Text

Rev 19 to Odcm
	ML20203H250
Person / Time
Site:	Limerick
Issue date:	12/31/1997
From:	Boyce R; PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	;
Shared Package
ML20203H137	List: ML20203H133; ML20203H191; ML20203H220; ML20203H250; ML20203H270;
References
	PROC-971231, NUDOCS 9803030182
	Download: ML20203H250 (175)
	v • d • e

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Part I-- RADIOLOGICAL EFFLUENT CONTROLS f l 1. 0 DEFINITIONS 1 !

2.0 BASES 6 3.0 CONTROLS 17 r l 3.1 METEOROLOGICAL MONITORING 17 l 3.1.1 Meteorological Monitoring Instrumentation 17 l 3.2 LIQUID EFFLUENTS 21 ;

i 3.2.1 Radioactive Liquid Effluent Monitoring

Instrumentation 21

l. 3.2.2 Concentration In Liquid Effluents 26 l

l 3.2.3 Dose Due To Liquid Effluents 30 l 3.2.4 Liquid Radwaste Treatment System 31 l 3.3 GASEOUS EFFLUENTS 32 j 3.3.1 Radioactive Gaseous Effluent Monitoring ,

l Instrumentation 32 l '3.3.2 SITE BOUNDARY Dose Rate 37 l' 3.3.3 Dose - Noble' Gases 41 3.3.4 Dose - Iodine-131, Iodine-133,' Tritium, and l Radionuclides-in Particulate Form 42 l 3.3.5 Ventilation Exhaust Treatment System 43 l l 3.3.6 Venting or-Purging 44 3.3.7 Total Dose 45 3.3.8 Dose Incineration of Radioactive Waste Oil 46 l 3.4 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 47 l __ 3 '. 4 ._1 :. Monitoring Program _ l47 l- -3.4.2'- Land Use'censur 60

.l 3.4.3 Interlaboratory Comparison-Program 61 l 3.5 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT. 62 i

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63 l 3.6 ANNUAL RADIOACTIVE EFFLUENT RELEAS3 PIPORT '

3.7 MAJOR CHANGES'TO RADIOACTIVE WASTE TREATMENT SYSTEMS 66 i Part II ~ CALCULATION METHODOLOGIES -

l 1.0 LIQUID EFFLUENTS 67 f 1.1 RADIATION MONITORING INSTRUMENTATION AND CONTROLS 67 ;

LIQUID EFFLUENT MONITOR SETPOINT DETERMINATION 68 ;

l 1. 2 1.2.1 Radwaste Discharge Monitor 68 l

I l 1.2.2 Service Water Radiation Monitor 71 1.2.3 RHR Service Water Monitor 72 l

LIQUID EFFLUENT DOSE CALCULATIONS - 10 CFR 50 73 l 1. 3 1.3.1 Member of the Public Dose - Liquid Effluents 73 :

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LIQUID EFFLUENT DOSE PROJECTION 76 l 1. 4 ,

77 l 2.0 GASEOUS EFFLUENTS RADIATION MONITORING INSTRUMENTATION AND CONTROLS 77 l 2.1 GASEOUS 8:FFLUENT MONITOR SETPOINT DETERMINATION 78 l 2.2 2.2.1 North Vent Noble Gas Effluent Monitors 79 l

l 2.2.2 Sduth Vent Noble Gas Effluent Monitors 81 l 2.2.3 Noble Gas Effluent Fractional Contribution 83 ;

2.2.4 Noble Gas Effluent Default Setpoints 83 l

2.2.5 WRAM Noble Gas Effluent Monitor 86 l

GASEOUS EFFLUENT DOSE EVALUATIONS 88 l 2.3 l 2.3.1 Site Boundary Dose Rate - Noble Gases 88 2.3.2 S te Boundary Dose Rate - Radioiodine and Particulates 90 a-

-l- 2.3,3 Noble Gas Air Dose 90

_l 2.3.4 Radioiodine_and Particulate Dose Calculations 91 l 2.3.5 Incineration of Contaminated Oil 93 l

j' 2.3.6 Gaseous Effluent' Dose Projection 95 11

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I l Page I l 3.0 ANNUAL DOSE EVALUATION 96 {

l 4.0 SPECIAL DOSE ANALYSIS 96 fi l 4.1 TOTAL DOSES TO MEMBERS OF THE PUBLIC 96 l 4.2 DOSES DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY 97 j 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 98 5.1 SAMPLING PROGRAM 98 l 1

5.2 INTERLABORATORY COMPARISON PROGPM 98 !

l LIST OF TABLES j lI 1.1 Surveillance Frequency Notation 5 l 1 3,1-1 Meteorological. Monitoring Instrumentation 18 I 3.1-2 Meteorological Monitoring Instrumentation Surveillance Requirements 18 ;

I 3.1-3 Meteorological Tower Data Retrieval 19 I 3.2-1 Radioactive Liquid Effluent Monitoring l Instrumentation 22 I 3.2-2 Radioactive Liquid Effluent Monitoring i l Instrumentation Surveillance Requirements 24 l I 3,2-3 Radioactive Liquid Waste Sampling and Analysis 27

Program I 3'.3-1 Radioactive Gaseous Effluent Monitoring

l Instrumentation 33 i

I 3.3-2 Radioacti've Gaseous Effluent Monitoring l Instrumentation Surveillance Requirements 35 I 3.3-3 Radioactive Gaseous Waste Sampling and Analysis l Program 38 !

l I 3.4-1 Radiological Environmental Monitoring Program 49

, I'3.4-2 _ Reporting Levels for Radioactivity Concentrations In

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Environmental Samples 56 '

I'3.4-3 Detection Capabilities For Environmental Sample

j. Analysis. 57 l l

l1151 Ingestion Individual Dose Factors (D,ug) For Liquid 99 i

. Effluents l-111

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< l II 1-2 Dose Factors for Standing on Shoreline 108 i i

II 1-3 Assumptions Used In Limerick Effluent Dose Evaluations 109 .

l II 2-1 Dose Factors for lloble Gases 110

II 2-2 Ingestion Individual Dose Factors (R,) For Gaseous l Effluent 111 Il 2-3 Assumptions Used In Limerick Gaseous Eff'uent i Dose Evaluation 136 ,

) II 2-4 Nearest Gaseous Effluent Dose Receptor Distances (Meters) 137 l

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4 LIST OF FIGURES '

l- Page I 2.2-la Map Defining Exclusion Areas for Radioactive l Gaseous and Liquid Effluents 7 -

1 2.2-1b Map Defining Low Population Areas for l Radioactive Gaseous and Liquid Effluents 8 lI 3.1-1 Meteorological Tower Location 20 l II 1. 3.1-1 LGS Dilution vs River Flow (Station outfall) 150 l II 1. 3.1-2 LGS Dilution vs River Flow (Citizen's Utility) 151 l II 1. 3.1-3 LGS Dilution vs River Flow (Phoenixville) 152 l'II 1.3.1-4 LGS Dilution vs River Flow (Philadelphia 153 Suburban) l Il 1. 3.1-5 LGS Dilution vs River Flow (Crew Course) 154 l II 1-1 Liquid Effluent Flow Diagram 155 l II 2-1 ,

Gaseous Effluent Flow Diagram - North Stack 156 l II 2-2 Gaseous Effluent Flow Diagram - South Stack 157 II 2-3 Gaseous Effluent Flow Diagram - Hot Maintenance l Shop 158 B-1 Environmental Sampling Location on Site or Near l the Limerick Generating Station 159 B-2 Environmental Sampling Locations at Distances Less Than Five Miles from the Limerick l Generating Station 160 B-3 Environmental Sampling Locations at Distances

, Greater Than Five Miles from the Limerick l . Generating Station 161 i

! APPENDICES i

l Appendix A - Technical Specification /ODCM Matrix 138 l Appendix B - Radiological Environmental Monitoring . 141

-Program - Sample Type, Location and Analysis

} Appendix C - Requirements for_ODCM Revision 146 V

PURPOSE The purpose of the offsite Dose Calculation Manual is to establish methodologies and procedures for calculating doses to individuals in areas at and beyond the SITE BOUNDARY due to radioactive effluents from Limerick Generating Station, l

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. ODCM Rev. 19 l Page 1 l 1

i 12/97 ;

i i

l 1.0 DEFINITIONS i i !

, The following terms are taken from LGS Unit 1/ Unit 2 Tech Specs, f t

I unless otherwise noted.

i 1.1 ACTION !

! ACTION shall be that part of a specification which prescribes remedial measures required under designated i*

conditions.

1.2 CHANNEL CALIBRATION l A CHANNEL CALIBRATION shall be the adjustment, as !'

necessary, of the channel output such that it responds j with the necessary range and accuracy to known values of !

the parameter which the channel monitors. The CHANNEL >

j CALIBRATION shall encompass the entire channel including i the sensor and alarm and/or t. vip functions, and shall 4 include the CHANNEL FUNCTION 'iEST. The CHANNEL !

CALIBRATION may be performed by any series of sequential, ,

j overlapping or total channel steps such that the entire

1 channel is calibrated. !

1.3 CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment of

! channel behavior during operation by observation. This determination shall include, where possible, comparison of ;

the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.

1.4 CHANNEL FUNCTIONAL TEST

A CHANNEL FUNCTIONAL TEST shall be:

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

b. Bistable channels - the injection of a simulated -

signal into-the sensor to verify OPERABILITY including alarm and/or trip functions. ,

The CHANNEL FUNCTIONAL TEST may be performed by any series f i of sequential, overlapping or total channel steps such.

that the entire channel is tested.

- 1. 5 CONTINUOUS SAMPLING Per L ASTM Standard (1987)Section II (Water and Environmental ; Technology) , Volume 11.03, Article D1356; is t, defined as;" sampling without interruptions throughout an-

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ODCH Rev. 19 Page 2 j 12/97 ;

2.0 DEFINITIONS i i

operation or for a predetermined time. A CONTIh'UOUS SAMPLE is the opposite of a GRAB SAMPLE. The time period :

involved to secure (shut-down) ventilation or re-establish !

sampling of the release pathway shall meet the intent of l CONTINUOUS SAM" LING. Consistent with industry standards, i the time allowance shall not exceed 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , j 1.6 DOSE EQUIVALENT I-131 DOSE EQUIVALENT I-131 shall be that concentration of I- l 131, microcuries per gram, which alone would produce the same thyroid doce as the quantity and isotopic mixture of I-131, I-132, 1-133, I-134 and I-135 actually present. '

The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, " Calculation of Distance Factors for Power and Test Reactor Sites." ,

1.7 FREQUENCY NOTATION ;

The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 11.1. l 1.8 MEMBER (S) OF THE PUBLIC MEMBER (S) OF THE PUBLIC shall include all persons who are i not occupationally associated with the plant. This category does not include employees of the utility, its contractors, or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who .

use portions of the site for recreational, occupational or other purposes not associated with the plant.

1.9 OFFSITE DOSE CALCULATION MANUAL The OFFSITE ;>OSE CALCULATION MANUAL (ODCM) shall contain

the meth7&. logy and parameters used in the calculation of

offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Radiological Environmental Monitoring

?- Program.- The ODCM-shall also contain (1) the Radioactive '

Effluents controls and Radiological Environmental Monitoring Programs required by Technical Specification l- 6.8.4, (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radiological Effluent Release Reports ,

required by_ Technical Specifications 6.9.1.7 and 6.9.1.8, i and.(3) description of meteorological monitoring controls.

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ODCM Rev. 19 l Page 3 l 12/97 j i

1.0 DEFINITIONS !

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, 1.10 OPERABLE - OPERABILITY i

A system, subsystem, train, component or device shall be l'

OPERABLE or have OPERABILITY when it is capable of performing its specified functions (s) and when all ,

necessary attendant instrumentation, con *.rols, electrical "

power, cooling or seal water, lubrication or other ;

auxiliary equipment that are recuired for the system, .i subsystem, train, component or c.evice to perform its function (s) are also capable of performing their related ;

support function (s) . ':

1.11 OPERATIONAL CONDITION - CONDITION i i

e An OPERATIONAL CONDITION, i.e., CONDITION, shall be any one inclusive combination of mode switch position and average reactor coolant temperature as defined in the Technical Specifications.

1.12 PURGE - PURGING PURGE or PURGING shall be the controlled process of

, discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

1.13 RATED THERMAL POWER See current LGS Tech Spec definition.

1.14 REPORTABLE EVENT -

A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 of 10 CFR Part 50.

1.15 SITE BOUNDARY The SITE BOUNDARY shall be that line as defined in Figure I I2.2-la. l 1.16 SOURCE CHECK A SOURCE CHECK shall be the qualitative assessment of

channel-response when the-channel-sensor is exposed to a- ;

radioactive source.

1.17 THERMAL POWER THERMAL POWER shall be the total reactor core heat .

transfer-rate-to the reactor coolant. !

I ODQ4 Rev.19 !

Page 4 12/97 1.0 DEFINITIONS l 1.18 UNRESTRICTED AREA l 1

An UNRESTRICTED AREA shall be any area at or beyond the

SITE BOUNDARY access to which is not controlled by the !

I licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any l area within the SITE BOUNDARY used for residential ,

quarters or for industrial, commercial, institutional, ;

and/or recreational purposes. -

t 1.19 VENTILATION EXHAUST TREATMENT SYSTEM A VENTILATION EXHAUST TREATMENT SYSTEM shall be any system designed and installad to reduce gaseous radioiodine or j radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal absorbers and/or HEPA filters for the purpose of removing lodines or particulates from the gaseous exhaust stream prior to the release to the environment (such a system is not considered to have any effect on noble gas effluents).

Engineered Safety Feature (ESP) atmospheric cleanup :

systems are not considered to be VENTILATION EXHAUST !

TREATMENT SYSTEM components. j 1.20 VENTING f VENTING shall be the controlled process of discharging air ;

or gas frem a confinement to maintain temperature, ~

pressure, humidity, concentration or other operating i condition, in such a manner that replacement air or gas is not provided or required during VENTING. Vent, used in '

system names, does not imply a VENTING process, i i

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Page 5 :

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1.0 DEFINITIOllS I e

TABLE 11.1 -

SURVEILLANCE PkEQUENCY NOTATION NOTATION FREQUENCY r

-S (Shift) At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

D (Daily) At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

W (Weep.ly) At least once per 7 days.

H (Monthly) At least once per 31 days.

0 (Quarterly) At least once per 92 days. !

SA-(Semi-annual) At least once per 184 days. I A (tenual) At least once per 306 days, s

E At least once per 18 months (550 day,5) . !

R At least once per 24 months (731 days).

S/U Prior to each reactor startup. ;

P Prior to each radioactive releese.

N.A. Not applicable, '

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ODCM Rev. 19 [

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l l 2.0 BASES 3

! I l 2.1 METEOROLOGICAL INSTRUMENTATION ,

i The OPERABILITY of the meteorological monitoring -

instrumentation onrures that sufficient meteorological l

data is available for estimating potential radiation doses to the public as a result of routine or accidental release ;

i of radioactive materials to the atmosphere. This capability is required to evaluate the need for initiating measures to protect the health and safety of the public.

This instrumentation is consistent with the

!: recommendations of Regulatory Guide 1.23 "Onsite Meteorological Programs," Pebruary, 1972.

Site data compiled since January 1972 provide correlation between Elevation 1 (Tower 1) and Elevation 1 (Tower 2),

! and between Elevation 2 (Tower 1) and Elevation 2 (Tower i 2). This correlation serves as justification for the use '

t of the appropriate Tower 2 instrument as a back-up to the Tower 1 instrument as shown in Table 13.1-1 and Table I3.1-3.

2.2 MAPS DEFINING UNRESTRICTED AREAS AND SITE BOUNDARY FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS Information regarding radioactive gaseous and liquid -

L effluents, which will allow identification of structures and release points as well as definition of UNRESTRICTED AREAS within the SITE BOUNDARY that are accessible to l MEMBER (S) OF THE PUBLIC, shall be as shown in Technical ;

j Specifications Figures 5.1.3-la and 5.1.3-lb.

The exclusion area and low population zone shall be as

, shown in Figures 12.2-la and I2.2-1b.

}- 2.3 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents.

The-alarm / trip-setpoints for these instruments shall be calculated in accordance with the procedures in the ODCM

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Part II to ensure that the alarm / trip will occur prior to exceeding the-limits of 10 CFR Part 20 (pre-1994). 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, a

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12/97 i l 2.0 BASES l

! I

l 2.4 CONCENTRATION IN LIQUID EFFLUENTS

] This control is provided to ensure that the concentration

of radioactive materials released in liquid waste '

i effluents to UNRESTRICTED AREAS will be less than the concentration levels specified in 10 CFR Part 20, Appendix l B, Table II, Column 2 (pre-1994). This limitation i provides additional assurance that the levels of

! radioactive materials in bodies of water in UNRESTRICTED

]

AREAS will result in exposures within (1) the Section II.A -

design objectives of Appendix I, 10 CTR Part 50,-to a !

) MEMBER OF THE PUBLIC, and (2) the limits of 10 CFR

'j 20.1301(e) to the population. The concentration limits ;

for dissolved or entrained noble gases are based upon the assumption that Xe-135 is the controlling radioisotope and ;

its MPC in air was converted to an equivalent i concentration in water using the methods described in the

{ International Commission on Radiological Protection (ICRP) 4 Publication 2. ,

! The required detection capabilities for radioactive i materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits can be found in RASL Procedures Manual, HASL-300 (revised annually); Currie, L.A., " Limits for Qualitative Detection and Quantitative Determination - Application to j Radiochemistry"; Anal. Chem, 40, 586-93 (1968); and ;

Hartwell, 1.K., " Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June, 1975).

l 2.5 DOSE DUE TO LIQUID EFFLUENTS

! This Control is provided to implement the requirements of Sections II.A, III.A, and IV.A of Appendix I, 10 CFR Part

50. The Control implements the guides set forth in Section II.A of Appe dix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be_kept "as-low as reasonably achievable". Also, for fresh water sites with' drinking Pater-supplies which can be potentially-affected by plant operations,=there is reasonable-assurance-that the-operaticn of the facility will not result in radionuclide concentrations in the finished drinking water t' : . are in excess of the requirements-of 40_CFR Part 141. Tha-dose '

calculation methodology and parameters in the 09CM implement the requirements 4n Section III.A of Appendix I that conformance with the guides of Appendix I be-shown-by calculational procedures based on models and data, such

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! ODCM Rev. 19 !

! Page 10 ,

12/97 i

i l 2.0 BASES f'

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i that the actual exposure of a MEMBER OF THE PUBLIC through ,

appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for 4 calculating the doses due to the actual release rates of .

i radioactive materials in liquid effluents are consistent !

l with the methodology provided in Regulatory Guide 1.109, !

1

" Calculation of Annual Doses to Man from Routine Releases !

of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, 4

October, 1977 and Regulatory Guide 1.113, " Estimating ;

{ Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April, 1977 ;

] This control applies to the release of radioactive

' materials in liquid effluents from the site, a

j l 2.6 LIQUID RADWASTE TREATMENT SYSTEM

The requirement that the appropriate-portions of this '

l system be used when specified provides assurance that the

! releases of radioactive materials in liquid effluents will ,

be kept "as low as reasonably achievable". This

specification implements the requirements of 10 CFR

! 50.35a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid

radwaste treatment system were specified as a suitable L fraction of the dose design objectives set forth in i Section II.A of Appendix I, 10 CFR Part 50, for liquid '

j effluents.

l2? RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION

! The radioactive gaseous effluent instrumentation is

provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents.

