 6,01 i 114 0.005 00 .061 00 0.008 00 0.ous 00 0.00 2.328. 00 08 1 43% -3.19. 04 6. 28 04 3.238 01 0.003. 000,095. 1.06 00 00 . 24 0% t.208 01 C ?..li.0% 1.2%8 0 2.645 0% .

2. 04.t .0201- 3. 18 0% t.ati.0% 7.028 03 C.8 *l). 134 4.448 04 4.14 06 1.37. 04 1.098 04 04 C4 137. 1.12. 0. l..'s.0. .l.698 06 4 26. 02

. 013 60. 06 p.063. 1.2. 06 03 4..lbt.03

01. 03 0.008 00 0.008 00 0.005 00 00. 00 .00 0.004 00 0.008 00

.CJ.ll. .,003 00 0.004 00 .00 00 0.00.6 0000D 00. 00 3.618 0%

.A.139 A.140 0.6 004 00. 968 0 6.068 02 .l.3. 3+00 3. % .00 6, 18 00 4.3 8 04 A.144 0. 4.v4 0300 0.00 00 0.008 00 . 005 00 0.008 00 0.006 00 0.00:e00 005 090.003 00 0.,.008 008 00 00 0,003 00 A.142 LA.14. 0.30 005 0L 00 .694 01 3.278 01 2,195 01 2 698-01

665 04 0.004.

6.66 0300 LA.142 0. 0.005 00 0.008 00 0.003 00 0.005 00 042 00 1.968 04

2. 0. 00 1.065 0L 2.1 5 00 1.21 0L 1.2 L t.01 1,2 38 04 C8 141.

Pt.14 3 - 4. 48 14t. 01 ~ 1.428 2.44.02 01 2,23. 01 2. 6.03.3 . 00 0n 2.238-01 2.0 8 03 48 144 2.398 03 .t.618 02 1.30. 02 2.678 00 4. lit *02 2.97 00 1.955 01 tk.143 1. lts.0 L - 3.338 00 - 1.618 04 0.008 00 1.808 00 0,005 00 1.208 04 PA.144 0.00 0.008 00 0.004 00 0.003 00 0.004 00 0.00. 00 MD+141 -7,3.t. 5 00 9 0.005.0L00 1.. 3.418-04 3.418 60 3.478..I 9.028 03 Wit? 2. 58 01.'1.165 . 041 01 00 7. lit.00 1.1?g.01 1.T?t.01 1,1?g.01 2,495 03 NP.239 4.001 04 . 2.038 04 1.998 06 1..t. 01 2.325 01 1.6 8 01 1.132. 3 i

I Attachment 9 Page 3 of 4.

h

. MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP-0002 !

PROCEDURES MANUAL REVISION: 9 ;

TITLE: OFF SITE DOSE CALCULATION MANUAL PAGE: 55 of 74 i i

N i i ORGAN DOSE FACTORS FOR LIOUID EFFLUENTS (Continued) i DOJE FACTOR TABLES Atti - Inf0nt ;

Units are miem/hr per WCI M i l'

(

"*'I88' ti- 3 6 9,,,,,,,,,,,y

.004*00

'h...

ytt,,,,,,,,,7pft,,,,,,lty blisect 8. l N e 01 e,,ti,,,,E. hpt ig,,,,,,,ynn01,,,,JA!fyi

.lel*01

01 4 446 1.448e04 ,

Calt- 4.00tect 1 248*0% 4.248e0% l.!44 06 4.24860% 1.24te0% 1.248*06 NA 24 1.16te02 1.16t+02 8.16te02 1 168e02 1.144 02 1.168+c2 1.168e02 0 32 9.00le06 6.290e64 3.498+04 0.00$e00 0.00le00 0.0(te06 1.22te04 00+44 0.00te00 0.006 00 1.028 0% %.let.01 4.128 01 9.938 01 2.29 teel 80e a lt 0.00te00 3.688e02 3.0!$+08 0.00$e00 3.13t+01 0.008e00 4.leteel '

see 66 0.004+00 8.828 04 0.000+00 0.00te00 1.068 06 0.00te00 4.llt.04 78 66 4.618e02 3.638*02 0.498e04 0.00te00 0.00te00 4.118e02 4.418e01

84 69 8.048e03 1.018 03 1.14B+02 0.008600 0.00t+00 6.lete0J 0.46t*02 Co 60 0.00Be00 1.048602 2.108602 0.008e00 0.00te00 0.00t+00 2.10t+02 C0-40 0.004800 3.018602 0.99te02 0.00t*00 0.00te00 0.00t+00 0.06te02 pl.63 1.128*06 1.06te64 4.958e03 0.00le00 0.00B+00 0.00te00 6.298*02 pl 4% 1.418 04 1.668 06 1.%68 04 0.008+00 0,00Be00 0.008400 1.2't 03 CU.64 0.00$+00 2.29te00 1.068+00 0.00$e00 B.t'te00 0.00$e00 4.100+08

$N.46 3.02te04 1.038 06 4.118e04 0.00te00 6,02 8 e 34 0.00$e00 0.14te04 i

f' $N.49 0.00$e00 0.00Be00 0.00Be00 0.00t+00 0.00se03 0.00te00 0.000e00

! 68 03 0.00te00 0.008400 4.168 06 0.008+00 0.008600 0.000+00 0.008e00 d 09 04 0.00te00 0.00le00 0.09te00 0.00t+00 0.00te00 0.00te00 0.0et+00

$9 0% - 0.00800 0.Bote04 0.00$e00 0.00tede 0.006600 4.Mtes) 0.Mte00 d 93 04 0.00te00 3.148 06 6.618e04 0 00te00 0.00se00 0. 00 t

00 0.00t+00 2.928 03 60 00 0.00te00 0.008e00 0.00t+00 0.00t*00 0,0c8600 0.08e00 g

06 09 0.008e00 0.006 00 0 001 00 0.005 00 0.00t+00 0.00t*00 0.00t*00

$6 49 6.176e04 0.00se00 1.66t*03 0 00te00 0. Hie 00 0.00te00 1.198e03 ft.90 3.91340% 0.00se00 1.0$ teen 0.00te00 0.008e00 0.398 00 1.228883 68 91 4.01te00 0.008800 1.464 01 0.00$e00 0.00te00 0 00t*00 4.ibl+00 ,

dt.92 1.048 04 0.008e00 4.938 04 0.00t+00 0. cote 00 0.008*00 1.948 03 f.00 4,668 03 0.00te00 1.228 04 0.00t+00 0.00te00 0.0cte00 6.20t+00 i

v.91M 0.00te00 0.00$e00 0.008+00 0.008 00 0.00t*00 0.008e00 0.008e00 t 91 3.328 01 0.000e00 4.688 03 0.008+00 0.00t*00 0.00te00 1.388*01 Y 92 0.005 00 0.008800 0.008600 0.00t+00 0.0cte00 0,v0t+00 3.388 04

V 03 3.0et.06 0.008+00 0.008+00 0.008600 0.00l+00- 0.0cte00 2.428-01 Ik 96 3.068 02 1.468 03 %.208 03 0.008e00 0.018 03 0.00te00 3.118e00 '

14 01 4.318 0% 1.408 06 3.308 06 0.00t+00 1.458 04 0,0c1 00 4.128 01 WS 9% 2. tite 00 1.168+00 6.108 01 0.00t*00 0.318 01 0.008e00 9.108+02 PD.99 0.00t+00 1.388*03 2.69te02 0.00t+00 2.06 teal 0.008 00 4,368 02 ,

TC 9fM l.618 04 1.868 01 4.494 02 0.008+00 1.215 02 4.0t$.04 1.368 01 1'. 108 0,00te00 0.00te00 0.008+00 0.00se00 0.003e00 0,00te00 0.008600 AU.lti 4.005 02 0,008800 1.318 02 0.008*00 0.608 02 0.031*00 4.915 01 kU 10% 0.008s00 0.' teJO D,00te00 0+00t*00 1.628 04 0.008,00 0.268 4%

0.0vt600 1.068 04 0.00te00 0.745 01 0,0cte00 s,3 ele 00 ;

l 0U 194 0.408 01

A)*ll0M 1.814403 1.328 eel 3.144e02 0.00t*00 3.698 03 0.0ct+00 e.064e04 ft*12%M 0.408*02 2.838 02 1.155e02 2.068e02 0.00te00 0.008 00 4.048*02

, 18 12'M 2.428 03 0.695e02 3.118e02 1.618e02 6.46te01 0.0ete00 1.0ste03 784121 9.618 02 3.228 02 2,0ft.02 1.828 06 2 348 81 0.00500 2.021e00 ft.129M 3,0$8+03 1.0ite3) 4.108 02 1.l'te0J 1.638*03 0.00t+00 n.428e03 18 129 0.00te00 0.00Ee00 0.00te00 0.00$*00 0.00$+00 0.00t+00 0.00t*00 ft.131N 2.0't+01 1,468*04 9.655600 2. 3 4 t o t 1.06 teel 0.09te00 1,948e02 Thl31 0.00t*00 0.00t+00 0.00te00 0.0at*00 0.00t+00 0.008 00 0.008 00 2 f t.142 1.414+02 4.90te01 6.618 eel 1.038*02 4.361 02 0.00te00 2.60Be02 1 140 8.9Jte00 1.948*01 1,00te00 2.20t*03 2 16te01 0.00te00 4.218e00 3 131 3.018+03 1.4tt*03 8.S98+03 1.198+0a 4 22te03 0.0c8 00 8.298 02

!*I32 1 304 06 2 648 06 9.418 06 l.248 03 2 958 06 0.00E*oo J.848 0%

l.133 6.998s01 3.028 02 2.908601 1 0$te04 1.20te02 0.00t+00 1.12L+0i I.134 0.00te08 6.00le00 0.008+00 4. 1*00 0.00t+00 0.00t+00 0.00t+0B t

l.136 4.238 01 0.418 01 1.4't-04 1.648*01 9.30s.01 6. cote 00 3.048 01 C3 134 1,titeel 2.etteJ5 8.928e04 0.00le 00 .1.4 3 8 *04 J 048*04 5.945e02 Ca.136 4.0%8e04 3.088+04 1.168e04 0.00t+00 8 23te04 2.565+03 4.61t+02 C3.ll? 2.32t+04 2.16t*06 1.928*04 0.00t*00 1.21t+04 4.tst+04 0.45te0J CS*130 0.00te00 0 008e00 0.00t*00 0.00t*00 0.00te00 0.00te00 0.008e06 FA 139 0.00te00 0.00t+00 0.005e00 0.005 00 0.00t+00 0.vate00 0,008600 SA 140 1.26te33 1.208+Je 6.618e01 0.00te00 3.018 01 '4848 01 1.158e42 DA 14. 0.00ao06' O.008eJO 0.00t*40 0.004 00 0.005 00 3.004 00 0,003 00 SA.142 0.00t*00 0.005.J0 0.008*00 0.005 00 0.00te00 4.oSt*90 0.005e00 tkl40 3.018.c4 1.208 34 3.095 0) - 0.00tene 0,008 00 0.0et+00 1,418 00 1.A.842 0,008e00 0.00EeJe 0. 0 0 E e 00- 0.00te00 0.2 05 G0 0.0;tt00 0.208:00

'Ch.444 - 2.011 04' l.868 01 1.498 02 0.005 00 3.048 0.' omten 6.62 t*0 t = ,

Ct.143 3.208 01 2.12te00 2.42E.04 0.00te00 0. l e r.04 0.098000 1.245 01 Ct.444 9.028 00 4.028 00 n.60s.01 0.001 00 1.#28 00 0.003 00 %.438802 -