The alarm / trip setpoints for these instruments shall be calculated in accordance with the procedures in the ODQ4 ;

Part II to ensure that the alarm / trip will occur prior to i exceeding the limits of 10 CFR Part 20 (pre-1994) . The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 54 of Appendix A to 10 CFR Part-50.

l 2.6 DOSE RATE FROM GASEOUS EFFLUENTS

-This control is provided to ensure that the dose at any

. time:at and beyond the SITE BOUNDARY from gaseous effluents from the site will be within the annual dose

l limits of 10 CFR' Part 20 (pre-1994)-to UNRESTRICTED AREAS.

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

ODQ4 Rev. 19 Page 11 12/97 l 2.0 BASES l The annual dose limits are the dose associated with the concentrations of 10 CFR Part 20, Appendix B, Table II, l Column I (pre-1994) . These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either within or outside the SITE BOUNDARY, to annual average concentrations exceeding the limits specified in Appendix l B, Table II of 10 CFR Part 20 (pre-1994). For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy factor for that MEMBER OF THE PUBLIC will usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor for above that for the SITE BOUNDARY. Examples of calculations for such MEMBERS OF THE PUBLIC, with the appropriate occupancy factors, are given in the ODCM. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrems/ year to the total body or to less than - or equal to 3000 mrems/ year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the' inhalation pathway to less than or equal to 1500 mrems/ year.

This Control applies to the release of radioactive materials in gaseous effluents from all reactors at the site.

The required detection capability for radioactive materials in gaseous waste-samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits can be tound in HASL Procedures Manual, RASL-300 (revised annually); Currie, L.A., " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry"; Anal. Chem. 40, 586-93 (1986); and Hartwell, J.K., " Detection Limits for Radioanalytical Counting. Techniques." Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

l 2.9 DOSE - NOBLF GA3ES This control is provided to implement the requirements of Sections II.B, III.A, and IV.A of Appendix I, 10 CFR Part '

50. The control-implements the_ guides set forth in Section II.B of Appendix I.- The ACTION statements provide _

-the required operating _ flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as reasonably achievable". The Surveillance Requirements implement _the requirements in Section III.A of Appendix I that

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

ODCM Rev. 19 ;

Page 12 l 12/97 !

l- '

l l 2.0 BASES l

! conformsnce with the guides of Appendix I be shown by l l calculational procedures based on appropriate pathways is unlikely to be substantially underestimated. The dose !

calculation established in the ODCM for calculating the i

doses due to the actual release rates of radioactive noble (

j gases in gaseous effluents are consistent with the

! methodology prcvided in Pegulatory Guide 1.109, ,

l " Calculation of Annual Doses to Man from Routine Releases !

of Reactor Effluents for the Purpose of Evaluating ,

i Compliance with 10 CFR Part 50, Appendix I," Revision I, ;

j october 1977 and Regulatory Guide 1.111, " Methods for !

l Estimating Atmospheric Transport and Dispersion of Gaseous '

j Effluents in Routing Releases from Light-Water Cooled

Reactors," Revision 1, July 1977 with site specific

- dispersion curves and deposition methodology. The ODCM

j equations provided for determining the air doses at and i j beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions.

i l 2.10 DOSE - IODINE-131, IODINE-133, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FOkM I This control is provided to implement the requirements of Sections II.C, III.A, and IV.A of Appendix I, 10 CFR Part 50. The controls are the guides set forth in 3

Section II.C of Appendix I. The ACTION statements provide ,

~

the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in !

j gaseous effluents will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in i the Surveillance Requirements implement the requirements in Section III.A of Appendix I, that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of 4

a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methods for calculating the doses due to the actual release rates of the subject materials are

& consistent with the methodology provided in Regulatory 4

Guide 1.109, Calculation of Annual Doses to Man from 4

Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50 Appendix 1,"

Revision I,-October 1977-and Regulatory Guide 1.111,

" Methods for Estimating Atmospheric Transport and i Dispersion of Gaseous Effluents in Routine Releasas from Light-Water-Cooled Reactors," Revision 1, July 1977 with site specific dispersion curves and deposition 1 methodology. These equations also provide for determining the actual doses based upon the historical average atmosphetic conditions. The release rate specifications ;

i for iodine-131, iodine-133, tritium, and radionuclides in i

- particulate 1 form with, half-lives greater than 8 days are -

rW*wWM m B-9'trf '1 WWW9""TN7P-d- -9't*"'-U-'"31e'* Thengr-'Sw+=*'iiM-$- -L'amtt*"+=vaiw-*mg7- t hy - F vet *7 eyp*r"--"p+9e" Tr> cP*#"-8g" F "Ty-igrWT-"-etPT"M-'-"--'-M7

ODCM Rev. 19 Page 13 12/97 l 2.0 BASES dependent on the existing radionuclides pathways to man in areas at and beyond the SITE BOUNDARY. The pathways which were examined in the development of these calculations were: (1) individual inhalation of airborne 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.

l 2.11 VENTIIE.1ON EXHAUST TREATMENT SYSTEM The requirement that the appropriate portions of this system be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This control implements the requirements of 10 CFR 50.36a, General Design Criteria 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Section II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.

l 2.12 VENTING OR PURGING This control provides reasonable assurance that releases from drywell purging operations will not exceed the annual dose limits of 10 CFR Part 20 for UNRESTRICTED AREAS.

l 2.13 TOTAL DOSE This control is provided to-meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20 by 46 CFR 18525. The control requires the preparation and submittal of a Special Report whenever the calculated doses from plant radioactive effluents exceed twice the design objective doses of Appendix I. For s'.tes

-containing up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR 190 if the individual reactors remain within the reporting requirement level.

The Special Peport will-describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE'PUBLIC to within the 40 CFR Part 190 limits.

For.the. purposes of-the Special Report, it may be assumed that the dose commitment to-the MEMBER OF THE PUBLIC from

-other uranium-fuel cycle sources.is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 5

i i l

ODOM Rev. 19 l Page 14 ;

12/97 ;

l 2.0 i BASES 4 i 1

miles must be considered. If the dose to any MEMBER OF l THE PUBLIC is estimated to exceed the requirements of 40 i CTR Part 190, the Special Report with a request for a 1 variance (provided the release condition resulting in

violation of 40 CFR Part 190 have not already been

! corrected), in accordance with the provisions of

! 40 CFR 190.11 and 10 CFR 20.2203, is considered to be a timely request and fulfills the requirements of 4

40 CFR Part 90 until NRC staf f action is completed. An individual is not considered a MEMBER OF THE PUBLIC during

any period in which he/she is engaged in carrying out any I operation that is part of the nuclear fuel cycle.

l l 2.14 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM The Radiological Environmental Monitoring Program- (REMP) required by this control provides representative

! measurements of radiation and of radioactive materials in

! those exposure pathways and for those radionuclides that lead to the hignest potential radiation exposures of

MEMBER OF THE PUBLIC resulting from the station operation.

This monitoring program implementsSection IV.B.2 of-Appendix I to 10 CFR Part 50 and thereby supplements the radiological effluent monitoring program by verifying that i

the measurable concentrations of radioactive materlats and ,

, levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. ,

j The required detection capabilities for environmental

~

sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs required by Table I3.4-3 are considered optimum for routine environmental i measurements in industrial laboratories. It should be I recognized that the LLD is defined as an a priori (before j the fact) limit representing the capability of a

measurement system and not an after the fact limit for a particular measurement.

Detailed discussion of the LLD, and other detection r

limits, can be found in RASL Procedures Manual, RASL-300 i (revised annually); Currie L.A., " Limits for Qualitative Detection and Quantitative Determination - Application to 4 Radiochemistry," Anal. Chem, 40, 586-93 (1968), and i Hartwell,.J.K., " Detection Limits for Radioanalytical

. Counting Techniques," Atlantic Richfield Hanford Company Report AAH-SA-215 (June, 1975).

l 2.15 LAND USE CENSUS This control is provided to ensure that. changes in the use of areas at and beyond the SITE BOUNDARY are t identified and that. modifications to the monitoring i

~

k

, r ODQ4 Rev.19 [

, Page 15 ,

l 12/97 !

j l 2.0 - BASES l

! program are made if required by the results of the !

census. The best information from the door-to-door !

3 survey, aerial survey or consulting with local !

i agricultural authorities or any combination of these l methods shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census to gardens of gretter i thaa 500 square feet provices assurance that sign ficant ;

exposure pathways via leafy vegetables will be identified l

and monitored since a garden of this size is the minimum !

required to produce the quantity (26 Kg/ year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were used: (1) that 20%

of the garden was used for growing broad leafy vegetation ,

(i.e. similar to lettuce and cabbage), and (2) a vegetation yield of 2 kg/ Square meter.

l 2.16 INTERLABORATORY COMPARISON PROGRAM 4

i The requirement for participation in an Interlaboratory l

Comparison Program ensures that independent checks on the precision and accuracy of the measurements of radioactive

material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are

, reasonably valid for the purpose of Section IV.B.2 of Appendix I to 10 CFR Part 50.

l 2.17 APPLICABILITY #

2.17.1 Compliance with the controls contained in the following i controls sectior. is required during the OPERATIONAL CONDITIONS or other conditions specified therein; except that upon failure to meet the controls, the associated ACTION requirements shall be met.

l 2.17.2 Non compliance with a control shall exist when the requirements of the control and associated ACTION requirements are not performed within the specified time )*

intervals. If the control is restored prior to expiration of the specified time intervals, completion of the ACTION requirements is not required.

1l-2.17.3 There are no actions in the ODC4 which would require an I

operational condition change.

l 2.17.4 There are no restrictions on changing operating conditions in-any of the controls on the ODCM. ,

l 2.17.5 Surveillance Requirements shall be met during the ,

OPERATIONAL CONDITIONS or_other ccnditions specified for 1 individual controls unless otherwise stated in an

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

l ODCM Rev. 19

Page 16 l 12/97 l 2.0

)

EASES ,

4 f

I

! individual Surveillant .aquirement.

! i l 2.17.6 Each surveillanco Requirement shall be performed within i j the specified interval with a maximum allowable extension !

not to exceed 25% of the surveillance interval. ;

t i 2.17.7 Failure to perform a Surveillance Requirement within the ,

j allowed surveillance interval defined by Bases 2.17.6, t kall constitute noncompliance with the OPERABILITY j ,quirements for a control. The time limits of the ACTION j requirements are applicable at the time it is identified l'

that a surveillance Requirement has not been performed.

! The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to permit the completion of the surveillance whei the i allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Surveillance requiremer.ts do not have to be performed on inoperab.ie equipment.

The associated bases from the LGS Technical Spr:ifications l apply to this section.

2.18 10CFR20 Par Technical Specification Section 6.8.4.d, the Radioactive Effluent Controls Program must conform with limitations specified in 10CFR50.36a, 10CFR Part 50, Appendix 1, 10CFR Part 20, Appendix B, Table II, Column 2 (pre-1994 issue) and 40CFR 190. (See Reference 14) 1

'I

_ . - - . . . , _ . _ . _ _ . , - . - - ~ - . . - , . _ . . . - - ___. - _ ._ _ ,-.. - _ 4

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

ODCM Rev. 19 Page 17 ,

12/97 !

3.0 CONTROLS

3. I' METEOROLOGICAL MONITORING l 3.I.1 METEOROLOGICAL MONITORING INSTRUMENTATION The meteorological monitoring instrumentation channels shown in Table I3.1-1 shall be OPERABLE.

APPLICABILITY: At all times.

ACTION:

With less than the minimum required instrumentation channels operable for more than 7 days, prepare and submit a Special Report to the Commission pursuant to LGS Technical Specification 6.9.2 within the next 10 days

outlilang the cause of the malfunction and the plans for restoring the instrumentation to OPERABLE status.

SURVEILLANCE REQUIREMENTS 3.1-1 Each of-the above required meteorological monitoring instrumentation channels shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 13.1-2.

4 i

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J ODCM Rev. 19 Page 18 12/9~/

3.0 CONTROLS 3.1 MEIEOROLOGICAL MONITORING TABLE 13.1-1 METEOROLOGICAL MONITORING INSTRUMENTATICJ MINIMUM Tower 1 Tower 2 INSTRUMENT INSTRUMEb]T_ (Primary) (Backup) OPERABLE

1. Wind Speed

a. Elevation '. 30 feet 159 feet 1

b. Elevation 2 175 feet 304 feet 1

2. Wind Direction

a. Elevation 1 30 feet 159 feet 1

b. Elevation 2 175 feet 304 feet 1

3. Air Temperature Difference (AT)

a. Elevations 266 feet 300 feet 26 feet 26 feet 1 TABLE I3.1-2

-METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Channel Channel INSTRUMENT Check CALIBRATION

1. Wind Speed

a. Elevation 1 (Tower 1 and Tower 2) D SA

b. Elevation 2 (Tower 1 and Tower 2) D SA

2. Wind Direction a.-Elevation 1 (Tower 1 and Tower 2) D SA

b. Elevation 2 (Tower 1 and Tower 2) D SA

3. Air Temperature Ditierence ( AT)

a. Elevations 266 - 26 ft (Tower 1) D SA

b. Elevations 30C - 26 f t (Tower 2) D SA NOTE:

The meteorological towers shall be located as shown on Figure 13.1-1. For backup. sources of data retrieval, refer to Table 13.1-3.

E 1

ODCM Rev. 19 Page 19 12/97 3.0 CONTROLS 3.1 METEOROLOGICAL MONITORING TABLE I3.1-3 METEOROLOGICAL TOWER DATA RETRIEVAL INSTBUMEN'l TOWER 1 TOPIER 2 DATA LOGGER DATA '

RM-21A Channel if Wind Speed 1 (TWR1)

a. Elev. 1 Strip Chart Strip Chart RM-21A 14 (TWR2)

Wind Speed 5 (TWR1)

b. Elev. 2 Strip Chart Strip Chart RM-21A 21 (TWR2)

Wind Dir. 0 (TWRl)

a. Elev. 1 Strip Chart Strip Chart RM-21A 13 (TWR2)

Wind Dir. 4 (TWR1)

b. Elev. 2 Strip Chart Strip Chart RM-21A 20 (TWR2)

DELTA T Multi-pt Rec Multi-pt Rec RM-21A 7 (TWR1) 23 (TWR2)

PRIMARY OPTION:

A) IF DATA IS UNAVAILABLE FOR TOWER 1 TIIEN v tify corresponding data available for Tower 2 B) DATA IS AVAILABLE FROM RM-21A, DATA LOGGER OR STRIP CHARTS. THE SOURCES OF DATA IN ORDER OF PREFERENCE ARE THE RM-21A, DATA LOGGER OR STRIP CHARTS. DATA LOGGER AND STRIP CHARTS ARE LOCATED IN THE CONTROL ROOM.

l ODCM Rev. 19 Page 20 l 12/97 3.0 CONTROLS 3.1 METEOROLOGICAL MONITORING Figure 13.1-1 Meteorological Tower Location

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ODCM Rev. 19 Page 21 12/97 3.0 CONTROLS .

3.2 RADIOACTIVE LIQUID EFFLUENTS 3.2.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent monitoring instrumentation channels shov:n in Table I3.2-1 shall be OPERABLE with

their alarm / trip setpoints set to ensure that Control 13.2.2 is not exceeded. The alarm /setpoints' of these channels shall be determined and adjusted in accordance l with the methodology and parameters in Section II 1.2.

3 APPLICABILITY: At all times.

ACTION:

a. With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above control, immediately suspend the release of radioactive liquid effluents monitored by the affected channel, and declare

the channel inoperable.

b. With--less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table I3.2-1. Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION or explain in the next j Annual Radioactive Effluent Release Report why this

! inoperability was not corrected within the time specified.

4 SURVEILLANCE REQUIREMENTS 3.2.1-1 Each radioactive liquid effluent monitoring ;

instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST l operations at the frequencies shown in Table I3.2-2.

i

Excluding the flow rate measuring devices which are not determined and adjusted in accordance with the ODCM.

1 _

ODCM Rev. 19 Page 22 i 12/97.

3.0 CONTROLS ,

l -- 3.2 RADIOACTIVE LIOUID EFFLUENTS ,

! TABLE I3.2-1

. RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION

1. Gross Radioactivity Monitors Providing Automatic Termination of Release

! a. Liquid Radwaste. Effluent Line 1 100

l b. A/B RHR Service Water Effluent Line

1/ loop 101

2. Gross Radioactivity Monitors Not Providing Automatic Termination of Release

a. Service Water Effluent Line 1 101

3. Flow Rate Measurement Devices

a. Liquid Radwaste Effluent Line 1 102

} b. Discharge Line 1 102 Termination of the release is accomplished by auto trip of

-- the RHRSW pumps and remote manual closure of isolation

} valves.

t 4

i 5

1 4

b 4

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ODCM Rev. 19 Page 23

_l 12/97 3.0 CONTROLS 3.2 RADIOACTIVE LIQUID EFFLUENTS l

j- ACTION STATEMENTS Action 100- 'With less than the Minimum Required Channels operable, effluent releases may continue for up to 14 days provided that prior to initiating a ralease:

a. At least two independent samples are analyzed in accordance with Table 13.2-3, and

b. At least two technically qualified members of the facility staff independently verify the 4 release rate calculations and discharge line velving; Otherwise, suspend release of radioactive effluents via this pathway.

l Action 101- With less than the Minimum Required Channels operable, effluent releases via this pathway may continue for up to 30 days provided that, at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , grab samples are collected and analyzed for radioactivity by gamma isotopic

,- analysis (Principal Gamma Emitters, I-131, and 4

l Dissolved / Entrained Gases) at a Lower Limit of

, Detecticn as specified in Table I3.2-3 or gross radioactivity (beta or gamma). Gross Beta is i analyzed at an LLD of at.least 1N7 uCim1. Gross Gamma is analyzed at an LLD of at least SN7 uCi/ml.

If the A or'B RHRSW Process Rad Monitor should become inoperable, sampling is required at least once every eight (8) hours at a sample point common with the inoperable A and/or B RHRSW Process Rad Monitor (s). If a monitor is inoperable but will still continuously sample and annunciate on high activity, i.e. rad monitor bypass switch placed in

~

" Bypass", Chemistry sampling is not required as the continuous monitor sampling complies with the periodic sampling requirement.

1 Action 102- With less than_the Minimum Required Channels operable, effluent releases via this pathway may continue for up to 30, days proviued the flow rate is

, estimated at least o'nce per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual

-l releases. Pump curves generated in situ may be used to estimate flow.