Pl.14 8 ' 9.064 03 P.948 03 3,905 04 0.006 00' 4.098 03 0.003 00 4.358*00 ft.144 - 0.00$+00 0.00t*00 .0,00B+00 0.00s.00 0, ste00 0.008 00 0.00t*00 ND.147 4.918-0s 4,%45 03 3,028 04. 0.00$e00 1.008 03 0.0o5 04 3.138*00

- tbl01 %.6!8.J1 3.448 01 1 338.01 0.00t*00 0.00te00 0.008 00 2.2*tett Nf*236 2.118 04 2.248 06 1,218 0% - 0.00te00 4.418 0% 0,005 00 6.408 01

- Attachment 9 - '

Page 4 of 4 a

---.,--r-g y p- e y -++ vv y g. -4.---yg e.-%-yw#--s-.mg3g.- - .-e-+, y - a.y-3:n-,:-yy-- r +. -u-e--. - --- --.- -

MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE: OFF. SITE DOSE CALCULATION MANUAL PAGE: 56 of 74 OASEOUS hiONITOR DETECTOR EFFICIENCIES Rl5044, R15045, and R15546A (Detector hiodel RD 52)

Efficiency

Nuclide epm /pCl/cc KR 83h1 0.0 KR 85h1 7.30 E407 KR 85 7.19 E+07 KR 87 8.70 E+07 KR.88 8.70 E+07 KR.89 8.70 E+07 KR.90 8.70 E+07 XE.13 thi 0.0 XE.133ht 0.0 XE 133 2.94 E+07 XE 135ht 0.0 XE 135 7.75 E+07 XE 137 8.70 E407 XE 138 8.70 E+07 AR-41 7-80 E+07

From Calculation Z RDht 10261 Attachment to Page1ofI

MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP-0002 i PROCEDURES MANUAL REVISION: 9 {

TITLE: OFF SITE DOSE CALCULATION MANUAL PAGF: 57 of 74 ;

DOSE FACTORS FOR N_OBLE GASES AND DAUGIITERS i

?

FACTORS FOR EXPOSURE TO A SEMI-INFINITE CLOUD

or NOBLE GASES Dose to Peoplet Dose to Airt Gamma-Body Beta-Skin Ganma Beta i Nuclide K(i) L(1) M(1) N(i)

AR-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 i KR-83M 7.56E-02 0.00E+00 1.93E+01 2.88E+02 KR-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 KR-85M 1.17t+03 1.46E+03 1.23E+03 1.97E+03 KR-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 KR-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 KR-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 KR-90 1.56E+04 7.29E+03 1.63E+04 7.03E+03 XE-131M 9.15E+01 4.76E+02 1.56E+02 1.11E+03 XE-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 XE-133M 2.51E+02 9.94E+02 3.27E+02 1.48E+03 XE-135 1.01E+03 1.06E+03 1.92E+03 2.46E+03 XE-135M 3.12E+03 7.11E+02 3.36E+03 7.39E+02

-XE-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 XE-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 t -- mrem /yr per pCi/m'

-- mrad /yr per pC1/m'

- Attachment 11 Page1of1-

MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP 0002 PROCEDURES MANUAL REVISION: 9 TITLE: OFF+ SITE DOSE CALCULATION MANUAL PAGE: 58 of 74 ORGAN DOSE FACTORS FOR GASEOUS EFFLUENTS DOSE FACTOR TABLE: R(1) - Adult, inhalation Units are mrom/yr per pCi/m' Nuclide Sche Liver 71My Thytold M1dhey Lung Gitteet H.3 0.ovlevu 1.toteu) 1.26L+03 1. 2 61. c o ) 1.260*03 1.26L*0) 1 2tE+v)

Ch*ll 0.00E+00 0.00t*00 1.00t*02 6.960+01 2.20t*01 te44t+04 3.32t*03 HH+54 0.000*00 3.96t+04 6.30E+03 0.000400 9.04t*03 1.40t*06 1.14t+04 FE.55 2.46E+04 1.10t*04 3.9tte03 0.00E*00 0.00t*00 7.21E*04 6.03t+03 l'E*69 1.19t*04 2.19E+04 1.06te04 0.000+00 0.00E*00 1.02E+06 1.69t*06 Co*te 0.00t*00 1.68t*03 2.01E*03 0.00t+00 0.00t*00 9.20E*06 1.06t+0L Co 60 3.00Et00 1.ltt*04 1.40t*04 0.000+00 0.00t*00 6.97t+06 2.61t*C$

EN 6S 3.*4t*04 1.0Jt+0$ 4.66t+04 0.00t+00 6.900*04 e.64E+06 S.3tE*04 2R=84 3.04E+0L 0.00t*00 9.120$03 0.00t*00 0.00E*00 1.4GL*06 3.t0E+0$

SR*90 9.92[+07 0.000*uo 6.10t*06 0.00t+00 0.00t+00 9.600+06 1.22E*05 ER 96 1.070405 3.44E+04 2.330+04 0.00t*00 5.42t+04 1.17E*06 1.60E*05 1-131 2.b2E+04 3.59E*04 2.0tt+04 1.19t+07 6,13E+04 0.00t+00 6.29E+03 1-133 8.64E*03 1.48I*04 4.62E+03 2.1LE*06 2.59t*04 0 00t+00 9.6et*03 C#+134 3.130*05 9.460+0% 7.26t*05 0.00t*00 2.87E*0b 9.76t*04 1.04L+04 C3 136 3.91L*04 1.46t+0S 1 10t+0$ 0.000+00 0.b6t+04 1.20t+04 1.11E*04 C3 137 4.19t+0S 6.21t*05 4 20te06 0.00t+00 2.23Ee06 1.52E*04 6.400+03 RA 140 3.91E+04 4.91t*01 2. bit *03 0.00E+00 1.67t+01 1.27t+06 2.16t*06 CE 141 1 990404 1.3tt+04 1.63t+03 0.000*00 6.27E*03 3.62E*0$ 1.20E*06 CE-144 3.430+06 1.43t*06 1.e4t+06 0.00E+00 9.40E+06 1.10E+06 U.16E*06 DOSE FACTOR TABLE: R(1) - Teen, inhalation, Units are mrom/yr per pCi/m' N ellde Bone Liver Tbody Thyroid Kadney Lung 01 tract iia J 0.vvE+vu 1.4fL.u) 1.21L*03 1.s1L*0J 1 2't*0J I 1 41L+4J 1.s?L+v)