1-

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ODCM Rev. 19 Page 24

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12/97 1

3.0 CONTROLS j- ,3 . 2: RADIOACTIVE LIQUID EFFLUENTS

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

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

TABLE I3.2-2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL 4 CHANNEL SOURCE CHANNEL ' FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST

1. Gross Radioactivity Monitors Providing 3 Automatic Termination of Release

a. Liquid Radwaste Effluent Line D* D* R(3) O(1)

b. RHR Service Water System Ef fluent Line D M R(3) Q(1)

2. Gross Radioactivity. Monitored Not Providing JAutomatic Termination of Release

a. Service Water System Effluent Line D M R(3) Q(2)

3. Flow Rate Measurement Devices

a. Liquid Radwaste Effluent Line D(4) N.A. R Q _

b. Discharge Line D(4) N.A. R O Daily when in une 4

3 I:

i ODCM Rev. 19 Page 25 l 12/97 3.0 : CONTROLS 3.2 RADIOACTIVE LIQUID EFFLUENTS TABLE-13.2-2 (Continued)

TABLE NOTATIONS 4

(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that 4

automatic isolation of this pathway and control room alarm annunciation will occur if any of the following conditions exists:

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

,- 2. Circuit failure.

3. Instrument indicates a downscale failure.

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

1. Instrument indicates measured levels above the alarm setpoint.

2. Circuit failure.

3. Instrument indicates a downscale failure.

(3) The initial CHANNEL CALIBRATION shall be performed using reference standards certified by the National Institute of Standards and Technology (NIST) obtained from suppliers that participate in measurement assurance activities with NIST.

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

~

(4) CHANNEL CHECK shall consist of verifying indication of flow

_ during periods of release. CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days-on-which batch releases are made.

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ODCM Rev. 19 i Page 26 12/97 ,

3.0 CONTROLS 3.2 RADIOACTIVE LIQUID EFFLUENTS l 3.2.2 CONCENTRATION IN LIQUID EFFLUENTS The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see Figure I2.2-la,b) shall be limited to the concentrations specified in ,

l 10 CFR Part 20, Appendix B, Table II, Column 2 (pre-1994) for radionuclides other than dissolved or entrained nobles gases. For dissolved or entrained noble gases, the concentration shall be limited to 2E-4 microcuries/ml l total activity (NUREG 0133, Section 2).

APPLICABILITY: At all times.

ACTION:

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

SURVEILLANCE REQUIREMENTS 3,2.2-1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 13.2-3, 3.2.2 The results of the radioactivity analyses shall be used in accordance with the methodology and parameters in l Section II 1.2 to assure that the concentrations at the point of release are maintained within the limits of Control I3.2.2.

-ODCM-Rev. 19 Page 27 12/97

-3.0 CONTROLS 3.2 RADIOACTIVE LIQUID EFFLUENTS TABLE I3.2-3 i RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGPR!

Lower Limit Minimum Type of of Detection t Liquid Release Sampling Analysis Activity (LLD)*

Type Frequency Frequency Analysis (uCi/M1)

A. Batch Waste P P . Principal Gamma SE-7 Release Each Batch Each Batch Emitters #

Tanks" I-131 IE-6

1. Floor or P M Dissolved and 1E-5 Equip. Drain One Batch /M Entrained Gases Sample Tanks (Gamma Emitters)'

2. Laundr'/ P M H-3 1E-5 d

Drain Sample Each Batch Composite Tank Gross Alpha 1E-7 P Q Sr-89, Sr-90 SE-8 Each Batch Composite d Fa-55 1E-6 B. Continuous W W Principal Gamma SE-7

, Release

Grab Sample Emitters #

I-131 1E-6 i 1

1. RHR Service W W Dissolved and IE-5 Water System Grab Sample Entrained Gases Effluent Line' (Gamma Emitters)#

, 2. Service Water W- M H-3 1E-5 System Crab Sample Composite" i Effluent Line' !

Gross Alpha 1E-7 i W Q Sr-89. Sr-90 SE-B Grab Sample Composite

Fe-55 1E-6 l

'- =- - - - , , - - , , ,

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

) ODCM Rev. 19 Page 28 12/97 3.0 CONTROLS ,

4 3.2 RADIOACTIVE LIQUID EFFLUENTS TABLE 13.2-3 (Continued)

TABLE NOTATIONS

a. The LLD is defined as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 951 probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

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

(2.71 + 4. 66ca) (Abt:)

LLD (Composite) = --

E'V 2.22E6 'a

[exp (-14 ti) ) (1-exp (- A A t ) )

l (2. 71 + 4. 66 c3)

LLD (Grab Samples)=

E V 2.22E6 Y (exp - A4ti)

Where:

LLD is the a priori lower limit of detection as defined above

( as microcuries per unit mass or volume),

l ca is the standard deviation of the background counting rate or of the counting rate of blank sample as appropriate (as counts per minute),

E is the counting efficiency, as counts per disintegration, V-is the sample size, in units of mass or volume, 2.22E6 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield, when applicable, A is the radioactive decay constant for the particular radionuclide, and Att for the plant effluents is the elapsed time between the end j' -of the sample collection and the start of sample count.

At: for the plant effluents is the elapsed time between the l -start and the end cf sample collection.

l ODCM Rev. 19 Page 29 l l 12/97 i

3.0 CONTROLS 3.2 RADIOACTIVE LIQUID EFTLUENTS TABLE 13.2-3 (Continued) >

TABLE NOTATIONS l

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

b. A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed to assure representative sampling.

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

The disso3ved and entrained noble gases (gamma emitters) for which the LLD specification applies include the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, Xe-135m, Xe-138. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent l Release Report pursuant to Control I3.6.

d. The term " Composite Sample" means a combination of individual samples obtained at regular intervals over a time period.

Either the volume of each individual sample is proportional to discharge flow rater, or the sampling interval (for constant volume samples) is proportional to flow rates over the time period used to produce the composite.

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

4 f.- Whenever effluent releases are in excess of the monitor's setpoint.

i l

-_ . _ . . - _ . _ _ .._ -__._._.-_...._~...___._.;u.--_..._-_.._.... . , _ . , _ ,

ODCM Ret. 19 ,

Page 30-

. 12/97 3.0 CONTROLS _

3.2. -RADIOACTIVE-LIQUID EFFLUENTS-i _

l 4

I

l 3.2.3 . DOSE DUE TO LIQUID EFFLUENTS j

j The dose or dose commitment to a MEMBER OF THE PUBLIC from 4 radioactive materials in liquid effluents released from the site to UNRESTRICTED 'REAS (See Figure I2.2-la) shall be

! limited:

l a. During any calendar quarter to less than or equal to 3 mrems to the total body and to less than or equal to 10 mrems to any organ, and I b. During any calendar year to less than or equal to 6 i mrems to the total' body and to less than or equal to 20 mrems to any organ, s

APPLICABILITY: At all times, i

i ACTION:

1 With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30

. days, pursuant to Technical Specification 6.9.2, a Special J

Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have'been taken to reduce the releases and the proposed corrective i actions to be taken to assure taat subsequent releases will

. be in compliance with the above limits. This Special Report shall also include the radiological impact on

finished drinking water supplies at the nearest downstream drinking water source.

l SURVEILLANCE REQUIREMENTS i

- 13.2.3-1 Cumulative dose contributions from liquid effluents for

. the currer.t calendar quarter and the current calendar year shall be determined at least once per 31 days.

4 i

9 d

8 f

8,- -- -

,.. , ,...__, ~ . .-m.--, ., -

, ,..<-.y,.. ..,...e.r- .r - v..-. , -

ODCMERev. 19 Page 31 ;

12/97 3.0 CONTROLS

3. 2. PADIOACTIVE ' LIQUID EFFLUENTS l

]-

4 l 3.2.4 LIQUID RADWASTE TREATMENT SYSTEM The liquid radwaste treatment system shall be IN SERVICE and

_ appropriate portions of the system shall be used to reduce '

i the radioactive materials in liquid waste prior to their discharge when the projected doses due to the liquid

effluent, from the site, to UNRESTRICTED AREAS' (See Figure i- l I2.2-la) would exceed 0.12 mrem to the total body or 0.4 mrem to any organ in_a 31-day period.

! APPLICABILITY: At all times.

ACTION

a. With radioactive liquid waste being discharged without

!- treatment and in excess of the above li".its, pursuant l-to Technical Specification 6.9.2, prepare L Special Report which includes the following information:

j 1. Explanation of what liquid radwaste was being .

! discharged without treatment, identification of i'

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

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

3. Summary description of action (s) taken to prevent a recurrence, i b. Submit report to Commission within 30 days.

SURVEILLANCE REQUIREMENTS

3.2.4-1 Lose due to liquid releases from the site to UNRESTRICTED AREAS shall be projected at least once per 31 days.

f i

I 1

1

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

1 ODCM Rev. 19 2 Page.32 12/97 l 4

3.0 CONTROLS ,

4 3.3 GASEOU3 EFFLUENTS >

a l 3. 3.1 . RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluents monitoring instrumentation channels in Table I3.3-1 shall be OPERABLE with their i

alarm / trip setpoints set to ensure that the limits of j' control 13.3.2.a are not exceeded. The alarm / trip setpoints of the applicable channels shall be determined in accordance l with the methodology and parameters in Section II 2.2.

APPLICABILITY: As shown in Table 13.3-1. !

, ACTION:

i a. With a radioactive gaseous effluent monitoring l .-.

instrumentation channel alarm / trip setpoints less l l conservative than required by Section II 2.2, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel or declare the channel inoperable.

i b. With less than the minimum number of radioactive l

gaseous effluent monitoring instrumentation channels

OPERABLE, take the ACTION shown in Table I3.3-1.

l Restore the inoperable instrumentation to OPERABLE i status within the time specified in the ACTION or explain in the next Annual Radioactive Effluent Release Report why this inoperability was not corrected within the time specified.

SURVEILLANCE REQUIREMENTS 3,3.1-1 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by

- performance of the CRANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION AND CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 13.3-2.

i N

. _ . . . . , _ . . , , m...,,,.i ....e. .l_... , . . . - . _ _ . , . ~ . , . . . _ . ~ , . . . . , , , . . .,.....J.-. , m.,_ .. _ - , _ _.

CDCN Rev. 19.

Page 33: !

12/97 3.0- CONTROLS 3.3 GASEOUS EFFLUEllTS >

. _ _ . ....m__ _ . _ _ _

TABLE 13.3-1

[- RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATIC'N

) MINIMUM CHANNELS

. INSTRUMENT OPERABLE APPLICABILITY ACTION i i !

1. SOUTil STACK EFFLUENT MONITORING SYSTEM '[

+

a. Noble Gas Activity Monitor 1 111 l

b. Iodine Sampler 1 + 112 r

+

c. Particulate Sampler 1 112

d. Effluent System Flow Rate Monitor- 1

113 ,

e. Sampler Flow Rate Monitor 1 113 !

2. NORTli STACK EFFLUENT MONITORING SYSTEM + ;

a. Noble-Gas Activity Monitor 1 114 ,

b. Iodine Sampler 1

112 l

c. Particulate Sampler 1 112 !

d. Effluent System Flow Rate Monitor 1 *'

113

e. Sampler Flow Rate Monitor. 1 113 .

3. HOT MAINTENANCE SHOP VENTILATION EXHAUST RADIATION MONITOR

a. Iodine Sampler **

1 112 ,

-b. Particulate Sampler 1 ** 112

c. Effluent System Flow Rate Monitor 1 **' 113 i

d. Sampler Flow Rate Monitor **

1 113 i t

+ The (A or B) North Stack Normal Range Radiation Monitors OR the Wide Range Accident i Monitor (Low Range) .may be used to satisfy requirements for the North Stack Effluent Monitoring f System. !

l l

At all times. '

- During operation of the hot maintenance shop ventilation system. I i

ODCM Rev. 19

-Page 34 ,

12/97 i 3.0 CONTROLS i

3.3 GASEOUS EFFLUENTS i 4 l TADLE 13.3-1(Continued)

TABLE NOTATIONS i ACTION STATEMENTS ACTION 111 -

With less than .he minimum Required Channels (SS Noble Gas) OPERABLE, effluent releases via this pathway may continue for up to 30 days provided grab samples are taken at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and these samples are analyzed for radioactivity by. gamma isotopic analysis within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

-ACTION 112* - With less than the minimum Required Channels (Iodine & Part.) OPERABLE, effluent releases via this pathway may continue for up to 30 days provided samples are continuously collected with auxiliary sampling equipment as required in Table I3.3-3.

IF the Sample Pump is operable, a particulat4 and iodine sample can be obtained; AND the Minimum Channels Operable requirements are satisfied.

ACTION 113* -

With less than the minimum Required Channels (Eff. & Smpl. OPERABLE, effluent releases via NS, SS or HMS Flow Rate) may continue for up to 30 days provided the flow rate is estimated by adding the nominal flow rates indicated in P&ID M-26 for each in-service fan. This shall be documented in the MCR operations Shift Log at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . _.

ACTION 114 -

With less than the min.4mun Required Channels (NS-Noble Gas) OPERABLE,-effluent releases via this pathway may continue for up to 30 days provided grab samples are taken at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and these samples are analyzed for l radioactivity by gamma isotopic analysia within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months '. The Mechanical Vacuum Pumps may-not_be operated while in this action

=stetement.

If release point is theLHot Maintenance Shop, Then secure ventilation because no means exist to-alternately sample the ventilation.

ODCM Rev. 19 Page 35 12/97-3.0. COtITROLS 4 ,

'3.3 GASEOUS EFFLUENTS

.- -=-- . - - - - -. i TABLE I3.3-2 l RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ,

CHANNEL MODES IN WHICH CHANNEL SOURCE CHANNEL FUNCT. SURVEILLANCE

-INSTRUMENT CHECK CHECK CALIBR. TEST- IS REQUIRED I

1. SOUTH STACK EFFLUENT MONITORING SYSTEM ;

a. Noble' Gas Activity Monitor D M R(2) Q(1) * ,

b. Iodine Sampler W(3) N.A. N.A. N.A.

c. Particulate Sampler W(3) h A. N.A. N.A.

D N.A. R *

d. Effluent. System Flow Rate Monitor Q !

e. Sampler Flow Rate Monitor D N.A. R Q i

-2. NORTH STACK. EFFLUENT MONITORING SYSTEM #

a. Noble Gas Activity Monitor D M R(2) O(1) *

b. Iodine Sampler W(3) N.A. N.A. N.A. i

! c. Particulate Sampier W(3) N.A. N.A. N.A. t

d. Ef fluent System Flow Rate Monitor D N.A. R Q !

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

3. HOT MAINTENANCE SHOP VENTILATION EXHAUST RADIATION MONITOR i

a. Iodine Sampler- W(3) N.A. N.A. N.A. '

b. Particulate Sampler . W(3) N.A. N.A. N.A.

c. Effluent System Flow Rate Monitor D N.A. R Q

d. Sampler Flow Rate Monitor D R **

N.A. Q

~

6 Wide Range Accident Monitor (WRAM) surveillance is specified in Technical Specification 3.'3.7.5.

At all times. ;

- During operation of the hot maintenance shop ventilation exhaust system. '

l i .!

l .

. . . - - _ . _ _ _ . - - . . . _ ._ _.m._ . _._.__..m_______.__ _ . _ _ . _ _ _ . . . _ . _ _ _ . - _

ODCM Rev. 19 -j

-Page 36 l 12/97 l-

3.0 CONTROLS 3.3 GASEOUS EFFLUENTS l

TABLE I3.3-2 (Continued)

TABLE NOTATIONS (1) The CRANNEL FUNCTIONAL TEST shall also demonstrate that

- control room alarm annunciation occurs if any of the j following conditions exists:

1. Instruments indicate measured levels above the

! alarm / trip setpoint.

2. Circuit failure.

3. Instrument indicates a downscale failure. ,

, - 4. Instrument controls not set in operate mode.

(2) The initial CRANNEL CALIBRATION shall be perfo:med using one or more of the reference standards certified by the

. National Institute of Standards and Testing (NIST) or using i standards that have been obtained from suppliers that participate in measurement assurance activities with NIST.

-These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that are traceable 1 to the initial calibration shall be used.

'3) The iodine cartridges and particulate filters will be changed and analyzed at least once per 7 days, d

.m_ = - n-- # 4 w% - . , . . im-r v.- ,-,. , - - . . , - - _ . , - . -

,e.-.---- ~-% -.- -

ODCM Rev. 19 Page 37 12/97 3.0 CONTRCLS 3.3 GASEOUS EFFLUENTS

.l 3. 3.2 SITE BOUNDARY DOSE RATE The dose rate due to radioactive materials released in gaseous effluents from the site to areas at or beyond the SITE BOUNDARY (See Figure I2.2-la) shall be limited to:

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

b. For iodine-131, iodine-133, tritium, and for all radionuclides in particulate form with half-lives greater-than 8 days: less than or equal to 1500 mrems/yr to any organ. (Inhalation pathways only.)

APPLICABII ITY : At all times.

ACTION:

With the dose rate (s) axceeding the above limits, immediately restore the release rate to within the above limits.

SURVEILLANCE REQUIREMENTS 3.3.2-1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits.

3.3.2-2 The dose rate due to iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the above limits by obtaining representative samples-and performing analyses in accordance with the sampling and analysis program specified in Table I3.3-3.

_ ._.__._._._.._.~-. _ _____ _ ___ _ _________._ __.__ ___.

4 l

ODCM Rev. 19 i Page.38 i 12/97 I 3.0 CONTROLS 3.3' GASEOUS EFFLUENTS a

TABLE I3.3-3 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGPAM Lower Limit Minimum Type of ot Detection

- Gaseous Release Sampling Analysis Activity (LLD)*

l Point Frequency Frequency Analysis (uCi/M1)

A. North Stack / Continuous" Q- Gross Alpha 1E !

South Stack Comp. Part. Sr-89, Sr-90 - 1E-11 Sample M"'

Grab Smpl. M Noole Gas 1E-4 H-3 1E-6 Continuous d W#

Char. Smpl. 1-131 1E-12 1E-10 I-133 Part. Smpl. Principal Gamma Emitters' 1E-11

Continuous d Continuous Noble Gas I Noble Gas Beta or Gamma 1E-6

Monitor (Based on l: Xe-133)

J

B. Hot Mainten. Continuous" Q Gross Alpha 1E-11 Shop Vent Comp. Part. Sr-89, Sr-90 1E-11 Exhaust #

Smp1.

4 Continuous d W Char. Smp1. I-131 1E I-133 1E-10 Part. Smpl. Principal Gamma 1

Emitters

1E-11 C. Auxiliary-- -Prior to: P I-l'31 1E-6 i Boiler batch Each batch Principal Gamma SE-7

. release Emitters' for burn.

O Gross Alphs 1E-7 Composite Sr-89, Sr-90 5E-8 Sample H 1E-5 Fe-55 1E-6 4

vt-- , 1i,wsg '.--.p . +- e -, + . y n r- , - - - - - - -

.e av - -- t- - >wu

ODCM Rev. 19 Page 39 12/97 3.0 CONTROLS 3.3 GASEOUS EFFLUENTS TABLE I3.3-3 (Continued)

TABLE NOTATIONS

a. The LLD is defined, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95%

probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an after the fact limit for a particular measurement.