CR.$1 0.00E+00 0.00Ee00 1. 35t + 02 7.bOE*01 3.07E*01 2.10E*04 3.00E*03 MN.14 0.00E*00 6.11E*04 6.40E+03 0.00E*00 1.2?t*04 1. 99t e 06 6.6eE+04 FE 55 3.350404 2.39E*04 5.h5E*03 0.000e00 0.00E*00 1.24Ee05 6.39E*03 FE*5 9 - 1 69E*04 3.10t+04 1.43t*04 0.00L*00 0.00L*00 1. 5 )t + 06 1.1tE*05 CO-50 0.00E+00 2 01E*03 2. 7 BE* 03 ' O.00E+00 0.00E+00 1.34t*06 9.620*04 CO.60 0.00E*00 1.510*04 1.98E+04 0.00E+00 0.00E+00 0.12E+06 2.59E*05 CN,66 3.86E*04 1.34E*05 6.24E+04 0.00t+00 9.64t*04 1.24t*06 4.67t*04 BR*99 4.3SE*06 0.00E*00 1.200+04 0.00E*00 0.00E*00 2.42E*06 3.11E*05 SR-90 1.ctt+08 0.00E*00 e.6aEe06 0.00t*00 .0.00E+00 1.6SE*01 7.6tt+0h th 96 1.4ttt0S 4.59L+Q4 3.150604- 0.000e00 6.14t*04 2.69E'06 1.49E+05 1 131 3.htt+04 4.91E*04 2.64E*04 1.46E*01 6.40t*04 0.00E*00 6.4 9f

03 1+133 1.22E*04 2.0$E*04 6.23E*03 2.'s20+06 3.5)E+04 v.00t*00 1.c3E*94 Ca*144 'S.03t+0S 3.13E406 5,49E+0S 0.00t+00 3.75E*0$ 1.460*06 1.16t*03 C3-136 S.150+04 1.94E*05 1.37E*06 0.00Ee00 1.10E+05 1.100+04 1.09E+04 CS*131 6.11E+05 9.4BE*06 3.11E+05 0.00E+00 3.04t*05 1.21E*05 6.48E+03 BA-140 S.41E+04- 6.11E*01 3.$2E+03 0,00E+00 2.28t+01 2,03E*06 2.29E*06 CE-141 2.84E*04 1.90E+04 2.11E+0 0.00E+00 8.89t+03 6.14E+0$ 1.26t*05 CE+144 4.89E+06 2.02L+06- 2.63Ee05 0.00E+00 1.21t+06 1.34E*01 9.64t*0$

Attachment 12 Page 1 of 2

n

_ _ _ . _ _ . _ _ _ .._ a

I i

i MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP 0002 ,

PROCEDURES MANUAL i REVISION: 9 !

TITLE: OFF SITE DOSE CALCULATION MANUAL PAGE: 59 of 74 i

ORGAN DOSE FACTORS FOR GASEOUS EFFLUENTS (Continued)

DOSE FACTOR TABLE: R(i) - Child, inhalation I Units are mrem /yr por UCi/m' !

t Nuclide lune Elver Tbody thyroid Midney Eung 'Jitteet i

. g. .g.g. ..g.g g .) j.

.g 7 7g.y.... . ..g.. .

.g.., g. -

CR.61 0.00E*00 0.00E+00 1.540*02 8.bbC+01 2.43E+01 1.1EE*04 1.00t+03 MNeld 0.00E+00 4.29E*04 9.61E*0) 0.00E+00 1.00E*04 1.69E+06 2.29E*04 FE.66 4.74t*04 2.52E+04 7.11E+03 0.00E+00 0.00E+00 1.11E*0$ 2.97E*0) fE*69 2.01E*04 3.36t*04 1.67E*04 0.00E*00 0. 00E

00 1.27E*06 1.07t+04 ,

Co-$9 0 00E+00 1 17E*D3 3.16t*03 0.00E*00 0.00E+00 1 11E*06 3.44t*04 -

-Co-60 0.00E+00 1.31E+04 2.27E*04 0.00E*00 0. 00E + 00 7.010406 9.620*04 5 EN+66 4.26E+04 1.13E*06 1.04E*04 0.000+00 7.14t*04 9.96t*05 1.63E*04 l i $R-89 6.00E*06 0.00E+00 1.12E*04 0.00E+00 0.0CE+00 2.16Ee06 1.67t+06 '

l SR 90 1.01E*00 0.00E*00 6.44E+06 0.000+00 0.00E+00 1.4eE+07 3.44E+0t .

ER-96 1.90E+05 4.160+04 3.10E*04 0.00E+00 6.96E*04 2.23E*06 6.11t*04 1-131 4.01E+04 4.81E*04 2.13E+04 1.63E*07 7.etE*04 0.00E+00 2.84t+03 /

l 133 1.66t+04 2.03E*04 7.10E*03 3.8EE+06 ).3tE+04 0.00E+00 5.46Ee03

. CD 134 6.51E*06 1.01E*06 2.2LE*05 0.00E*00 3.31E*06 1.21E+05 3.ME*03 ,

CS 136 6.61t+04 1 11t*05 1.16E*06 0.00E+00 9.55E*04 1.15E 04 4. lee *03 i

C5-1.4 7 9.07E+0L 6.26t+0h 1.280+06 0.00t+00 2.020*05 1.04E.05 3.62E+03 BA+140 7.40E*04 6.48t*01 4.33E*03 0.00E+00 2.11E+01 1.74E+06 1.02E*06 CE.141 3.92E+04 1.9$E+04 2.90E*03 0.00E+00 8.htE*03 6.44E*05 5.66E+04 CE 144 6.71E406 2.12E+06 3.62E+06 0.00E+00 1,170+06 1.2DE+01 3.89E*06 DODE FACTOR TABLE: R(1) - Infant, inhalation

Units are mrem /yr per pCi/m# .