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

(2. 71 + 4. 66ca) ( A A t:)

LLD (Composite) =

E V 2.22E6 Y- [exp (- A A ti) ) (1-exp (- A A t:) )

(2. 71 + 4. 66 c3)

LLD (Grab Samples)=

E V 2.22E6 Y (exp - A6 ti)

Where:

LLD is the a priori lower limit of detection as defined above (uCi/cc or uCi/mL) ,

l ca is the standard deviation of the background counting rate or of the counting rate of blank sample as appropriate (as cpm), shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance.

l E is the counting efficiency, as counts per disintegration, V is the sample size, in units of cc or m1, 2.22E6 is the number of dpm/uCi Y is the fractional radiochemical yield, when applicable, A is the radioactive decay constant for the particular radionuclide, and Att for the plant effluents is the elapsed time between the j end of the sample collection and the start of sample count.

.7.. , . . - - y--.,

.I l

ODCM Rev. 19 l Page 40 '

-l 12/97 3.0 CONIROLS

+ J I 3.? GASEOUS EFFLUENTS TABLE I3.3-3 (Continued)

TABLE NOTATIONS l- At2 for the plant effluents is the elapsed time between the start and the end of sample collection, a

1 b. Sampling and analyses shall also be performed following

shutdown, startup, or a THERMAL POWER change exceeding 15% of the RATED THERMAL POWER within a 1-hour oeriod. This requirement does not apply if (1) analys'is show that the DOSE 4- EQUIVALENT I-131 concentration in the primary coolant has not i increased more than a factor of 3; and (2) the main condenser offgas pre-treatment radioactivity monitor shows that effluent activity has not increased more than a factor of 3.

1

c. Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing, or after

removal from sampler. Sampling shall also be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months far at least 7 days following each shutdown, startup or THEhMAL POWER change exceeding 15% of RATED THERMAL POWER in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and analyses completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing. When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are

analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement does not apply if (1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.

E

d. The ratio of the sample flow rate to the sampled stream flow rate shall be known.for the time period covered by each dose or dose rate calculation made in accordance with Controls l I3.3.2, I 3. 3. 3, and I3.3.4.

e. The principal gamma emitters for which the LLD specification

, -applies include the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, Xe-135m and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60,-Zn-65, I-131, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. This list does not_mean that only these nuclides are to be considered. Other gamma peaks which are identifiable, together with the above nuclides, sha]l also be analyzed and reported in the Annual

.] Radioactive Effluent Release Report, pursuant to Control I3.6.

f. Required for the hot maintenance shop ventilation exhaust only during' operation of the hot maintenance shop ventilation exhaust system.

F

,e , .-r ---

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

I-ODCM Rev. 19

- Page 41 1 12/97 1

3.0' CONTROLS 3.? GASEOUS EFFLUENTS m

l3.3.3' DOSE -- NOBLE GASES The air dose due to noble gases released in gaseous l

effluents, from the site to areas at and beyond the SITE 1 BOUNDARY (See Figure I2.2-la) shall be limited to the 4

-following:

a. During any calendar quarter: less than or equal to 10 mrads for gamma radiation and less than or equal to 4 20 mrads for beta radiation, and i b. During any calendar year: less than or equal to

! 20 mrads for gamma radiation and less than or equal to 40 mrads for beta radiation.

i APPLICABILITY: At all times.

ACTION:

With 1 ' calculated air dose from radioactive noble gases in gase as effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report which identifies the cause (s) for exceeding the limit (s) cnd defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

SURVEILLANCE REQUIREMENTS 3.3.3-1 Cumulative dose contributions for the current quarter-and current calendar year for noble gases shall be determined every 31 days.

ODCM Rev. 19 Page 42 12/97-3.0 = CONTROLS 3.3 GASEOUS-EFFLUENTS l 3. 3. 4 DOSE - IODINE - 133, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM The dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from the site to areas at or beyond the SITE SOUNDARY (See Figure 12.2-la) shall be limited to the following:

a. During any calendar quarter: less than or aqual to 15 mrems to any organ and,

b. During any calendar year: less than or equal to 30 mrems to any organ.

APPLICABILITY: At all times.

ACTION: l With the calculated dose from the release of iodine-131, iodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days in gareous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9,2, a Special Report which <

identifies the cause (s) for exceeding the limit and defines the corrective-actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

SURVEILLANCE REQUIREMENTS 3.3.4-1 Cumulative dose contributions _for the current calendar quarter and current calendar year for lodine-131, iodine-133, tritium and radionuclides in particulate form with half-lives greater than 8 days !

shall be determined once per 31 days.

- . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ . _ _ . - . _ _ ._ .. _ _ .m - _ . _ . . . _ _ _ . . _

ODCM Rev. 19

~ Page 43 ;

12/97 l 3.0 CONTROLS L3.3' GASEOUS EFFLUENTS l 3. 3.5 VENTILATION EXHAUST TREATMENT SYSTEM The VENTILATION EXHAUST TREATMENT SYSTEM shall be IN SERVICE .

and appropriate portions of the system shall be used to >

_ reduce radioactive material in gaseous waste prior to their discharge when the projected doses _due to gaseous effluent releases, from the site to areas at and beyond the SITE l- BOUNDARY-(See Figure I2.2-la) would exceed 0.6 mrem to any organ in a 31-day period.

APPLICABILITY: At all times.

ACTION:

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

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

j. inoperability.

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

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

SURVEILLANCE REQUIREMENTS 3.3.5-1 Doses due to gaseous releases from the site to areas at and beyond the SITE BOUNDARY shall be projected-at least once per 31 days.

J' i

I

.,u_.-.-.- - - ,: .. , . . . . ...- - . - - --

ODCM Rev. 19

.PageL44 1

12/97-e 3.0 . CONTROLS 3.3 GASEOUS EFFLUENTS l j l 3.3. 6 VENTING OR PURGING

The VENTING or PURGING of the Mark II containment shall be through the-standby gas ^.teatment system.

t i

APPLICABILITY: . Whenever the containment is vented or purged.*

i. '

ACTION:

With the requirements of the above specification not satisfied, suspend all VENTING and PURGING of the containment.

i

SURVEILLANCE REQUIREMENTS 3.3.6-1 The containment shall be determined to be aligned for

,~

VENTING or PURGING through the standby gas treatment system within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to start of and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during VENTING or PURGING of the containment.

3.3.6-2 Prior to use of the purge system through the standby gas treatment system assure that:

i

a. Both standby gas treatment system trains are OPERABLE whenever the purge system is in use, and

b. Whenever the purge system is in use during OPERATIONAL CONDITION 1 or 2 or 3, only one of the standby gas treatment system trains shall be used to prevent damage to both trains should a LOCA occur (LCO 3.6.5.3 ACTION a applies during this configuration),

i Except after Containment is deinerted and purged while the reactor is in OPCON 4 or 5 OR for the one inch /two inch vent valves to the Reactor i

Enclosure Equipment Compartment Exhaust-. Filters when used for contain ant pressure control and nitrogen make-up operations, i

~

i

--. . . . . . _ , . ,a ,.. . _ , . . . .-.E,.,, --_. - ._. .. _. , _ . . . . . . _ _ -. .L. . . _ _ _ - - - -

ODQ4 Rev.19 Page 45 12/97 3.0 CON 7ROLS 3.3 GASEOUS EFFLUENTS l 3. 3.7 TOTAL DOSE The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC, due to releases of radioactivity and radiation, from uranium fuel cycle sourc's shall be limited to less-than or equal to 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

APPLICABILITY: At all times.

ACTION:

With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding the limits of Controls 13.2.3.a, 13.2.3.b, 13.3.3.a, 13.3.3.b, I3.3.4.a or I3.3.4.b, calculations shall be made including direct radiation contributions from the reactor units and from outside storage tanks to determine whether the above limits l of Control 13.3.7 have been exceeded. If such is the case, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and incitdes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR 20.2203, shall include an analysis that ,

estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from the uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this report. It shall also describe levels of radiation and concentration of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose (s) exceeds the above limits, and if the release condition resulting in l violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

SURVEILLANCE REQUIREMENTS 3.3.7-l_ Cumulative dose contributions from liquid and gaseous effluents shall be determined.

, 3.3.7-2 If the cumulative dose contributions exceed the limits l defined in Control I3.3.7, cumulative' dose contribution from direct radiation from anit_ operation shall be determined.

i I

! ODCM Rev. 19 i Page 46 ;

12/97 i l

3.0 ColiTROLS i

3.3 GASEOUS EFFLUEllTS 1

3.3.0 DOSE - I!!CIllERATIOli OF RADIOACTIVE WASTE OIL

) . :

l Incineration of radioactive waste oil shall be allowed in [

i accordance with the requirements of 10CFR20.2004. The <

exhaust stack of the affected auxiliary boiler will be a

release point for the radioactive effluento. Doses -

i calculated will be based on the radioactive content of the !

j oil prior to incineration. Dose calculated shall meet the !

t limits specified in Controls 13.3.4 and I3.3.5.

' APPLICA131LITY: At all times .

ACTIOlit

! a. With the radioactive content of waste oil not determined as specified in Table I3.3-3, do not incinerate waste oil.

b. With the calculatad dose from the incineration of l

radioactive waste oil exceeding limits specified in ,

Controle 13.3.4 and 13.3.5, do not incinerate waste oil.

4 l

SURVEILLA!!CE REQUIREMEllTS:

3.3.8-1 Dose contributions shall be determined for each batch and summed with other gaseous effluents once per 31 days.

Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined once

per 31 days.

3.3.8-2 Doses due to gaseous releases from the incineration of _

J radioactive waste oil shall be projected at least once per 31 days.

4 4

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ODCM Rev. 19 i Page 47 ;

i 12/97 l t

3.0 CONTROLS ;

i 3.4 RADIOLOGICAL E!NIRONMENTAL MONITORING PROGRAM (REMP) !

~~

i :

l 3. 4.1 MONITORING PROGRAM -;

The monitoring program shall be conducted as specified in !

Table I3.4-1. ,

j APPLICABILITY: At all times. ;

ACTION:

a. With the radi,;ogical environmental menitoring program .

not being conducted as specified in Table 13.4-1, i prepare and submit to the Commission, in the Annual :

2 Radiological Environmental Operating Report per l Control 13.5, a description of the reasons for not t

conducting the program as required and the plans for preventing a recurrence.- ,

b. With the level of radioactivity as the result of plant l effluents in an environmental sampling medium at a specified location exceeding the reporting levels of .

Table I3.4-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days,

, pursuant to Technical Specification 6.9.2, a Special -;

Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose to a MEMBER OF THE PUBLIC is less than the l calendar year limits of Controls 13.2.3, I3.3.3 and 13.3.4. When more than one of the radionuclides in Table 13.4-2 are detected in the sampling medium, this report shall be submitted if:

j- concentration (1) + concentration (2) + , 21.0 reporting level (1) reporting level (2)

When-radionuclides other than those in Table I3.4-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to a MEMBER OF THE.PUBLIC is equal to or greater than the 4

l. calendSr year limits of Controls 13.2.3, 13.3.3 and I3.3.4. This report is not required if the measured level i

of radioactivity was not the result of plant effluents: !

however; in such an event, the_ condition shall be reported and described in the Annual Radiological Environmental Operating Report.

- - . - . - . - . - ._.a-._.--__ -:

1 ODCM Rev. 19 Page 48 !

12/97 !

3.0 CONTROLS r

-3.4 RADIOLOGICAL E!NIRONMENTAL MONITORING PROGPAM (REMP) i

c. With milk or fresh leafy vegetable samples unavailable ,

from one or more of the sample locations required by Table !

13.4-1, identify locations for obtaining replacement i samples and add them to the radiological environmental !

monitoring program within 30 days. The specific locations i from which samples were unavailable may then be deleted J from the monitoring program. Pursuant to Technical '

Specification 6.14, submit as a part of or concurrent with the Annual Radioactive Effluent Release Report, a i complete, legible copy of the entire ODCM, including a _i revised figure (s) and table for the ODCM reflecting the ;

new location (s) .

SURVEILLANCE REQUIREMENTS 3.4.1-1 The radiological environmental monitoring samples shall be.

collected pursuant to Table I3.4-1 from the specific .

locations given in the table and figure (s) in the ODCM and l shall be analyzed pursuant to the requirements of Table -

l 13.4-1, with the detection capabilities required by the Table 13.4-3. ,

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CDCM Rev. 19 Page 50 e i 12/97 3.0 CONTROLS'

~3.4 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) !

--.n-- . -- .

l.. !

TABLE I3.4-1 (Continued) I t

i FADIOLOGICAL ENVIRO?RTENTAL MONITORING PROGRM1 ;

?

NUMBER OF REPRESENTATIVE !

, EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLE LOCATION

COLLECTION FREQ. OF ANALYSIS l

i j 2. AIRBORNE

t Radiciodine and Samples from 5 locations: Continuous sampler Radioiodine canisters:

1 Particulates a.3 samples from close to the operation with sample I-131 analysis

, 3 SITE BOUNDARY locations (in collection weekly, or weekly.

l-different sectors) of the more frequently if highest calculated annual required by dust Particulate Sampler:

j l average ground level I/O. loading". Gross beta radio activity analysis l b.1 sample from the vicinity following filter j community having one of the change:4 ,

j highest calculated annual Gamma isotopic !

l l ground level X/O. analysis

of l 1 sample from a control loca- composite (by

j. tion,.as for example 15-30 km location) at least l distant and in the least pre- quarterly I valent wind direction. !

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ODCM Pev. 19 [

j Page 51 !

J 12/97 l I I l .3. 0 CONTROLS f

3.4 RADIOLOGICAL EINIRONMENTAL MONITORING PROGPR4 (REMP)

_ . - . -- n n - -

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

j TABLE 13.4-1 (Continued) l RADIOLOGICAL EINIRONMENTAL MONITORING PROGPRI !

i l NUMBER OF REPRESENTATIVE I i EXPOSURE PATHWAY SN4PLES AND SAMPLING AND TYPE AND FREQUENCY [

]- AND/OR SAMPLE SAMPLE LOCATION"7 4 COLLECTION FREO. OF ANALYSIS [

3. WATERBORNE

a. Surface' I sample upstream Composite sample Gamma isotcpic analysis' f

. I sample downstream over 1-month monthly. Composite for !

!- period'. tritium analysis

quarterly. !

r i', ;

l b. Ground Samples from 1 or 2 sources Quarterly. Gamma isotcpic" and !

4 only if likely to be affected" tritium analysis l c. Drinking I sample of each on 1 to 3 Monthly. I-131 analysis on each

- of the nearest water supplies (Composite) composite when the dose l that could be affected by its calculated for the con-3 discharge. sumption of the water is j greater than 1 mrem per i I sample from a control year.' Composite for grass

location beta and gamma isotopic'

! analysis monthly. Comp- ;

osite for tritium analysis [

quarterly. !

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GDCM Rev. 19

! Fage 53 12/97 .

3.0 CONTROLS 3.4 ' RADIOLOGICAL ENVIRONMENTAL MONITORING PROGPM4 (REMP)

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

TABLE 13.4-1 (Continued) i RADIOLOGICAL ENVIRONMENTAL MONITORING FROGRN4 NUMBER OF REPRESENTATIVE EXPOSURE PATHWAY SM4PLES MID SM4 FLING AND TYPE MID FREQUENCY !

AND/OR SN4PLE SN4PLE LOCATION

COLLECTION FREO. OF ANALYSIS

4. INGESTION (Continued)

b. Fish and I sample of two recreationally Sample in season, Gamma isotopic" Inverte- important species in vicinity or semiannually analysis on edible i brates of plant discharge area. 1 if they are not portions. i sample of same species in seasonal.

area not influenced by plant i discharge.

1

c. Food Samples of 3 different kinds of Monthly when avail- Gamma isotopic

and ;

. Products broad leaf vegetation grown able, if milk sampling I-131 analysis. i nearest each of 2 different is not performed.

4 offsite locations of highest t j predicted annual average j ground level D/0 if milk sampling is not performed.

, t I sample of each of the similar Monthly when avail- Gamma isotopic' and broad leaf vegetation grown able, if milk sampling I-131 analysis.

15-30 km distance in the least is not performed.

prevalent wind direction if milk sampling is not performed.

t ;

l i

i

ODCM Rev. 19 '

Pgge 54 i 12/97 l

}:

3.0 CONTROLS l

3.4 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 1 i 1

TABLE 13.4-1 (Continued) l l

l TABLE NOTATIONS i

l a. Specific parameters of distance and direction sector from

, the centerline of the two reactors and additional 1 description where pertinent, shall be provided for each and 1 every sample location in Table 13.4-I in a table and

[ figure (s) in the ODCM. Deviations are permitted from the required sampling schedule if specimens are unobtainable due

' to hazardous conditions, seasonal unavailability, 4

malfunction of automatic sampling equipment and other ,

i legitimate reasons. If specimens are unobtainable due to j sampling equipment malfunction, e'rery effort shall be made

, to complete corrective action prior to the end of the next i nampling period. All deviations from the sampling schedule

< shall be documented in the Annual Radiological Environmental j -l Operating Report pursuant to Control 13.5. It is recognized ,

that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the i most desired location or time. In these instances suitable a alternative media and locations may be chosen for the j particular pathway in question and appropriate substitutions ,

j made within 30 days in the radiological environmental

< monitoring program. Pursuant to Technical Specification 6.14, submit as a part of or concurrent with the next Annual Radioactive Effluent Release Report a complete legible copy i of the ODCM including a revised figure (s) and table for the ODCM reflecting the new location (s) .

b. One or more instruments, such as a pressurized ion chamber, i for measuring and recoding dose rate continuously may be i used in place of, or in addition to, integrating dosimeters.

For the purpose of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more i phosphors in a packet are considered as two or more

-dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation. .

c. Methodology for recovery of radiciodine shall be described .

.in=the ODCM.

d. Airborne particulate _ sample filters shall be analyzed for '

gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months _or more after sampling to allow for: radon and thoron daughter decay. If gross beta l' activity;in-air particulate samples is greater that 10 times Lthe yearly mean of control samples, gamma isotopic analysis j shall be performed on the-individual samples.

I F

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ODCM Rev. 19 Page 55 12/97 3.0 CONTROLS 3.4 RADIOLOGICAL E!NIRONMENTAL MONITORING PROGRAM (REMP)

e. Gamma isotopic analysis means the identification and l quantification of gamma-emitting radionuclides that may be I attributable to the effluents from the facility.

f. The " upstream sampic" shall be taken at a distance beyond significant influence of the discharge. The " downstream sample" shall be taken in an area beyond but near the mixing zone.

g. A composite sample is one in which the quantity (aliquot) of. L liquid sampled is proportional to the quantity of flowing l liquid and in which the method of sampling employed result- 6 in a specimen that is representative of the liquid flow. In '

this program composite sample aliquots shall be collected at time intervals that are very short (e.g., hourly) relative .

to the compositing period (e.g., monthly) in order to assure obtaining a representative sample.

h. Groundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination.

1. The dose shall be calculated for the mcximum organ and age :

group.

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4 4

i ODCM Rev. 19

. Page 56 12/97 l 3.0 CO!1TROLS 3.4 RADIOLOGICAL EINIRO!EE!JTAL MO!1ITORI!4G PROGRAM (REMP) 1 TABLE 13.4-2 l REPORTI!1G LEVELS FOk FADIOACTIVITY CO!1CE!!TRATIO!1S I!J E!NIRO!ME!1TAL 4

@D l l Reporting Levels i

4 AIRBORNE FOOD 4

! WATER '

PARTICULATE or FISH MILK l; i PRODUCTS 1 i l A!1ALYSIS (pC1/L) GASES (pCi/m') (pCi/kg, wet) (pCi/L) (pC1/kg, j wet)

H-3 20,000*

Mn-54 1,000 30,000 t

l Fe-59 400 10,000 Co-56 1,000 30,000 4

Co-60 300 10,000 Zn-65 300 20,000 Z r-!Jb- 95 400**

I-131 2 0.9 3 100 2

I Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200** 300

, 1 For drinking water samples. This is a 40 CFR Part 141 value. If no drinking pathway exists, a value of 30,000 pCi/L may be used. ;

- Total for parent and daughter.

l i

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

I ODCM Rev. 19 Page 57 j 12/97 i 3.0 CONTROLS l 3.4 PADIOLOGICAL E!NIRONMENTAL MONITORING PROGRAM (REMP) t TABLE 13.4-3 DETECTION CAPABILITIES FOR EINIRO!TMENTAL SAMPLE A!1ALYSIS"' i Lower limit of Detection lLLD) * "' '

AIRBORNE FOOD WATER PARTICt' LATE or FISH MILK PRODUCTS SEDIMENTS ANALYSIS (pC1/L) GASES (pC1/m') (pCi/kg, (pC1/L) (pCi/kg, (pC1/kg, wet) wet) dry)

Gross Beta 4 0.01 H-3 2,000 Mn-54 15 130 Fe-59 30 260 Co-58,60 15 130 Zn-65 30 260 Zr-95 30 Nb-95 15 I-131 l '"' O.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-140 60 60 -

La-140' 15 15

CDCM Rev. 19 Page 58 12/91 3.0 CO!1TROLS 3.4 3ADIOLOGICAL EliVIRO!'ME!1TAL M0111 TORI!1G PROGRAM (REMP)

TABLE 13.4-3 (Continued)

TABLE liOTATIO!!S (a) This list dose not mean that only these nuclides are to considered. Other peaks that are identifiable at 954 confidence level, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating report pursuant to Control 13.5.

(b) Required detection capabilities for thermoluminescent dosimeters used for environmental measurements are given .in Regulatory Guide 4.13.

(c) The LLD is defined, for purposes of these controls, as the smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 951 probability with only 51 probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurenent system (which may ir.clude radiochemical separation):

l .

4.60cn LLDa E ' V 2.22 Y exp (- Aat)

Where:

LLD is the a priori lower limit of detection as defined above (as picoeuries per unit mess or volume),

l 03 is the standard deviation of the background counting rate or of the counting rate of blank sample as appropriate (as counts per minute),

E-is the' counting efficiency (as counts per disintegration),

V is the sample size (in units of mass or volume),

2.22 is the number of disintegraticns per minute per picoeurie, Y,is the fractional radiochemical- yield-- (when applicable),

Als the radioactive ~ decay constant for the particular radionuclide, and At for the environmental samples is the elapsed time between sample collection (or -end of the sample collection period) and time of counting.

)

l i

ODCl4 Rev. 19 :

Page 59 j j 12/9~7 I i i j 3.0 CONTROLS !

I 3.4 RADIOLOGICAL ENVIRON!4 ENTAL 140NITORING PROGPAli (RE!iP) -

f l TABLE 13.4-3 (Continued) s TABLE NOTATIONS i l i

It should be recognized that the LLD is defined as an a priori I (before the fact) limit representing the capability of a ,

5 measurement system and not as an after the fact limit for a !

i particular measurement. Analyses shall be performed in such a l manner that the stated LLDs will be achieved ander routine i j conditions. Occasionally background fluctuations, unavoidably ;

small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs i unachievable. In such cases, the contributing factors shall !

be identified and described in the Annual Radiological l i l Environmental Operating Report pursuant to Control 13.5. <

i i

(d) LLD for drinking water samples.

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,s._--. _ _ , . , , , . _ . . . _ , . . _ . . . . . , , _ . . , _ . _ _ , _ - _ . _ , _ _ _ _ . _ _ . . . _ , _ , . , _ . . . . . . . _ , . . _ . , . . _ _ _ - . _ ._____..J

ODQ4 Rev. 19 Page 60 12/97 3.0 CONTROLS 3.4 PADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAM (REMP) 3.4.2 LAND USE CENSUS A land use census shall be conducted and shall identify within a distance of 8 km (5 miles) the location (in each of the 16 meteorological sectors) of the nearest garden

of greater than 50 m* (500 ft*) producing broad leaf or vegetables.

APPLICABILITY: At all times.

ACTION:

a. With a land use census identifying a location (s) which yields a calculation dose or dose commitment greater than the values l currently being calculated in Control 13.3.4, identify the

- new location (s) in the next Annual Radioactive Effluent l Release Report, pursuant to Control 13.6.

b. With a land use census-identifying a location (s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a location from which samples are currently being obtained in accordance with Control 13.3.4, add the new location (s) to the radiological environmental monitoring program within 30 days. The sampling location (s), excluding the control station location, having the lowest calculated dose or dose commitment (s) (via the same exposure pathway) may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted. Pursuant to Technical Specification 6.14, submit as a part of or concurrent with in the next Annual Radioactive Effluent Release Report a complete, legible copy of the entire ODCM

-including a revised figure (s)_ and table (s) for the ODCM reflecting the new location (s) .

SURVEILLANCE REQUIREMENTS 3.4.2-1 The land use census shall be conducted during the growing season at least-once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting-local agriculture authorities. The results of the land use census are included in the Annual-Radiological Environmental

-l

Operating Report - pursuant -to Control I3.5. -

'*~ ' Broad leaf v6getation sampling of at least 3 different kinds of vegetation may be performed at the SITE BOUNDARY in each of 2 different dir'ection sectors with the. highest _ predicted.D/Os in l lieu of the garden census.-'Controis-for. broad leaf vegetation sampling in Table I3.4-1 item 4.c. shall be followed, including

- analysis of control samples.

4

1 ODCM Rev. 19 I Page 61 l 12/97 l 3.0 COliTROLS 3.4 RADIOLOGICAL EliVIRO!JMENTAL MONITORI!1G PROGPRf (REMP) 3.4.3 I!1TERIABOPJtTORY COMPARISO!1 PROGRAM l In accordance with LGS Technical Specification 6.8.4.f, analyses shall be performed on radioactive materials .

supplied as part of an Interlaboratory Comparison Program traceable to NIST.

APPLICABILITY: At all times.

t ACTION! >

With analyses not being performed as required above, ,

report the corrective actions taken to prevent a :

recurrence to the Commission in the Annual Radiological i l Environmental Operating Report pursuant to Control I3.5.

SURVEILLANCE REQUIREME!1TS 3.4.3-1 The Interlaboratory Comparison Program shall be l described in the Section II 5.2. A summary of the results shall be included in the Annual-Radiological Environmental Operating Report pursuant to Control I3.5.

i i

9

_,',m-3m.h em.

~ .'~ - c,-,,~e.v.m. . .-~,,rrc,-,-r--.-,--. m.- - , , ', . - - - . . , , - - - - , , - , , . , - - , - - .

ODCM Rev. 19 Page 62 12/97 3.0 CONTROLS

-3.5 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

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

Routine Annual Radiological Environmental Operating Report covering the operation of Unit ) and Unit 2 during the previous calendar year shall be submitted prior to May 1 for each year.

The initial report was submitted prior to May 1 of the year following initial criticality (1984) . A single report is submitted for a multiple unit station. The Annual Radiological Environmental Operating Report shall include summaries, interpretations, and an analysis of trends of the results report period, including a comparison (as appropriate), with preoperational studies, operational controls and previous.

environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment.

The reports shall also include the results of land use census l required by Control 13.4.2. The Annual Radiological Environmental Operating Report shall include the results of all radiological environmental samples and of all environmental radiation measurements taken during the report period pursuant to the locations specified in the tables and figures in the OFFSITE DOSE CALCULATION MANUAL, as well as summarized and tabulated rer11ts of these analyses and measurements in the format of the table in the Radiological Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report. The report shall also include the following: a summary description of the radiological environmental monitoring program and at least two legible maps. One map shall cover stations near the SITE BOUNDARY; a second shall include the more detailed distant stations. Covering all sampling locations keyed to a table giving distances and directions from the centerline of the reactor plant; the results of licensee participation in the l Interlaboratory Comparison Program, required by Control I3.4.3 discussion of all deviations from the Sampling Schedule of Table 13.4-1; and discussion of all analyses in which the LLD required by Table 13.4-3 was not achievable.

4

ODCM Rev. 19 l Page 63 l 12/97 i 3.0 CONTROLS l l

3.6 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT !

-= - -

A Routine Annual Radioactive Effluent Release Report i covering the operation of Unit 1 and Unit 2-during the j previous year shall be submitted in accordance with Tech Spec section 6.9.1.8. The period of the first report shall ,

begin with the date of initial criticality. A single unit i submittal is made for the 2 unit station. The submittal !

combines those sections that are common to all units at the station. The Annual Radioactive Effluent Release Report f shall include a summary of the quantities of radioactive ,

liquid and gaseous effluents and solid waste released from the facility as outlined in Regulatory Guide 1.21,

" Measuring, Evaluation, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power :

Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof. l t

l The Annual Radioactive Effluent Release Report shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either !

in the form of an hour-by-hour listing on magnetic tape of !

wind speed, wind direction and atmospheric stability, and ,

precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, ,

atmospheric stability. The licensee haa the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request. This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from both units during the previous calendar year. This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBER OF THE PUBLIC due to their activities inside the SITE BOUNDARY (Figures I2.2-la and ;

~

12.2-lb) during the report period. All assumptions used in making these assessments shall be included in these reports. l The assessment of radiation doses shall be performed in accordance with the methodology and parameters of the OFFSITE DOSE CALCULATION MANUAL (ODCM).

l The Annual Radioactive Effluent Release R? port shall also include an assessment of radiation doses to the hypothetically highest exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources ,

(including doses from primary effluent pathways and direct '

radiation) for the previous calendar year to show conformance l With 40 CFR Part 190, Environmental Radiation Protection ;

Standards for Nuclear Power Operation. Dose contribution from liquid and-gaseous effluents is calculated-based on i

l i

1 ODCM Rev. 19 j Page 64 12/97

'3. 0 CONTROLS 4 l

3.6 ANNUAL RADIOACTIVE' EFFLUENT RELEASE REPORT .

7

Regulatory Guide 1.109, Rev 1, October 1977 The Annual Radioactive Effluent Release Reports includes the 1 i

following information for each type of solid waste (as I

defined in 10 CFR Part 61) shipped offsite during the report period

1. Total volume, activity and estimated total % error for i each waste type: !

a. Spent resins filter sludges, evaporator bottoms, i etc.

b. Dry comprensible waste, contaminated equipment, ;

i etc.

i c. Irradiated compc'snts, control rcds, etc.

i

d. Others (describe). '

2. _ Activity and percentage of each principle radionuclide f

-(>1%),-for each individual waste type as defined in

1. (a-d) above.

3. The disposition of solid waste shipments (identify the number of shipments, the mode of transport, and the '

f destination). ;

4. The disposition of irradiated fuel shipments (identify the number of shipments, the mode of transport, and the ,

destination.

The Annual Radioactive Effluent Release Report includes a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive material in gaseous and liquid effluents made during-the reporting period.

Changes made during the reporting period to procedure RW-C-100 (formerly the PROCESS CONTROL PROGRAM) and to the ODCM, as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use ~

-l census pursuant to Control I3.4.2. shall-be submitted in the form of a complete, legible copy of the entire ODCM as part -

of or concurrent with the Annual Radiological Effluent :

Release Report for the period of the report in which any change to the ODCM was made.

v -- ,,-er-- ,y-i,.g ,,r,.y,-.wE.,y,

-ry,i--c.-,.,,-,.vmw_,,,.-,.- m. -i y w e ,, e -,-----**----,,,.-,,,,,,rm -

gr...m,wr,-..-~,,,-..,,---.,m

i ODCM Rev. 19 Page 65 j 12/97 ;

3.0 CONTROLS f i

3.6 AlmUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT l t

i i

The Annual Radioactive Effluent Release Reports includes an explanation as to why the inoperability of liquid or gaseous ;

effluent monitoring. instrumentation was not corrected within !

l the time specified in controls I3.2.1 or 13.3.1, :

respectively; and description of the events leading to liquid i holdup tanks or gas storage tanks exceeding the Control- ;

limits. ,

i i

I

+

1 I

?

i i

,,,.-.e-,s.-, ,m .-+,---,e-ce --e,,44,,.,w.m-,,---..%-m-----r..,,-.---,,-., c..-,, - , - - - . .-.. m , .,. m - ..- - ,~,_,c.,-.,,--m-,---,<

l !

1 ODCM Rev. 19 !

Page 66 j 12/97 i 3.0

! CONTROLS t i !

I 3.7 MAJOR CHANGES TO RADICACTIVE WASTE TREATMENT SYSTEMS !

i i j w-1

! l 3.7 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTD4S l

4 i Licensee-initiated major changes to the radioactive waste !

systems (liquid, gaseous, and solid): !

t j a. Shall be reported to the Commission in the Annual l

Radioactive Effluent Release Report for the period in 4 which the change was made effective. The discussion of l 1 each change shall contain: !

4 i 1. A summary of the evaluation that led to the j j determination that the change could be made in ;

4 accordance with 10 CFR 50.59; :

1 1

2. Sufficient detailed informatica to totally support 4 the reason for the change without benefit of 9

additional or supplemental information;

i j'

3. A detailed description of the equipment, +

components, and processes involved and the ;

interface with other plant systems; !

1 -

j 4. An evaluation of the change which shows the ;

predicted releases of radioactjve materials in !

liquid and gaseous effluents and/or quantity of ;

! solid waste that differ from those previously ;

predicted in the license application and amendments thereto; !

. 5. An evaluation of the change which shows the t expected maximum exposures _to individual in the '

UNRESTRICTED AREA and to the general population !

, that differ from those previously estimated in the !

license application and amendments thereto; ;

6. A comparison of the~ predicted releases of .

radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when the changes are to be made; i 7.> lui estimate of _ the exposure to plant - operating _

personnel as a result of the change; and ;

8. Documentation.of the fact that the change was.

revi\ted and ,und acceptable by.the_PORC.

b.- -Shall be review 6 3 1; accepted by the PORC prior to _l

~

implementation. ~

l' I

i

_ ... ,.- ,__..,__-._,_.-__.,..,____..,_.._._.,.,_..__.___;_.___-___.___~

ODCM Rev 19 i Page 67 12/97

! CALCULATION METHODOLOGIES

[

1.0 LIQUID EFFLUENTS !

i 1.1 RADIATION MONITORING INSTRUMENTATION AND CONTROLS The liquid effluent monitoring instrumentation and controls at Limerick for controlling and monitoring normal radioactive material releases in accordance with the Limerick Technical Specifications are summarized as follows:

1) Liquid Radwaste System: The liquid radwaste 31scEarge monitor (RISH 63- Oh'( :s provides an alarm 4

and automatic termination of dioactive material releases from the liquid radwaste system as required l by Technical Specification 6.8.4.d. Additional design features of the liquid radwaste system which prevent inadvertent releases to the environment include 1) redundant discharge valves, 2) single discharge line with loop seal and siphon breaker to eliminate probability of inadvertent discharges, 3) Low Cooling Tower Blowdown flow interlock which isolates the radwaste discharge line.

2) Service Water System The Service Water discharge monitor (RISH10-1K605 AND RISH10-2K605) provides an alarm upon indication of activity in the service _

water system as required by Technical Specification l 6.8.4.d. While the service water system is not a normal release pathway, the monitor provides an indication of potential problems due to excessive leakage of the heat exchangers. In addition, the service water side of the fuci pool heat exchangers is kept at a higher pressure than the shell side to prevent potential radioactive contamination of the I

-service water.

3) RHR Service Water System: The RHR Service Water Radiation (RERSW) Monitors (RISH12-0K619A, RISH12-

-l OK6198)- provide alarm and automatic termination

of radioactive material release from the RHRSW system, l as required by Technical Specification 6.8.4.d.

While the RHRSW system is not a normal release pathway, the monitors provide indication of potential 3 problems due to excessive leakage of the heat exchangers.

Termination of the release is accomplished by auto trip of the.RHRSW pumps and remote manual closure of '

isolation valves.

L r..---v.., --, ., .,e= , , + s u r- -W-+ e-4a+ v m e --n r- et w v Y v w-~ * < - -N w-"- t---v vv - + f a w' W W F <"Wm'-mav-"***"*-'***"* --*~-"*e

- " * - * * - ' ' ' ' ' ' ' * " ' * * * - ' + " - *""

ODCM Rev 19 Page 68 12/97

! CALCUhATION METHODOLOGIES 1.2 LIOUID EFFLUENT MONITOR SETPOINT DETEPRINATION l Per the requirements of Technical Specification 6.8.4.d.1, )

alarm setpoints shall be established for the liquid l effluent monitoring instrumentation to ensure that the l

release concentration limits of Specification 6.8.4.d.2 )

l and 6.8.4.d.3 are met. The concentration of radioactive 1

material released in liquid effluents to UNRESTRICTED AREAS shall be limited to the concentrations specified in l 10 CFR 20, Appendix B, Table II, Column 2 (pre-1994), for i radionuclides other than noble gases and 2.0E-04 pCi/ml !'

for dissolved or entrained noble gases (NUREG 0133).

, t 1.2.1 Radwaste Discharge Monitor and Discharge Flow Rate -

RISH63-0K604 ,

l The setpoint for the liquid radwaste discharge monitor and j flow rate element are determined by the following

equations. The radwaste discharge monitor high-high j alarm / isolation setpoint is evaluated at least monthly i based on isotopes detected in the liquid radwaste sample tanks released during the previous month or on any specific sample tank being released (IC u,~ i ) , the required l l minimum cooling tower blowdown rate during discharge i (CTBD), and average liquid radwaste discharge flow (RR).

4 The flow rate determination is calculated for each release and the MPC traction calculated includes, in the 3-concentration mix, the most recent results from 1) the quarterly composite for SR-89, SR-90 and Fe-55, and 2) the

. monthly composite for H-3, and 3) the sample (s) for l dissolved and entrained noble gases.

i If the calculated setpoint is less than the existing

] l setpoint, the setpoint will be reduced to the new value.

If the calculated setpoint is greater than the existing l setpoint, the setpoint may remain at the lower value or be increased to tne calculated value,

~

The actual setpoint may be reduced to a value less than

[ the calculated setpoint at the discretion of supervision.

If,there were no sample tanks released or no activity j detected during the-previous _ month,- then-the calculation-is performed using release data from the most recent month i

during which isotopes were detected. In_ addition, if there were no sample tanks released during the previous

. l month, supervision-may substitute more restrictive values (e.g., tritium) based on-the plant sampling data.