+

) ,

"Ji t t a ct t Nuclide Done Elver Tisody Thyroid Kidney 1,ung

.). ...

y g. . . . . . . . .. .... g. .;.y. 7.g . ;.. j

..g.

CR 51 0.00E*00 0.00E*00 0.95E*01 S.76E*01 1.J2E+01 1.200+04 3,57E+0; I

MN $4 0.00E+00 2.64E+04 4.99E*03 0.00E+0D 4. 9 9E

03 1.00E*06 ?.06t+03 EE- b 5 1.97E*04 1.190+04 3.33E*03 0.00E*00 0.00E*00 8.10E*04 1.10E*03

. EE 59 . 36t+04 2.3%E*04 9.40E*03 0.00E*00 0.00E*00 1.02E+06 2.4tE*04 C0-58 0.00E+00 1.22E+03 1.82E+03 0.00E*00 0.0cE*00 7.11E*05 1.11E+04 C0-60 0.00E*00 0.03E+03 1.16E+04 0.000 00 0.0'E*00 4.51E*06 3.19E + 04 l EN 65 1.93E+04 6.26t+04 3.11E*04 0.00L*00 3,25E+04 6.47E*05 L.14t+04 BR-99 3. 99E

06 0.00E+00 1.14E*04 0.00E*00 0.00E+00 2.03E+06 6.40E*04 SR*90 4. 09E

07 0.00E+00 2.b9E*06 0.00E*00 0.00E*00 1.120*07 1.31E+0b >

ER-95 1.15E+0S 2.79E+04- 2.03E*04 0.00E*00 3.11E*04 1 7tE+06 2.17t+04 1+131- 3.90E*04 4.44E+0e 1.96E+04 1.4pt*01 S lee +04 0.00E+00 1.06t+03 '

1-133 1.32E*04 1.92E+04- 6.60E*01 3.56E+06 2.24E*04 0.00E+00 .it:E+03 CS 134 3.96E+06 1.03E+05 7.4vt*04 0.000 00 1.90E*06 7.97E+04 1.33E+03

-CS 136 4.63E*04 1.3hE+0S -6.29E+04 0.00E+00 h.64E+04 1.18E+04 1.43E*03 i CS-137' 6.490+0L 6.120+05 . 4.5bt+ 04 ; 0.00E* 00 1.12E+05 7.13E*04 1.3JE+03 RA+140 S.60E+04 .b.60E*01 2.90E*03 0.00E+00 1 34[*01 1.60E*06 3.84E+04 CE 141 2.77E*04 1.67E*04 1.99E*03 0.00E+00 5.25t+03 6.17Ee05 2.160 04 ,

CE 144- 1.19E*06 1.21E*06 1.76E*05 0.00E'00 5.38E*05 9.65E*06 1.40E*05 ,

Attachment 12 Prge 2 of 2 :

r y

~

[

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

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

1 4

MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP-0002 !

! PROCEDURES MANUAL i REVISION: 9 ,

TITLE: OFF. SITE DOSE CALCULATION MANUAL PAGE: 60 of 74 RADIOACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION ,

9

Minimum ,

Number of Channels instrurnent Operable Action

1. Gross Radioactivity Monitors

Prmiding Automatic Termination ofRelease Retention Basin Emuent Discharge i

Monitor (RIS017A) 1 With the monitor inoperable, emuent relcars may le resumed provided that prior to initiating a sclease from the retention basin

1) At least tuo independent samples are analyred in accordance with Step 6.14.2.-

l 2) At least two technically qualified members of the 4 Facility Staffindependently verify the release rate calculations and discharge line valving.

i Otherwise, suspend release of radioactive emuents via 3

the pathway, Exert best efforts to return the monitor to OPERABLE status within 30 days and. if unsuccessful, explain in the next Annual Radioactive Emuent Rticase 4 Report w hy the inoperable monitor was not restored in a timely manner.

2, Flow Measurement Devices Waste Water Flow Rate and With the flow measurement desice inoperable, emuent Totalizer (FIRQ93108) I reicases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during

! retention basin releases by a level desicc in the discharge stream.

1 Retention Basin Discharge Flow With the flow rate measurement device inoperable -

Rate (F19$001) I cmuent releases via this pathway may continue provided that the Retention Basin discharge flow rate is estimated

- using the Waste Water Flow Rate instrument.

' s Attachment D Page1of1

~ MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE: OFF-SITE DOSE CALCULATION MANUAL PAGE: 61 of 74 BAD 10 ACTIVE LLQlllD_Eff1J)ENT h!ONITOIUNG INSTRUhtENTATION SURVEll. LANCE BEOUIREhtENTS Instmment Instrument Channel Source Channel luilulmtat fjicsk Check Calibration Channellest

1. Gross Radioactivity hionitors Providing Alarm and AMomatic Termination Isolation Retention liasin Efiluent D" ' P R"' Q"'

Discharge Afonitor(R15017A)

2. Flow hionitors Waste Water Flow Rate and Totalizer (FIRQ95108) D"' N/A R Q Retention liasin Discharge Flow Rate (F195001) D"' N/A R Q Mle. Notation m During releases via this pathway, a check shall be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Normally, checks are automatically performed once every eight (8) hours.

(2) The instrument Channel Calibration for radioactivity measurcment instrumentation shall be performed using one or more reference standards.

(3) The Channel Test shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exist:

A. Instmmentation indicates measured levels above the alarm / trip setpoint.

fl. Circuit failure.

C. Instmment indicates a downscale failure.

D. Instrument controls not set in operate mode.

(4) The instrument Channel Check shall consist of verifying indication of flow during periods of release. The Instrument Channel Check shall be made at least once daily on any day in which batch releases are made.