I' 1.2.1-1_ Setpoint Determination -'RISH63-0K604 The setpoint_for the liquid radwaste discharge monitor is determined by the following equation:

~

t

.,,,,-,-wy,- m-,w.,..m,.--..,.--,w-.v .

..,,-v--,.w-,w-y,.~-w, ,,.,,,,.**r----~m --.-4v -%e v a -- . -,,4-4++%-=,wwe+ e4 . ---*+-n*,- r > - - - +-

--Ada NW. AAm&4A-..am44*% M J G empM*+A h n mM - 2 M . #-le i--ah'- - ^ 'N& + 44m .aM '

A. 4 he h s.'"' ""--'4e4h=_WCMM6S---*h4 - * ' M-AMJ.=mS-.ae*M ALA'41Ah4-i J

E 4

J 1

]

e 4

4 d

i i

1 1

a r

i J

l -

4 1 i

4 4

PART II e

it l CALCULATION METHODOLOGIES I

e !

I 1

s 4

- h 4 :

i I

I i

i ?

5 i

L 1

s v 4

1 0

t f

e I

4 7

d 1-

< .-.~,,r,,, r-,,,n_, , -,~,,,-w_e,,yw_,,,-.~m,4..-,-, . - , . , , - - , .--m.,,......_me- <-.o-,, ._. . .. . . - - - . . .- . . . . . - _. . _, . . . -,...... . -~m-...-~.- - - -

j ODCH Rev 19 '

Page 69 l 12/97 i

CALCUIATION METHODOLOGIES

., m .. . . . _ _ . __

i I I t

l C/%/am s

.I. (S)(RR)/ E(Cs )/ MPCs.,)) (E C,, .)(idt + CTBD) .

+ BKG,am (1-1)

, (lut + C7BD) . _(.9(E)(RR)lECw / MPC,, ~].

4 t

j where: ,

CPMuno = Calculated liquid radwaste discharge monitor (RISH63-OK604)

count rate attributable to the gamma emitting radionuclide, cpm VC4, = the sum of the concentration of the f i identified gamma emitting nuclides

. (pci/ml), .

1 CTBD = the required minimum cooling tower

< blowdown rate during discharge (gpm),

) RR = average liquid radwaste discharge flow (gpm),

BKG am = background count rate of liquid

'- radwaste discharge monitor (CPM),

E = the gross detection efficiency of the liquid ri! waste discharge monitor (pci/ml/ cpm), and S = 2; margin of safety factor to '

assure that the release is terminated prior to 10 CFR 20 limita being exceeded. Included in this factor are errors associated with monitor uncertainty, sampling

. uncertainty, flow rate uncertainty, and the contribution of other.

release paths (Service Water and RHRSW) which are not normally contaminated.

T(Cm m /MPC m,.n,) = the ef f ective gamma MPC ratio for

. the mixture of radionuclides in the ;

liquid radwaste discharge line (unitiess).

e- , 3 +m,me- e.,e e --es- ,--r-we-,-er--ew-+,1---r-wet-,m.----s s--,,--,-.w-,-w-,, -n--,,= r-..--.vm,--,,,-E.- vv--,.----rw-w .4, , , , - - -v -,--------t w-e-,.~wr

l ODQ4 Rev 19 Page 70 l 12/97 CALCULATIO!1 METil0DOLOGIES i

where:

Cp,3

= the concentration of each identified gamma emitting radionuclide i in the liquid effluent (undiluted) ( Ci/ml)

MPCo... = the MPC value corresponding to ;

radionuclide i from 10 CFR 20 i Appendix B, Table II, Column 2 (dissolved and entrained noble i l gases MPC = 2.0E-4pCi/ml)

E (Co..u/MPCn u) = the offective nongamma MPC ratio i for the mixture of radionuclides in the liquid radwaste discharge line (unitiess) where:

C a.o = the concentration of each identified nongamma radionuclide i in tne liquid effluent (undiluted) l (pC1/ml)* (See note below)

MPCn,n = The MPC value corresponding to radionuclide i from 10 CFR 20, Appendix B, Table II, Column 2

NOTE: The concentration mix must include the most recent sample data for 1{-3,- Sr-89, Sr-90, Fe-55 and gross alpha.

1.2.1-2 Flow Rate Determination

' Whenever the value (E (C,/MPC ) >1. 0) , then the setpoint for the 3 liquid radwaste flow rate is determined by the following equation:

CTBD FLOlih 5 (1<2)

S [(C / MFC,)- 1 NOTE: If the value (E (C /MPC1) <1. 0) , then no setpoint 4

determination is required.

where:

t l ODCM Rev 19 7

Page 71 !

l 12/97 l

, CALCULATION METHODOLOGIES l i . - _ _ _ . _ _ _ _ . _ . _ _ _ _ _ _ _

l

PLOWa.o = flow limit for radwaste discharge -

! line (gpm). ,

1 CTBD = required minimum cooling tower blowdown flow l

l l during discharge (gpm).

l l S = 21 margin of safety factor to elsure that the release does not exceed 10 CFR 20 limits.

ECi/MPC1 ) = the effective MPC ratio for the mixture of !

radionuclides in the liquid radwaste discharge line (unitiess) ;

! where: ;

Ci = the concentration of each identified radionuclide i in the liquid effluent ;

l (undiluted) (pCi/ml)* (See note below)

MPC 4 = the MPC value correspcnding to radionuclide i from 10 CFR 20 Appendix B, Table II, Column ,

2, (dissolved and entrained noble gases MPC = ,

2E-4pci/ml) (pCi/ml) .

The concentration mix must include the most recent

NOTE:

sample data for H-3, Sr-89, Sr-90, Fe-55 and dissolved and entrained noble gases.

1.2.2 Service Water Radiation Monitor - RISH10-1K605, -2K605 l The Service Water Radiation Monitor maximum (High-High) setpoint is determined by the following equation. The setpoint is evaluated every 24 months to assure th ' a high background count rate-does not prevent adequat,

-monitor sensitivity in order to meet the requirements of Technical Specifications 6.8.4.d.2 and 6.8.4.d.3.

The high set point shall be administratively controlled to ,

a value that is=less than the High-High set point.

1.2.2-1 Setpoint Determination l _The maximum setpoint (High-High) for the Service Water Radiation Monitor.is determined by the-following equation:

CPM,, =

(S)(MPCca - m) (CF) (1-3)

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

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

l ODCM Rev 19 Page 72 l-12/97 CALCULATION METHODOLOGIES where:

CPMu = Calculated Maximum Service Water Radiation Monitor (RISH12-1K605, l -2K605) count-rate, cpm. ,

l MPCe,:n = MPC limit for Cs-137 2.0E-05 pCi/ml i

CF = Monitor calibration factor - in' cpm /pCi/ml.

l S = Safety-Factor, 0.5 l 1.2. 3 RHR Service Water Monitor -RISH12-OK619A, -0K619B l

The RHR Service Water Radiation Manitor maximum High-High setpoint is determined by the following equation. The setpoint is evaluated every.24 mor t- *o assure that a .

high background count does not prews.. adequate monitor sensitivity in order to n.eet the Technical Specifications l 6.8.4.d.2 and 6.8.4.d.3.

The high set point shall be administrative 1y controlled to a value that is less-than the High-High set point.

1.2.3-1 Setpoint Determination l The setpoint (High-High) for the RHR Service Water Radiation Monitor is determined by the following equation:

CPMwsw =

(S)(MPCco - m)(CF) (1-4) where:

. CPMmcw = Calculated maximum RHR ervice Water Radiation Monitor (RISH12-0K619A, -

l .l OK619B) count rate, cpm.

l MPCe.:n = MPC limit for Cs-137 2.0E-05 pCi/ml

, CF = Monitor ca?.ibration factor - in cpm /pC1/ml.

S = Safety Factor, 0.5 l _l l-1

ODCM Rev 19 Page 73 12/97 CALCULATION METHODOLOGIES 1.3 Liquid Effluent Dose Calculation - 10 CFR 50 l 1. 3.1 Dose to Members of the Public l Control I3.2.3 limits the dose or dose commitment to' MEMBERS OF THE PUBLIC from radioactive materials in liquid effluents from Limerick Generating Station to:

- during any calendar quarter, s 3 mrem to total body s10 F. m to an, organ

- during a., calendar year.

s 6 mrsm to total body l $20 mrem to any organ.

Per Control 13.2.3-1 the cumulative dose contribution from liquid effluents for the current calendar quarter and calendar year shall be determined at least once per 31 days in accordance with the following calculation methods, l The monthly results are accumulated to give the quarterly doses and the quarterly results are accumulated to give the annual doses.

Receptor Dist. Pathways Location (mi) Potable Water Fish Shoreline LGS outfall 0 X X Citizen's Utility 2.5 X X X Phoenixville Water 9.0 X X X Phil. Sub. Water 13.6 X X crew Course 37.8- X 1.3.1-1 Potabh Water Pathway U.,

R , = 1100 GIA, exp(- Ati) (1-5) 1.3.1-2 Fish (Aquatic Fooc) Pathway U"

R., - 1100 g p, 0, B,, Dan exp(- Ato) (1 - 6) 1.3.1-3 Shoreline Deposition' Pathway Eh 5 l h $$ 8f

ODCM Rev 19 Page 74 12/97 CALCULATION METHODOLOGIES where:

Bp i = equilibrium bioaccumulation factor for nuclide I in pathway p, expressed as the ratio of the concentrction in biota, in pCi/kg, to the radionuclide concentration in water, in pCi/ liter (liters /kg)

BIOACCUMULATION FACTORS FOR FRESHWATER FISH (pCi/kg per pCi/ liter)

ELEMENT B ELEMENT B H 9.Ti$1-1 Nb 3. TIN 43 C 4.6E 3 Mo 1.0E 1 Ma 1.0E 2 Tc 1.5E 1 i' 3.0E 3* Ru 1. 0E 1-Cr 2.0E 2 Rh 1.0E 1 Mn 4.0E 2 Te 4.0E 2 Fe 1.0E 2 I 1.5E 1 Co 5.0E 1 Cs 2.0E 3 Ni 1.0E 2 Ba 4.0E O Cu 5.0E 1 La 2.5E 1 Zn 2.0E a Ce 1.0E O Br 4.2E 2 Pr 2.5E 1 Rb 2.0E 3 Nd 2.5E 1 Sr 3.0E 1 W 1.2E 3 Y 2.5E 1 Np 1.0E 1 l Zr 3.3E O Ref: 1) U.S.N.R.C. Reg. Ga'de 1.109, Rev. 1, Table A-1 l 2)* Letter LTR 881209L001, from R.J. Clark, U.S.N.R.C., to G.A. Hunger, Philadelphia Electric Co., December 9, 1988, transmitting evaluation of Limerick ODCM.

D.in = dose factor specific to a given age group a, radionuclide 1, pathway p, and organ j which can be used to calculate radiation dose (1) from an intake of a radionuclide, in mrem /pCi, or (2) from exposure to a given concentration of a radionuclide in sediment, in mrem /hr per pCi/m8 Values are listed in Table II 1-1 and Table II 1-2.

l F = flow rate of liquid effluent from site, cfs.

Mp = dilution factor at point of exposure or at point of withdrawal of drinking water (dimensionless). Values are graphically listed by receptor location in Figures II 1.3.1-1 to II 1.3.1-5. Value will be based on average monthly river flow. M e appears in the

l ODCM Rev 19 Page 75 l- 12/97 CALCULATION METHODOLOGIES. l i equation denominator because river flow graphs display Mp as dil ation flow and not the mixing ratio.

= total rele'ase of nuclide 'i' for tine period 4

Qi (C1).

2 R.g . = total dose for calculation time period to organ j of individuals of age group a from all 1

nuclides i in pathway b (mrem).

, -Ti = radioactive half-life of nuclide 1 (days)..

1 U,p = usage factor specifying exposure time or intake

! rate for an individual of age group a

! associated with pathway p (hr/yr, liters /yr, l or kg/yr) as indicated in the table below.

Pathway Infant Child Teen Adult

! l Fish (Kg/yr) --

6. 9* 16* 21*

Potable Water i

(1/yr) 330* .510' 510' 730'

Shoreline Recreation 90 6 600* 600 5 (hr/yr) --

Ref:

Regulatory Guide 1.109, Rev 1, Table E-5 EROL Tcble 5.2.A-3 l W =

shoreline width factor (dimensionless) = 0.2.

Ref: Regulatory Guide 1.109, Rev. 1.

t3 = time period during which sediment is exposed to contaminated water (1.752E+5 hrs) (midpoint of ,

plant life = 20 ' yrs)

L = radioactive decay constant of-nuclide 'i' (hr")

tp = -12 hours for delay time for water pathway in l

hours to allow for nuclide decay during transport through the water purification plant and the water distribution system, Ref:

Regulatory Guide 1.109, Rev. 1, App. A.

-l t, ' = 24 hates for delay time for fish pathway to allow for nuclide decay during transport

_ through the food chain, as well as during food preparation. Ref: Regulatory Guide 1.109, Rev. 1, App A.

l ODCM Rev 19 Page 76 l

12/97

, CALCULATION METHODOLOGIES tg = 0 hours0 days 0 hours 0 weeks 0 months for delay time for shoreline pathway.

Zero hours are assumed as shoreline activities can occur at the outfall. ,

1100 = factor to convert from Ci/yr per f t'/see to pCi liter.

110,000 = factor te convert f rom Ci/yr per f t'/sec to pCi/ liter and to account for proportionately censtant (100) used in sediment radioactivity model.

1.4 1iquid Effluent Dose Projections l Control 13.2.4 requires that the liquid radwaste treatment system shall be operable and appropriate portions of the systems used to reduce the radioactive materials in liquid waste prior to their discharge when the projected doses due to the liquid effluent to UNRESTRICTED AREAS would exceed:

l 0.12 mrem /31 days to the total body or l 0.4 mrem /31 days to any organ.

l Dose projections are made at least once per 31-days by the following equations:

Deep =

(Det/d)

31 days (1-8)

Dmop =

(Dm /d)

31 days (1-9) where:

Denn a the total body dose projection for the current 31-day period (mrem) .

l Dee = the total body dose to date for the current calendar quarter as determined by equation 1-5,-1-6, and 1-7 (mrem).

D.up = the maximum organ dose projection for the current 31-day period (mrem). .

Dux. = the maximum organ dose to date for the current calendar quarter as determined by equations 1-5, 1-6, and 1-7 (mrem).

ODCM Rev 19 Page 77 12/97 CALCULATION METHODOLOGIES 4

'l d = the actual number of days in the current-calendar quarter at the end of the release l (days).

31 days = the number of days of concern 2.0 GASEOUS EFFLUENTS l 2.1 Radiation Monitoring Instrumentation and Controls

- The gaseous effluent monitoring instrumentation and l controls at Limerick for controlling and monitoring-

radioactive material releases in accordance with the ODCM-Part I are summarized as follows:

1) North Vent (Common): The plant gaseous discharges via tris vent are monitored by two Particulate, Iodine and Gas (PIG) monitors (RY26-075A and RY26-075B) in parallel and by the Wide Range Accident Monitor l (WRAM) (RY26-076). The PIGS have separate Particulate, Iodine, and Gas sampling and monitoring

, l channels but the Controls require only particulate and iodine sampling and noble gas monitoring. The WRAM has extended range (via three channels) noble gas monitoring and particulate and iodine sampling capability. In addition, the WRAM provides an l isolation (Group 6A) of the large Drywell Purge and Vent valves, c

2) South Vent (one per unit): The plant gaseous discharges via each South Vent are monitored by two redundant PIG monitors (RY26-285A,B). As is the case of the North Vent, each. PIG'has separate particulate, iodine, and gas sampling and monitoring channels but l the Controls require only particulate and iodine sampling with gas monitoring.

3) Hot Maintenance Shop (Common): Due to the composition of the radioactive materials in the effluent steam (i.e., very-low potential for noble gas), this release point is sampled by a particulate and iodine (P&I) monitor (RY26-025). The P&I monitor has a separate particulate and iedine sampling and l monitoring channels but Controls require only particulate-and iodine sampling.

4) Auxiliary Boilers (Common) .: Waste oil with some amount of radioactive particulate content may be burned in the site auxiliary boilers, as allowed by 10CFR20,2004. In this case, the exhaust stack of the affected auxiliary boiler will be a release-point for radioactive effluents. Doses calculated will be based on'the radioactive content of the oil. sampled

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

ODCM Rev 19 Page 78

,12/97 CALCULATION METHODOLOGIES

.pritr to incineration. The radioactive effluent will l be summed with other effluents from the site and reported to the commission in the Annual Effluent' l Radiological Release Report.

2.2 GASEOUS EFFLUENT MONITOR SETPOINT DETERMINATION l Control I3.3.1 requires that an alarm setpoint be established for the noble gas effluent monitoring channels j (RY2 6 07 5A, B, ; RY2 6-18 5A, B, ; RY2 6-285A, B, ; and RY2 6-07 6) to ensure that the release rate of radioactive materials l does not exceed the limits of Control I3.3.2.a, which corresponds to a dose rate at the SITE BOUNDARY of 500 l mrem /yr to the total body or 3000 mrem /yr to the skin.

l Control limits are expressed in terms of dose rate, while '

the instruments waich monitor affluents produce data in units of concentration or release rate. It is therefore necessary to identify the isotopes and calculate the corresponding release rate which will result in the dose rate limit being reached at the site boundary. This calculation is made more complex by the use of multiple release points at LGS.

Calculation Bases The alarm setpoint calculation is performed monthly and is based on analytical results of grab samples from the appropriate release point. The concentration of each identified radionuclide in the grab tamples is determined, and the data is used to perform a setpoint calculation for that nuclide mix and release point. ,

l The highest calculated annual average concentration (x/Q) for an area at or beyond the site boundary (1.1E-05 sec/m', NE sector) is used in the setpoint calculation.

Maximum flow rates through the North anc South vents are used in alarm setpoint calculations. This is necessary since flow can vary. By using maximum values, any flow less than the maximum will assure that the monitor will alarm before release rate limits are exceeded.

'I The fractional-contribution of noble gas is calculated 'or each release point. The f ractional co itribution to

.whole body and skin dose rates due to noble gases for .ae north stack and south stack vents are calculated by taking the product of this fraction and the limiting release rate.. A comparison of the release rate for whole body and skin dose rates due to noble gas release is made to determine if the whole body or skin dose limit will be -

most. restrictive. It is expected that the whole body limit =will always be most restrictive, but the comparison

ODCM Rev 19 Page 79 12/97 CALCULATION METHODOLOGIES l is necessary to assure compliance with Control I3.3.2.a.

The sure of the contr_butions f rom each ralease point, l independently calculated for noble gases, will equal the maximum instantaneous release rate allowed from the site.

I 2.2.1 North Vent Noble Gas Effluent Monitors - RY26-075A-3, l RY26-075B-3, AND RY26-076-2 The North Vent Noble Gas Effluent monitor high-high sef. point is calculated monthly based on the grab sample l results performed in accordance with Table I3.3-3.. Release point grab samples may not identify any radionuclides. In l tais situation, use the results of the last grab sample uhich identified radionuclides or use the default setpoint which is based on expected concentration ratios as reported in the UFSAR. If any calculated alarm setpoint is less than the existing monitor setpoint, the setpoint will ba reduced to the new value. If the calculated -

setpoint value is greater than the existing value, the l setpoint may remain at the lower value or be increased to the new valta.

2.2.1-1_ Setpofnt Determination The high-High setpoint is calculated per equation 2-1 or 2.2. The High-High setpoint for the North Vent Noble Gas Effluent Monitor is set at or below the lesser of the NVSP (Hi-Hi) wus OR NVSP (Hi-Hi) wur value.

(per equations 2-1 or 2-2)

The high set point shall be administrative 1y controlled to a value that is less than the High-High set point.

l'Fmo1[500][E Ce]

NI'SP(Hi-Hiswa (2 -1) s ((3.471E9]E[(Ce)(K)]

I

[VFme][3000]IE Ce] (y.yy NVSP(Hi-Hi)ma S [3.471E9]E[(Ca)(L + 1.11AC)]

where:

l NVSP (Hi-Hi) scu = North Vent High Setpoint - Noble Gas Skin ( Ci/cc).

ODCM Rev 19 I

Page 80 12/97 CALCULATION METHODOLOGIES INSP (Hi-Hi) saws = North Vent High-High Setpoint - Noble Gas Whole Body (pCi/cc).

VFmm =

Fractional contribution to site boundary noble gas dose rate from the l North Vent. (unitless).

500 = Total body dose rate limit (mrem /yr) 3000 = Skin Dose rate limit (mrem /yr)

ECan = Total noble gas activity from North Vent grab sample (pCi/cc) l 3.471E9 = Conversion factor (pCi)(cc)

.m'XCi),

(

= (1.1E - 3 sec/ m')(IE6 pCi / pCi)(668,450 cfm)(1/ 60 min / sec)(2.832E4 cc / ft')

(2-3) where:

l 1.1E-5 sec/m' = highest annual average X/Q (NE Sector) 1E6 p;i/pCi = units conversion j 668,450 cfm =

maximum North Vent flow rate for two unit operation ,

7 1/60 min /sec =

units conversion 2.832E4 cc/ft 3 =

units conversion Cuu = concentration of noble gas nuclide i as determined by radioanalysis of North Vent grab sample (pCi/cc)

K = Total body dose conversion factor for noble gas nuclide i (mrem /yr per 3

j pCi/m, from Table II 2-1).

L i

=

3 eta skin dose conversion factor noble3 gas nuclide i (mrem /yr per l pCim, from Table II 2-1).

__ . ~ .um__--..----:-..-.- --

ODCM Rev 19 Page 81 12/97 i

CALCULATION METHODOLOGIES d

M i

= Gamma air dose conversion factor for noble gas nuclide 1 (mrad /yr per l pCi /m', From Table II 2-1).

. 1.11 = The average ratio of tissue to air energy absorption coefficients (mrem / mrad) (Ref: Regulatory Guide

. 1.109, Section 2.0).

2.2.2 South Vent Noble Gas Effluent Monitors -RY26-185A-3, RY26185B-3, RY26-285A-3, AED RY26-285B-3 Each unit's South Vent Noble Gas Effluent monitor High-High setpoint is calculated monthly based on the grab sample results performed in accordance with Table 13.3-3.

Release point grab samples may not identify any radionuclides. In this situation, use the results of the last grab sample which identified radionucl.4de or use the

defaul.t setpoint which is based on expected concentration ratios as reported in the UFSAR. If any calculated alarm setpoint is less than the existing monitor setpoint, the setpoint will be reduced to the new value. If the calculated setpoint value is greater than the existing l value, the setpoint may remain at the lower value, or be increased to the new value.

2,2.2-1 Setpoint determination 4

, The High-High setpoint for the South Vent Nucle Gas Effluent Monitor is set at the lesser of the SVSPIHi-Hi) sme and SVSP (Hi-H1) na3x value. SVSP(Hi-Hi)w2e and SVS P (Hi-Hi) ncsg are calculated for each unit's South Vent.

The High-High setpoint is calculated per equation 2-4 or 2-5. .

The high set point shall be administrative 1y controlled to a value that is less than the High-High set point.

[lFswa][500][E C.]

(2 - 4)

SI'SP(Hi-Hi),, s [1.2149E9]E[(C.)(Ki)]

[lTsmo][3000][E C,] ~

Hi-Him s [1.2149E9]E[(C )(L,'i.11M,)]

ODCM Rev 19 Page 82

'12/97 CALCULATION METHODOLOGIES whero:

l SVSP(H2-Hi)uws = South Vent High-High Setpoint - Noble Gas Whole Body (pCi/cc) l SVSP(Hi-Hi) sg = South Vent High-High Setpoint - Noble f Gas Skin (pCi/cc)

VFamo = Fractional contribution to site

.bcundary noble gas dose rate from the

! Unit's South Vent. (unitiess) 500 = Total body dose rate limit (mrem /yr) 3000 = Skin dose rate limit (mrem /yr)

EC t ., = Total noble gas activity from each unit South Vent grab sample (pCi/cc).

C1 ,, = concentration of noble gas nuclide i determined by radioanalysis of South Vent grab sample ( Ci/cc)

Kt = Total body dose conversion factor for noble gas nuclide i (mrem /yr per.

l pC1/m 3 , from Table II 2-1).

L 1

= Beta skin dose conversion factor noble gas nuclide 1 (mrem /yr per pC1/m 3 , From Table II 2-1). '

( l Mi = Gamma air dose conversion factor for noble gas nuclide i (mrad /yr per

_l pCi/m 3 , From Table II 2-1).

1.11 = The average ratio of tissue to air energy absorption coefficients (mrem / mrad) (Ref: Regulatory Guide 1.109, Section 2.0) 1.2149E9 = Conversion factor

~ (pCi)(cc) '

_( m')(pCi)_

-(1.1E -5 secim')(1E6pCi / pCi)(234,000 cfm)(1/ 60 min / sec)(2.83E + 4 cc /ft') (2 - 6)

-.- . - . .. .-. . - - . -- - - . . ~ - .- -

ODCM Rev 19 Page 83 12/97 CALCULATION METHODOLOGIES wherc:

l 1.lE-5 sec/m' = highest annual average x/O (NE Sector) 1E6 pCi/pCi = units conversion 234,000 cfm = maximum South Vent flow rate 1/60 min /sec = units conversion

2. 832E4 cc/f t' = units conversion 2.2.3 Noble Gas Effluent Fractional Contribution The three release points will be partitioned such that the sum does not exceed 100 percent of the limit (500 mrem /yr whole body noble gas, 3000 mrem /yr, skin noble gas.) The default fraction will be set at 80 percent for the North Vent, 10 percent for the Unit-1 South Vent and 10 percent for the Unit-2 South Vent.

These percentages can vary should operational concentrations warrant such change. However, the sum of the percentages shall be equal to or less than 100%. The following relationship shall be met:

VFm + VEssm + VFasm S 1 (2 ~ 7) where:

VFmy, = fractional contribution to site boundary noble gas total body dose rate from the North Vent (unitless) .

VFuca = fractional contribution to site boundary noble gas total body dose rate from the Unit 1 South Vent (unitless).

VFunn = fractional contribution to site boundary noble gas total body dose rate from the Unit 2 South Vent (unitless).

I 2.2.4 Noble _ , Effluent Default Setpoint This methodology may be used whec crab sample results from either the North Vent or the Sou'n tant do not identify any radionuclides. This methodology is based on expected

]- release-concentration ratios as outlined in Section 11.3 of the Limerick UFSAR. .

ODCM Rev 19 l Page 84 -

/

4 12/97 CALCULATION METHOD 0LOGIES -

'2.2.4-1 North Vent Noble Gas Monitors (RY26-075A-3 and RY26-075B-3). The default High-High setpoint for-the North-Vent Noble Gas Effluent Monitor is set at or

, below the NVSP (Hi-Hi) man value.

NVSP(Hi-- H/)uco(3.471E9][4.37E s [8.00E-1][500][1.3IE-6)

- 9)

~

l NVSP (Hi-Hi) m:0 < 3.45E-5 pCi/cc where:

NVSP (Hi-Hi) nce = Da'ault North Vent High-High Setpoint

- Noble Gas Whole Body (pCi/cc) 8.00E-1 = Default fractional contribution to site boundary noble gas total body dose rate from the North Vent (unitless) 500 = Total body dose rate limit (mrem /yr) l 1.31E-6 = Total noble gas concentration from North Vent (pCi/cc) l Ref: a) Based on UFS.iR Table 11.3-1.

b) Based on maximum North Vent l flow of 668,450 cfm l 3.471E9 = Conversion Factor

. (pCl)(cc) .

, (m')(pCi)3 4.37E-9 = Summation of the North Vent

-concentration of noble gas nuclide i multiplied by the corresponding whole body dose factor.

I(pCl)(mrem)(m')^

_ (cc)(yr)(pCi) _

l Ref: a) Based on UFSAR Table 11.3-1.

b) Based on maximum North Vent flow of-668,450 cfm.

c) Table II 2-1.

l

l ODCM Rev 19 '

Page 85 l 12/97 l 4

CALCULATION METHODOLOGIES 2.2.4-2 South Vent Noble Gas Monitors (RY26-185A-3, RY26-285A-3, RY26-185B-3, and RY26-285b-3). The default High-High setpoint for each Unit's South Vent Noble Gas Effluent Monitor is set at or below the SVSP(Hi-Hi)sco value.

SVSP(Hi- Hs)mo s [1.00E-1][500ll.025-7]

(2 - 9)

[12149E9][2.7IE-10]

1 SVSP (Hi-Hi) sco <,1.54E-5 pCi/cc j where:

l SVSP (Hi-Hi) sce = Default South Vent Setpoint - Noble Gas (pCI/cc) l 1.00E-1 = Default fractional contribution to site boundary noble gas total body dose rate from the South Vent (unitless) l 500 = Total body dose rate limit (mrem /yr) 1.02E-7 = Total noble gas concentration from South Vent (pCi/cc)

Ref: a) Based UFSAR Table 11.3-1 b) Based on maximum South Vent flow of 234,000 cfm.

1.2149E9 = Conversion factor

. (pCi)(cc)

,_( m')(pCi)_

l 2.71E-10 = Summation of the South Vent concentration of noble gas nuclide i multiplied by the corresponding whole body dose factor.

~ ~

(pCi) (mrem) (m')

(cc) (yr) (pci) _

Ref: a) Based on UFSAR Table 11.3-1.

b) Based on maximum South Vent flow of 234,000 cfm.

c) Table II 2-1.

ODCM Rev 19 Page'86 '

12/97 l CALCULATION METHODOLOGIES 2.2.5 Wide Range Accident Monitor Noble Gas Ef fluent Monitor (RIX-26-076-4)

The Wide Range Accident Monitor (WRAM) noble gas total effluent channel displays the North Vent noble gas release rate. This monitor has Main Control Room Annunciation as well as a group 6A isolation function on the primary containment purge and vent valves. The isolation setpoint value of 52.1 pCi/cc specified in Technical Specification j 3.3.2-2 is based on the accident dose limits for i containment purge during an accident (Ref: UFSAR Section _

l.13). For routine operations the total effluent high and high-high setpoints are based upon the methodology of Sections II 2.2.5-1 and II 2.2.5-2. The setpoint units are in microcuries per second using the two unit maximum '

l North Vent flow rate of 668,450 scfm. The total effluent channel High-High setpoint is set at a value less than or equal to ten times the High setpoint (not to exceed the 2.1 pCi/cc equiva' lent using the two-unit maximum North Vent flow rate). These values are always more conservative than the Technical Specification Table 3.3.2-2 required value of s 2.lpC1/cc.

If the calculated setpoint value is less than the existing monitor setpoint, the setpoint will be reduced to the new value. If the calculated setpoint is greater than the existing value, the setpoint may remain at the lower l value, or be increased to the new value.

2.2.5-1 Routine Operations High Setpoint Determination For routine operations, the High setpoint for the WRAM Noble Gas Total. Effluent Channel is set at or below the lesser of the NVSP (Hi-Hi)mus or NVSP(Hi-Hi) csx value when activity is detected. When no activity is detected, the High setpoint is set at or below the NVSP(Hi-Hi)mm. This setpoint is calculated to ensure compliance with Control I3.3.2.a.

l The setpoint values are converted from pCi/cc to pCi/sec using the maximum two-unit North Vent flow rate: ,

= [NVSP(Hi-Hi),ws or wao] [3.155E8] (2-10)

-l NVSPnwa

l. NVSPuss- = [NVSP (Hi-Hi) m3sg) [3.155E8) (2-11) where:

= WRAM total eftluent channel North Vent NVSPum High Setpoint - Noble Gas Whole Body (pCi/sec).

l ODCM Rev 19 Page 87

( l 12/97 CALCUIATION METHODOLOGIES NVSPuu = WPAM total effluent channel North Vent High Setpoint - Noble Gas Skin (pC1/sec).

NVSP (Hi-Hi) me = North Vent High-High Setpoint - Noble or um Gas Whole Body (pCi/cc) from equation 2-1 or 2-8.

NVSP(Hi-Hilmu = North Vent High-High Setpoint - Noble Gas Skin (pCi/cc) from equation 2-2.

l 3.155E8 = Conversion factor (cc/sec).

l

= (668,450 scfm) (1/60 min /sec) (2.832E4 cc/f t') (2-12) 2.2.5-2 Routine Operations High-High Setpoint Determination For routine operations, the High-High setpoint for the WPAM Noble Gas total effluent channel is set at or below ten times the lesser of the routine operations NVSPnw or NVSPuu value.

l NVHPun = [NVSPun) [10] (2-13) l NVHPusa = [NVSPusa) [10] (2 - 14 )

where:

NVHPms = WBAM total effluent channel North Vent High-High Setpoint Noble Gas Whole Body (pCi/sec).

NVHPuu =

WRAM total effluent channel North Vent High-High Setpoint Noble Gas Skin (pci/sec).

NVSPun = WPAM total effluent channel North Vent High Setpoint - Noble Gas Whole Body (pCi/sec) from equation 2-10.

NVSPna = WPAM total effluent channel North Vent Setpoint - Noble Gas Skin (pCi/sec) from equation 2-11.

10 = multiplication factor to calculate High-High value (unitless)

l ODCM Rev 19 Page 88 12/97 CALCULATION METHODOLOGIES 2.3- . Gaseous Effluent Dose Evaluation l ' Monthly dose calculations are performed based on limiting sector average-annual meteorological dispercion parameters._For the noble gas monthly dose calculation, effluent release data are based on the latest grab sample l analysis for radionuclide composition. For the iodine and particulate monthly dose calculations, the effluent release radionuclide composition and release activity are l based on weekly continuous samples.

The quarterly dose calculations are a summation of the applicable monthly dose results.

I_

2.3.1 Site Boundary Dose Rate - Noble Gases

=l Co:ttral 13.3.2.a limits the dose rate at the SITE BOUNDARY due to noble gas releases to s500 mrem /yr total body and

$3000 mrem /yr skin. Radiation monitor alarm setpoints are established to ensure that these release limits are not exceeded.

Simultaneous releases from the North and South Vents are considered in evaluating compliance with the release rate l -limits of Control I3.3.2.a following any releases exceeding the alarm setpoints. Monitor indications (readings) are averaged over time periods not to exceed 60 minutes.

NOTE: For administrative purposes, more conservative alarm setpoints-than those required to meet 10 CFR 20-Dose Rate limits are imposed. However, conditions exceeding these more limiting alarm setpoints do not necessarily indicate radioactive material-release rates exceeding the dose limits of

l. Control I3.3.2.a. Provided actual releases do not result in radiation monitor indications exceeding values based on the dose rate limits of l' Control I3.3.2.a, no further analysis are required for demonstrating compliance with the limits of l Control I3.3.2.a.

In the event of a noble-gas effluent release exceeding-the setpoint value specified in Sections II 2.2.1 or II 2.2.2, the site boundary dose rate from the release is calculated using the methodology stated below. This methodology is based on worst sector (NE) annual average meteorological dispersion but, if further refinement is required to meet the requirements of ,

l- Control I3.3.2.a, actual meteorological-data from l the time period of concern may be used to calculate !

actual meteorological dispersion. I

ODCM Rev 19 Page 89 12/97 CALCULATION METHODOLOGIES Dr, = y/G (lE + 06) GX, (2 - 15)

~= .

Dr = y/O (IE + 06) [ (L, + 1.1IM)G,' (2 - 16)

. sel .

lwhere:

Du, = Total Body Plume Dose Rate (mrem /yr)

Dy = Skin Plume Dose Rate (mrem /yr)

X/O = 1.1E-05 highest annual average relative concentration (NE Sector) (sec/m*)

, d, = The release rate of noble gas nuclide I from all vent releases averaged over one hour (uC1/sec)

Kt = Total body dose factor for noble gas nuclide l 1. Values are listed in Table II 2-1.

3.

mrem - m

. pCi - 3r _

L = Skin dose factor for the beta contribution-for noble gas nuclide 1. Values are listed l in Table II 2-1.

3.

Mi t.11 - m

. pCi - yr _

1.11 = the average ratio of tissue to air energy absorption coefficients (mrem / mrad) (Ref:

l Regulatory Guide 1.109, Section 2.)

l M t

= Gamma air dose factor for noble gas nuclide l 1. Values are listed in Table II 2-1.

~ mrad - m' ~

. pCi - yr _

l lE+06 = Units conversion pCi/ Ci

ODCM Rev 19 Page 90 12/97 l 1

CALCULATION METHODOLOGIES 2.3.2 Site Boundary Dose Rate - Radiciodine and Particulates Control 13.3.2.b limits the dose rate to $1500 mrem /yr to any organ (inhalation pathways only) for I-131, I-133, Tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents.

l Compliance with Control 13.3.2.b is determined monthly.

Simultaneous releases from the North and South Vents are considered in evaluating compliance with the release rate limits of Control I3.3.2.b. Release activity is based upon the results of the weekly continuous sample analysis performed in accordance with Table 13.3-3.

Dm.y/G.mfR,d (2 - 17)

,o where:

Dm = Inhalation dose rate (mrem /yr) x/Qa g = 1.0E-05 nighest average annual depleted x/Q (NE Sector) (sec/m 3)

R1 = Dose factor for radionuclides other than noble gases for the inhalation pathway only (mrem /yr/pci/m') Values are listed in Table II 2-2.

h = The release rate of radionuclide i other than

) noble gases from all vent releases (pCi/s).

2.3.3 Noble Gas Air Doses l Control I3.3.3 limits the air dose due to noble gases released in gaseous effluents (from both reactor units) to areas at or beyond the SITE BOUNDARY to:

s 10 mr'ad gamma for any quarter s 20 mrad beta for any quarter s .70 mrad gamma during any calendar year s 40 mrad beta during any calendar year l As required by Control I3.3.3-1 Surveillance Requirement, these doses are calculated at least once per 31 days using the results of the most recent grab samples for isotopic l corposition performed in accordance with Table I3.3-3. The monthly dose calculation is performed using the most limiting average annual meteorological dispersion values.

The quarterly doses are based on the summation of the' l applicable monthly results. The monthly dose calculations are performed in accordance with the methodology below.