Attachment 14 Page1ofI

~

MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE: OFF SITE DOSE CALCULATION MANUr PAGE: 62 of 74 RADJ0 ACTIVE LIOUID WASTE SAMPLING AND ANALYSIS PROGB2M Lower Limit of Liquid Release Sampling Minimum Analyiis Detection (LLD)"'

Type Frequency Frequency Type of Activity (pCi/ml) _

A. Retention Eau n wh Each Datch Mn 54, Co 60, Zn 65, 13asin (N/S) Cs 134, Cs 137, Ce 144 3.00 E-07 l- P l{3 1.00 E 05 B, Regenerant Each Batch Each Batch Mn 54, Co 60 4.00 E 00 lloldup Tar.k P P Zn 65 6.00 E 09 (A/B)" d' Cs 134, Cs 137 3.00 E 09 Standard Ce 144 6.00 E 08 Release 11 3 1.00F 05 Scenario

Each 13atch Composite'" Sr-90 1.00 E 09 P M Gross Alpha 1.00 E 07 C. Regenerant Each Batch Each Batch Mn 54, Co 60, Zn 65, lloldup Tank Cs 134, Cs-137 2.00 E 08 (A/II)" d' P P Cc 144 6.00 E-08 Rapid 11 3 1h3 E-05 l

Release _Each Hatch Composite'" Mn 54, Co 60 4.00 E 09 Scenario

P M Zn 65 6.00 E-09 Cs 134 Cs 137 3.00 E 09 Sr90 1.00 E-09 Grcss Alpha 1.00 E 07 Attachment 15 Page1of4-

MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP-0002 '

PROCEDURES MANUAL REVISION: 9 (

TITLE: OFF-SITE DOSE CALCULATION MANUAL PAGE: 63 of 74 l BADJOACTIVE LIOUJD WASTE SAMPLING AND ANALYSIS PROGRAM (Continued) )

Igble Notation (a) 1. The Lower Limits of Detection (1,LDs) for the radionuclides presented in this table are the smallest concentrations (expre . ed in rnicrocuries per milliliter) which are required to be detected, if present, in order tr .:hieve compliance with the limits of Step 6.14.3 (10 CFR 50, Appendix !) for a RHUT transfer to a retention basin and assurance of compliance with the limits of Step 6.14.2 (10 CFR 20, Appendix B, Table 2, Column 2) for a Retention Basin Discharge.

2. The LLD of a radioanalysis system is that value which will indicate the presence or absence of radioactivity in a sample when the probability of a false positive and of a false negative determination is stated. The probabilities of the false positive and false negative are tsken as equal at 0.05. The general equation for estimating the mat 'um LLD in microcuries per milliliter is given by the following:

2.7 + 3.29 x S b LLD = 5 (3.70 E + 04)(Y x E x V)e(4'd Where:

2.71 = factor to account for Poisson statistics at very low background count rntns 3,29 =

two times the constant used to establish the one sided 0.95 confidt nee interval 3.70 E+04 = disintegrations /second/microcuric Y = yield of radiochemical process, i.e., the product of all factors such as emission fraction, chemical yield, etc.

E = counting efficiency (count / disintegrations)

V = sample volume (milliliters)

A = the radioactive decay constant for the partice!ar nuclide (seconds)

te

= the elapsed time from midpoint of collecuon to the midpoint of counting Attachment 15 Page 2 of 4

MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE: OFF-SITE DOSE CALCULATION MANUAL PAGE: 64 of 74 i RADIOACTIVE LIOUID WASTE SAMPLING AND ANALYSIS PROGaAM (Continued)

Table Notation (Continued) l S6

= the itandard c eviation of the background counting rate r 3 0..i B B

=

S.

st tbs +h t Where:

B= background counts t6 = background counting interval (seconds)

t. = sample counting interval (seconds)

3. The LLD is defmed as an a priori (before the fact) estimate and is not to be calculated for each sample analyzed on an a posteriori (afler the fact) basis.

(b) A batch release is the discharge ofliquid wastes of discrete volume from the north or south Retention Basin. The Retention Basins are the maximum permissible concentration accountability points for 10 CFR 20, Appendix B compliance.

(c) A RHUT will be isciated and its contents thoroughly mixed to assure representative sampling prior to transfening the contents to a Retention Basin. The A and B RHUTs are the dose equivalent accountability points for 10 CFR 50, Appendix I compliance.

(d) Isotopic peaks which are measurable and identifiable from a RHUT sample analysis shall be reported and included in ODCM evaluations. Nuclides which are not observed in the analysis shall be reported as "less than" the nuclide's a posteriori mininium detectable concentration and shall not be reported as being present. The "less than" results shall be considered "zero" for the purposes of ODCM evaluations; hc, wever, if a nuclide is measured and identified at a value less than the Attachment 15 LLD value, it shall be reported and entered in ODCM evaluations.

(e) A composite sample shall be obtained by reing liquid aliquot volumes in proportion to the volume ofliquid released from each RHUT. Preparation of the composite is identical no matter which release scenario, or combination of scenarios, was used to release the RHUTs. If any RHUT which is part of the composite was released using the Rapid Release Scenario, the composite will be analyzed accordmg to the Rapid Release Scenario.

Attachment 15 Page 3 of 4

/

MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP-0002 PROCEDURES MANUAL REVISION: 9

_ TITLE: OFF-SITE DOSE CALCULATION MANUAL PAGE: 65 of 74 BB)JOACTIVE LIOUID WASTE SAMPLING AND ANALYSIS PROGRAM (Continued)

Table Notation (Continmd)

(f) Release of each Ri'UT may proceed along either of two separate scenarios depending on operational requirements. Normally, the Standard Release Scenario will be used for RilUT releases. The Rapid Release Scenario will be used when operational requirements dictate expediting the release process. In either scenario, the sr.mple must eventually be analyzed to an LLD level which equates to an off-site dose ofless tha; 10 percent of the 10 CFR 50, Appendix I guidelir.es. Preparation of the Monthly Composite is independent of the scenario used to release each RiiUT during a calendar month: the composite must be prepared for either scenario, only the analysis requirements differ. These Lower Limits of Detection for either or both scenario may change as the maximum annual eflluent outflow or the minimum annual average flow rate in the plani efiluent stream changes.

1. Slanditrd Release Scenario. This scenario uses the lower LLDs on a pre-release basis, resulting in correspondingly longer analysis intervals. In this scenario, the monthly composite does not need to be analyzed for gamma emitters. The pre-release and post-release (monthly composite)

LLDs equate to an off site dose ofless than 10 percent of the 10 CFR 50, Appendix I guidelines.

2. Rapid Release Scenario. This scenario allows the use of higher LLDs for pre-release dose calculations, resulting in correspondingly shorter analysis intervals. The pre-release LLDs equate to an off-site dose ofless than 20 percent of the 10 CFR 50, Appendix I guidelines. The post-release (monthly composite) LLDs equate to an otT site dose ofless than 10 percent of the 10 CFR 50, Appendix I guidelines 11-3 and Ce 144 analyses are specifically required only on a pre release basis. The LLDs for 11-3 and Ce-144 are required for the pre-release analysis only, however, these LLDs were included in the determination of post-release LLDs which meet the 10 percent criteria.

Attachment 15 ;

Page 4 of 4

t i MANUAL: CHIMISTRY ADMINISTRATIVE NUMBER: CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE! OFF. SITE DOSE CALCULATION MANUAL PAGE: 66 of 74 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Minimum 3 Number of Channels 4

Instrument Opnahic AttiDB

1. _ Reactor Building Stack

a. Noble Gas Activity 1 With the monitor channel alarm / trip setpoint less i

Monitor providing conservative than the setpoint ca ,:ulated as -

alarm and automatic described in Step 6.6, immediately suspend the termination of release. release or declare the channel ino,;erable.

With the monitor inoperable, ellluent releases via this pathway may continue provided grab samples are taken at least daily and these samples are analyzed in accordance with Attachment 18.

Increase grab sample frequency as necessary during unusual plant conditions.

~

b. - Particulate Sampler 1 With the collection device inoperable, efiluent releases via this pathway may continue provided continuous samples are taken within I hour after the monitor is declared inoperable and these samples are analyzed in accordance with Attachment 18*.

c. Sampler Flow Rate 1 With the flow rate device inoperable, ellluent Measurement Device releases via this pathway may continue provided the flow rate is estimated and recorded daily.

Interruption of continuous sampling is allowed for periods not to exceed I hour.

4 s . -

Attachment 16 Page1of3 I

1

MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE: OFF-SITE DOSE CALCULATION MANUAL PAGE: 67 of 74 RADIOACTIVE GASEOUS EFFLUENT htONITORING INSTRUhfENIATION 4

(Continued) i hiinimum Number of

Channels lastrument Operable Aclion

. 2. Auxiliary Building Stack

a. Noble Gas Activity 1 With the monitor alarm / trip setpoint less

, hionitor conservative than the setpoint calculated as described in Step 6.6, immediately suspend the release or declare the Qannel inoperable.

With the monitor inoperable, ellluent releases via l this pathway may continue provided grab samples are taken at least daily (every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during fuel handling activities) and these samples are analyzed in accordance with Attachment 18. Increase grab sample Requency as necessary during unusual plant conditions.

b. Particulate Samp!cr 1 With the collection device inoperable, ellluent

. releases via this pathway may continue provided

continuous samples are taken within I hour after the monitor is declared inoperable and these samples are analyzed in accordance with

. Attachment 18'

c. Sampler Flow Rate 1 With the flow rate device inoperable, efiluent hicasurement Device releases via this pathway may continue provided the flow rate is estimated and recorded daily.

Interruption of continuous sampling is allowed for periods not to exceed I hour.

Attachment 16 Page 2 of 3

MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE: OFF-SITE DOSE CALCULATION MANUAL PAGE: 68 of 74 ,

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION .

(Continued)

Minimum Number of Channels lastrument Operable Action

3. Auxiliary Building Grade Level Vent 4

a. Noble Gas Activity 1 With the monitor alarm / trip setpoint less Monitor conservative than the setpoint calculated as

. described in Step 6.6, immediately suspend the release or declare the channel inoperable.

With the monitor inoperable, effluent releases via this pathway may continue provided grab samples are taken at least daily and these samples are l

_ analyzed in accordance with Attachment 18.

Increase grab sample frequency as necessary during unusual plant conditions.

b. ' Particulate Sampler 1 With the collection device inoperable, elliuent releases via this pathway may continue provided l continuous samples are taken within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months aller the monitor is declared inoperable and these l

samples are analyzed in accordance with Attachment 18'

c. Sampler Flow Rate 1 With the flow rate device inoperable, effluent Measurement Device releases via this pathway may continue provided the flow rate is estimated and recorded daily.

4. .lOS Building Vent l

a. Particulate Monitor 1 With the monitor inoperable, ventilation flow shall be halted or continuous particulate samples shall be taken in accordance with Attachment 18, Section D, for particulate samples.

1 i

Interruption of continuous sampling is allowed for periods not to exceed I hour.

Attachment 16 -

Page 3 of 3 -

(

- MANUAL: CHEMISTRY ADMINISTRATIVE- NUMBER: CAP-0002 i

PROCEDURES MANUAL REVISION: 9 TITLE: OFF-SITE DOSE CALCULATION MANUAL PAGE: 69 of 74 l EADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REOUIREMENTS

Instrument Instrument

Channel Source Channel Channel l Instrument Check Check Calibration Test

1. Reactor Building Stack

a. Noble Gas Activity Monitor D M"' R) Q'"

b. Particulate Sampler W NA NA NA D NA R Q

c. Sampler Monitor Flow Rate Measurement Device

2. Auxiliary Building Stack D M R"' Q

< a. Noble Gas Activity Mor.itor l

b. Particulate Sampler W NA NA NA D NA R Q

c. Sampler Monitor Flow Rate Measurement Device

3. Auxiliary Building Grade Level Vent

a. Noble Gas Activity Mcnitor D M R* Q*

b. Particulate Sampler W NA NA NA D NA R Q

c. Sampler Monitor Flow Rate Measurement Device

4. IOS Building Vent

a. Particulate Sampler M NA R SA Attachment 17 Page1of2

~

MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP-0002 PROCEDURES MANUAL

. REVISION: 9 TITLE: OFF-SITE DOSE CALCULATION MANUAL PAGE: 70 of 74 RADIOACTIVE GASEOUS EEELUENT MONITORING INSTRUMENTATION SURVEILLANCE REOU1REMENTS (Continued)

Table Notation (1) The CHANNEL TEST shall also demonstrate that automatic termination of the purge and control room alarm annunciation occurs if any of the following conditions exist:

Instrument indicates measured levels above the alarm / trip setpoint.

1

Circuit failure.

Instrument indicates a downscale failure.

4 e Instrument controls not set in operate mode.

(2) The CHANNEL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist:

e Instrument indicate measured levels above the alarm / trip setpoint.

Circuit failure. -

Instrument indicates a downscale failure.

e Instrument controls not set in operate mode.

, (3) The INSTRUMENT CHANNEL CALIBRATION shall be performed using one or more reference standards.

(4) A check shall be performed prior to each release and monthly during periods of continuous purging.

l.

l l

Attachment 17 Page 2 of 2 i

MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE: OFF-SITE DOSE CALCULATION MANUAL PAGE:' 71 of 74 ;

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM d

Lower Limit ofDetection Sampling Minimum Analysis Type of Activity (LLD)'"

Gaseous Release Type Frequency Frequency Analysis (pCi/ml)

A. Reactor Building M M Kr 85 1.00 E-04 Stack Grab Sample H3 1.00 E-06 B. Auxiliary Building M*' M Kr 85 1.00 E-04 Stack Grab Sample H3 1.00 E-06 C. Auxiliary Building M M Kr-85 1.00 E-04 Grade Level Vent Grab Sample H3 1.00 E-06 D. All Release Continuous M Principal Gamma 1.00 E-11 Types as listed in Particulate Sample Emitters'"

A, B, C above Continuous M Gross Alpha"' l.00 E-11 Particulate Sample Sr-90"' l.00 E-l l Continuous Continuous Nuble Gases, Gross 1.00 E-04 (Noble Gas Monitor) Beta and Gamma as Xe-133 Table Nel;tti.0B (a) 1. The Lower Limits of Detection (LLDs) for the radionuclides presented in this table are the smallest concentration (expressed in microcuries per unit volume) which are required to be detected, if present, in order to achieve compliance with the limits of the Specifications in Steps 6.14.6, 6.14.7, and 6.14.8.

2. The LLD of a radioanalysis system is that value which willindicate the presence or absence of radioactivity in a sample when the probability of a false positive and of a false negative determination is stated. The probabilities of the false positive and false negative are taken as equal at 0.05. The general equation for estimating the maximum LLD in microcuries per milliliter is given by th9 following:

2.7 + 3.29 x S b LLD = 5 (3.70 E + 04)(Y x E x V)eN'd Attachment 18 Page1of3

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

i MANUAL:- CHEMISTRY ADMINISTRATIVE

- NUMBER: CAP-0002 -

PROCEDURES MANUAL

' REVISION: 9

- TITLE: OFF-SITE DOSE CALCULATION MANUAL' PAGE. 72 of 74

' RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM (Continued)

Where:

= factor to account for Poisson statistics at very low background count rates

) 2.71 3.29 - = two times the constant used to establish the one sided 0.95 confidence

, interval 4

3,70 E+04 = disintegrations /second/ microcurie i

Y = yield of radiochemical process, i.e., the product of all factors such as emission fraction, chemical yield, etc.

E = counting efliciency (count / disintegrations)

= sample volume (milliliters)

A = the radioactive decay constant for the particular nuclide (seconds)

t. = the elapsed time from midpoint of collection to the midpoint of counting S. = the standard deviation of the background counting rate r 3 0.5 B B S$

= .+

(t tbs t h Where:

B= background counts ts = background countinginterval(seconds)

t. - sample counting interval (seconds)

Attachment 18 Page 2 of 3

1 MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE: OFF-SITE DOSE CALCULATION MANUAL PAGE: 73 of 74 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAhl (Continued) :

Table Notation (Continued)

3. The LLD is defined as an a priori (before the fact) estimate and is not to be calculated for each sample analyzed on an a posteriori(after the fact) basis.

(b) Tritium grab samples shall be taken at least once per seven days from the ventilation exhaust from the auxiliary building stack anytime fuel is in the spent fuel pool and the pool temperature exceeds 110 F. Below 110*F there is ersentially no evaporation from this source.

(c) Principal gamma emitters for which the LLD applies are: Kr-85 for gaseous samples and Mn-54, Co-60,2n-65, Cs 134, Cs 137, and Ce 144 for particulate samples. This does not mean only these nuclides will be detected and reponed. Other peaks that are measurable and identifiable shall be reported in the Annual Radioactive Efiluent Release Report, pursuant to Step 6.15.1. All peaks which are measurable and identifiable shall be reported and entered into the ODCM evaluations.

Nuclides which are not observed for the analysis shall be reported as "less than" the nuclide's a posteriori minimum de'ectable concentration and shall not be reported as being present. The "less than" results shall be considered "zero" for the ODCM evaluations; however, if a nuclide is measured and identified at a value less than the Attachment 18 LLD value, it shall be reported and entered into ODCM evaluations.

(d) A gross beta analysis is performed on a monthly basis for each environmental release particulate sample. If any one of these samples indicates greater than 1,0E-11 pCi/cc gross beta Sr-90 activity, then an analysis will be performed on those samples exceeding this value (c) A gross alpha analysis is performed on a monthly basis for each environmental release particulate sample. This fulfills the requirements of performing a monthly composite.

Attachment 18 Page 3 of 3

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