1

ODCM Rev 19-Page 91 12/97 CALCULATION METHODOLOGIES Dra = (3.17E - 8)(1,00E + 6) y GT M,0, (2 - 18)

Dw = (3.17E-8)(1.00E + 6)y G ,N,G, (2 - 19) '

l where:

Dgn = Gamma air dose from noble gas releases in MRAD Dpa u = Beta air dose from noble gas release in MPAD 3.17E-8 = Units conversion [ year /sec) 1.00E+6 = Units conversion pCi/pCi y./ O = 1.1E-05, Highest average annual relative concentration (NE Sector) in sec/m 3 Q1

= The release of noble gas radionuclides, 1, from all vents in pCi. Releases shall be cumulative over the period of interest.

l Nt = Gamma air dose factor for noble gas nuclide 1. Values are listed in Table l II 2-1.

~ mrad - m' ~

.PCi - >r .

N i

= Beta air dose factor for noble gas nuclide 1. Values are listed in Table II 2-1.

~ mrad - m' '

. pCi - >r _

l 2. 3. 4 Radiciodine and Particulate Dose Calculations

_l Control I3.3.4 limits the dose (from both reactor-units) to a MEMBER OF THE PUBLIC from I-131, I-133, Tritium, and all radionuclides in particulate form with half-lives greater than 8 days;in gaseous effluents released to areas at or beyond the SITE BOUNDARY to:

< 15 mrem to any organ during any calendar quarter 1 30 mrem to any organ during any calendar year

l ODCM Rev 19 Page 92 l 12/97 CALCULATION METHODOLOGIES l As required by Control 13.3.4-1 Surveillance Requirement, these doses are calculated at least once per 31 days using the results of the weekly continuous sample analysis performed in accordance with Table 13.3-3. The monthly dose calculation is porformed using the most limiting average annual meteorological dispersion values. The quarterly doses are based on the summation of the applicable monthly results. The monthly dose calculations are performed in accordance with the methodology below.

Total organ dose is obtained by the summation of the l organ dose from each pathway.

2.3.4-1 Ground Pathway Dow - (3.17E-08) D/Q R,Q, (2 - 20) 2.3.4-2 Vegetation, Meat, Cow Milk, and Goat Milk Pathway

~ ~

2 a Dna = 3.17E - 08 y/G[ R,0, + D/GZ R,G. (2 - 21)

.., o.s .

2.3.4-3 Inhalatio_n Pathway Daa = 317E - 08 y/GE R,G, + y/gog[ R,G, (2 - 22)

..i ,.3 .

l where:

D uxa = dose from ground pathway due to release of particulates and iodines (rem).

Dvra = dose from-vegetation, meat, cow milk, and goat milk, pathways due to releases of particulates, iodines, and tritium (rem).

l Duo = dose from inhalation pathway due to i release of particulates, ' iodines, and l tritium (rem).

l 3.17E-8 = units conversion (year /sec).

i=1 = Tritium, H' l i=2 = Carbon 14, C" l

i=3 thru n = all other isotopes (particulate and iodine)

=

Q1 the release of nuclide i from all vents in pCi. Releases shall be cumulative over the time period of interest.

1 ODCM Rev 19 Page 93 12/97 CALCULATION METHODOLOGIEa .

R1 = dose factor for organ type, age group, and pathway (for radionuclides other than noble gas); dose factors are calculated based on the methodology given in NUREG-0133. - values of Ri are provided in Table II 2-2.

X/O = 1.lE-05 highest average annual X/O (NE sector) ( s /m*)

x/Qo.p = 1.0E-05 highest average depleted x/O (NE sector) (s/m )

D/Q = 1.82E-9 highest average annual deposition (ESE Sector) (1/m* )

2.3.5 Incineration of Contaminated 011 2.3.5.1 Site Boundary Dose Rate ,

The dose rate (mrem /yr) to any organ (inhalation pathway only) for I-131, I-133, Tritium, and all radionuclides in particulate form with half-lives greater than eight (8) days from the incineration of contaminated oil from the auxiliary boiler shall be calculated in accordance with the methodology below.

The dose rate from radioactive particulate release shall be determined by either of two methods. Method (a), total instantaneous release, assumes that the total activity contained in the contaminated oil is released in the first minute of incineration. Method

03) uses the activity release over the entire time of incineration.

For normal operations, it is assumed that Method (a) will be used, since the total activity from the waste oil is' expected to contribute an insignificant dose compared to the annual limits. However, in_the event that the dose rate calculated is higher than administrative or regulatory limits, then Method 03) may be used because it uses the actual time of release,-

which results in a more accurate dose and dose rate calculated.

Since the_auxilitry boiler stacks are at approximately the same height as the reactor vents and discharge from the auxiliary _ boiler will also be heated, the use of the reactor vent dispersion values' for the calculations is considered conservative.

a l

l l ODCM Rev 19 l Page 94 j l 12/97 CALCULATION METHODOLOGIES

_ _ - ---_-------n._..-- -.

l a. Instantaneous Release Rate Method 5 -

60 (2 - 23) where:

[L = The release rate of radionuclide, i, in gaseous effluents from the auxiliary stack releases, pCi/s.

Cu = activity concentration measured in oil for nuclide, i, in pCi/ml.

3785 = milliliters per gallon.

Z = gallons of oil consumed.

60 = number of seconds used for release.

b. Constant Release Rate Method (C )(3785)(2) where:

h, = The release rate of radionuclide, i, in gaseous effluents from the auxiliary stack releases, pCi/s.

Cn = activity concentration measured in oil for nuclide, 1, in pCi/ml.

3785 = milliliters per gallon.

Z = gallons of oil consumed.

T = number of seconds used to burn oil for release.

The dose rate (mrem /yr) is calculated using equation 2-17. The dose rate calculated must comply with the limits stated in Control I3.3.2.

.2.3.5.2 Radiciodine and Particulate Dose Calculations The dose to an individual from radioactive materials in particulate form and radionuclides other than noble gases with half-lives greater than eight c'.ays in ;

l

l ODCM Rev 19 Page 95 l 12/97 CALCULATION METHODOLOGIES n a___ -. - - - - - - . , . _ - - -

gaseous effluents released to areas at and beyond the SITE BOUNDARY from the incineration of contaminated waste oil from the auxiliary boiler stacks shall be calculated in accordance with the methodology below.

Doses calculated are based on the radioactive content of oil sampled prior to incineration.

Total curies released:

Qi = (C-)(3785)(2) (2 - 25) where:

01 = the release of radionuclide 1, pC1 Cn = activity concentration measured in oil for nuclide, i, in pC1/ml.

3785 = milliliters per gallon.

Z = gallons of oil consumed.

The dose (mrem) is calculated using equations 2-20, 2-21, and 2-22. The dose calculated must comply with limits stated in Control I3.3.4 and I3.3.5. The doses will be summed with cumulative dose contributions for current month, "alendar quarter, and calendar year.

2.3.6 Gaseous Effluent Dose Projection l Control I3.3.5 requires the VENTILI. TION EXHAUST TREATMENT SYSTEM be used to reduce radioactive material levels prior to discharge when projected doses from both units to areas at and beyond the SITE BOUNDARY would exceed 0.6 mrem to any organ in a 31 day period.

I A dose projection is performed at least once per 31-days by the following equation:

D or = (Dmo / a)

31d (2 - 26) where:

Dmaxp = maximum organ dose projection for current 31-day period (mrem)

Dmax = maximum organ dose to date for current calendar quarter as determined by equation

] (2-20) (2-21) or (2-22) (mrem).

ODCM Rev 19 Page 96 12/97 CALCULATION METHODOLOGIES d = number of days in current calendar quarter at the end of the release.

31d = the number of days of concern.

3.0 Annual Dose Evaluation 3.1 The assessment of radiation doses for the radiation dose assessment report shall be performed utilizing the methodology provided in Regulatory Guide 1.109,

" Calculation of Annual Doses To Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I", Revision 1, October 1977. Any deviations from the methodology provided in Regulatory Guide 1.109 shall be documented in the radiation dose assessment report, f 3.2 The meteorological conditions concurrent with the time of release of radioactive materials (as determined by sampling frequency of measurement) or approximate methods shall be used as input to the dose model.

4.0 Special Dose Analysis l 4.1 Total Dose to members of the public l Control 13.3.7-2 requires that the annual dose or dose commitment to any MEMBER OF THE PUBLIC, due to releases of radioactivity and radiation, from the uranium fuel cycle shall be limited to:

$ 25 mrem whole body or any organ except thyroid s 75 mrem thyroid l Control I3.3.7-2 Surveillance Requirem.nt requires that cumulative dose contributions from direct radiation from operations be evaluated when the calculated dose from the release of radioactive materials in liquid or gaseous l effluents exceed the limits of Controls I3.2.3.a, 3.2.3.b, 3.3.3.a, 3.3.3.b, 3.3.4.a, or 3.3.4.b. The direct radiation contribution shall be determined by the

. methodology described below. .This methodology calculates the direct radiation contribution which then must be added to the dose or dose commitment determined in accordance l with Sections III.3.1, II2.3.3, and II2.3.4 to determine total dose from-all pathways. This evaluation of direct radiation contribution is in accordance with ANSI /ANS 6.6.1-1979 Section 7. The error using this method is estimated to be approximately 8%. The following eva3uation=is performed for each receptor of concern.

l Deat = Dmm - Dx saa - D am.

i (4-1)

l ODCM Rev 19 Page 97

'l 12/97 CALCULATION METHODOLOGIES J

where:

=

D:n cumulative dose contribution from direct radiat$on l at the appropriate receptors-(mrem).

NOTE: -Due to the statistics of radiation measurements and to the conservative nature of effluent calttlations it is plausible the D:n may yield a a

negative value. In this situation the.value for

, Dem shall be reported as zero(0) .

Dnu, = total dose at receptor of interest (as evaluated by TLD measurement) (mrem) .

i

NOTE: If there is not a TLD location at the actual receptor location, a more conservative location j' will be used to evaluate Tott.1 Dose.

! Dne, = mean of the background dose as evaluated by TLDs at background sites (mrem).

Durra = effluent contribution to dose (as evaluated in sections 2.3.3 and 2.3.4.1).

4.2 Doses Due to Activities Inside the SITE BOUNDARY l In accordance with Control I3.6, the Annual Radioactive l l Effluent Release Report shall include an assessment of

, radiation dose from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY.

There are three locations within the SITE BOUNDARY that are accessible to MEMBERS OF THE PUBLIC for activities unrelated to the operation of Limerick Station. These locations are: 1) the railroad tracks which run along the river within the SITE BOUNDARY; 2) the Limerick Infor. nation Center, on Longview Road next to the 500kv substation; and 3) Fricks Lock. Of these three locations, the railroad tracks are the closest to the plant confines.

Sectors and distances.of these locations are provided below:

4 i

Sector Distance to Location (m)

Railroad Tracks:

S -300 SSW 225 SW 225 WSW 225 W 225 WNW 345 NW. 450

I ODCM Rev lQ Page 98 1 12/97 !

CALCULATION METHODOLOGIES J

Information Center:

ESE 884 ,

Fricks Lock:

WSW 450 Annual doses will be calculated in accordance with Reg.

Guide 1.109 and assume an occupancy factor of 0.25. The meximum dose calculated will be reported in the Annual

- Radioactive Effluent Release Report.

5.0 Radiological Environmental Monitoring Program 5.1 Sampling Program The operational phase of the Radiological Environmental Monitoring Program (REMP) is conducted in accordance with l the requirements of Control 13.4. The objectives of the program,are:

- To provide data on measurable levels of radiation and radioactive materials in the site environs.

- Io' evaluate the relationship between quantities of radioactive materials released from LGS and resultant radiation doves to individuals from principal pathways of exposure.

The san.pline, requirements (type of samples, collection frequency, and analysis) and sample locations are presented in Appendix B.

5.2 Interlaboratory Comparison Program l Technical Specification 6.8.4.f.3 requires analyses be per formed on radioactive material supplied as part of an Interlaboratory Comparison.

Participation in an approved Interlaboratory Comparison Program provides a check on the preciseness of measurements of radioactive material in environmental samples. A summary of tha Interlaboratory Comparison Program results is provided in the Annual Radiological l Environmental OperatJng Deport pursuant to Control I3.5.

1

1 TABLES

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

t l ODQ4 Rev. 19 h Page 99 i l 12/97 i

4 4

j TABLE 11 INGESTION INDMDUAL DOSE FACTORS (D,,)

For liquid efDuents 4

1 r

i Urdts for All Ingestion Patimays are: l mretWpa 3

b

,,4._,,;.- ,f_,____. ,, , , _ . , . . _ , . - _ ._--.-.._,_._.m._~..._.._._...,_.,,,__,...._,,,_._,_,_.,...-....;

I ODCM Rev. 10

Page 109 i I 12/97 l

j Table 1 1 i- l UgujdlwFamn from Table E Il of Reg Guide 1.109 Ingesdon Dose Factors for Adult-i 1

110NE LIVER T. BODY T11YROID - KIDNEY LUNO GILLI l 113 0(00E+vo 1.050E417 1.050E 07 1.050E417 1.050E417 1050E4)7 1050E 07

! Cid 2 840E4 $ 680E 07 5 680E47 5 680E 07 5 61'0E 07 5 680E 07 5 680E 07 i Na24 1.700E46 1.7(CE 06 1.700E 4 1.700E 4 1.700E 4 1.700E 4 1.7(CE4 l P32 1.930E44 1.200E 05 7.460E4 00(XiE40 0.(KK)E400 0.000E+00 2.l?0E 05 j Cr$1 00(K)EHC 0.(K0EM10 2 660E 09 1.590E 09 5 860E 10 3330E 09 6,090E 07 1 Mn54 'l 000E40 4.570E4 8,720E 07 0 000E+00 1360E46 0.000E400 1400E 05 -

Mn56 0 (KX)E+00 1.150E 07 2.040E 08 0 0(CE+00 1460E 07 0.000E+00 3.670E4 I

Fe55 2 750E4 1.900E 06 4.430E47 0 000E+00 0.000E*io 1.000E 4 1.090E 4 Tc59 4340E4 1.020E 05 3 910E46 0 000E+00 0 000E4K) 2 850Edi6 3.400E 05

-l CoS8 0.(KK)EHo 7.45CE417 1.670E 4 0 (x0E+00 0.000E+<K) 0 6(K)E+00 1.510E 05 i Cc60 0 00'iE+00 2.140E 4 4.720E4 0 (K0E+00 0(KK)E40 0 000 EMU 4.0202 05 Ni63 1300E44 9.010E 06 4360E 06 0 000E400 0 000E+00 0.000EMK) 1880E44 l

! %$ 5.280E4)7 6 860E 6o 3130E 08 0(KX)E40 0000EMO 0 000E@ 1.740E 06 i Cu64 0 00(>E40 8.330E48 3.910E418 0 000EHic 2.100E 07 0.(XCEMO 7.100E4 1 Zn65 4 840E4 1.540E 05 6 960E416 0 000EH10 1.030E 05 0 000Eno 9.700E4 Zn69 1.030E 08 1.970E 08 1370E 09 0 000E40 1.280E 08 0.(KK)E+00 2.960E49 -

! Dr83 0000E440 0 000E+00 4.020E 08 0.000Enio 0.000E+00 0 000E+00 5.790E 08 i j Br84 0000E40 0 000EM10 5,210E 08 0 000E40 0 000E+00 0.000E@ 4.090E 13

, Ilr85 0 000E+00 00(CE+60 2.140E 09 0.000E+00 0.000".+00 0.000Edio 0000 EMU l Rb86 0 000E400 2.110E4$ 9 830E46 0.000E410 0000E4:0 0.000E+00 4.160E4

!. Rb88 0 000E400 6.050E 08 3.210E 08 0.000EKKI 0 000E+00 0.000EMO 8 360E 19 i RbH9 0 000E+00 4 010E 08 2.820E418 0.000E40 0.000E400 0.000E400 2 330E 21 Sr89 3.080E 04 0 000E400 8 840E4 0.000EMio 0.000E+00 0 0(K)EMK) 4.940E 05

Sr90 7.580E 03 0 000E+00 1860E 03 0.000EKO 0 000EHK) iO00E+00 2.190E 04 j Sr91 5 670E 06 0 000EKO 2.290E4)7 0 000E+00 0 (KK)E+00 0.000E+00 2.700E 05

& 2150Em 0 (KK)E+00 9300E 08 0.000E+00 0 000E+00 0.000EH10 4.260E 05 1

Y90 9620E 09 0 000E+40 2.580E 10 0000EKK) 0000EMio 0.000E+00 1.020E-04

' i Y91m 9 090E.ll 0000E+(0 3.520E 12 0.000E+00 0.(KKiE*0 0 000E+00 2.670E 10 Y9I l.410E417 0000E40 3.770E4)9 0 000EMO OOCUE+00 0.000E+00 7.670E 05 Y92 8 450E 10 0.000E+00 2 470E 11 0 000E+00 0 000E+00 0 000E+00 - 1.480E 05 Y93. 2 680E 09 - 0.000E+00 7.400E Il 0.000EH10 0 000EMio 0 000E+00 8 500E 05 ZrW 3 040E 08 9.750E419 6 600E 09 0 (KKC+00 1.530E 08 0.000E+00 3 090E 05 Zrv7 1680E419 3390E 10 1.550E 10 0 000E4)U 5120E 10 0000EHic 1.050E 04

.Nb95 6 220E 09 3.460E 09 1.860E 09 OmiE+00 3.420E 09 0.000E+00 2100E 05 j_ Mo99 - 01XK)E4Ki 4 310E 06 8.200E417 0.000E410 9.760E4 6 0.000E+00 9.990E 06 j Tc99m . 2.470E 10 6.980E 10 8.890E 09 0.000E4Ki 1.060E 08 3.420E 10 4.130E 07 Tcl01- 2.$40E 10 3 6(OE 10 3.590E 09 0.000E+00 6.590E 06 1.870E 10 1.100E 21 1 Rul03 1.850E 0" 0 (K0E+00 7.970E 08 0.000E+00 7.060E-07 0 000E+00 2.160E 05 3 Rul05 - 1.540E418 0.000E+00 6 080E 09 0 0(K)E+00 1.990E417 0.000E+00 9.420E4 RuIM- 1750E46 Of00E+00 3.480E 07 0.000E+00 5310E 4 0.000E+00 1.780E 04 Agl10m L600E4)7 .1,480E 07 8.790E 08 0.000EKO 2.910E 07 0 000E+00 6 040E 05 ,

Tel25m . 2 860E416 9.170E 07 3.590E47 8 060E 07 1.090E 05 0.000E+00 . l.070E 05 i Te127m 6.770E 06 - u20E4 8.250E 07 1.730E 4 2.750E 05 0 000E+00 2.270E 05

Tel27 1.100E 07 3.950E 08 2380E 08 8.150E418 4 480E-07 0 000E+00 8 680E 06 Tel29m 1.150E 05 4.290E 06 1.820E 4 3.950E4 4 800E 05 0 000E+00 5.790E 05 i Tel29 3.140E 08 1.180E 08 7,650E 09 2.410E 08 1320E 07 0.000E+00 2370E 08

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

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

l ODCM Rev. 19 Page 101 q l 12/97 l Table 1 1(Contmud l l LiggjdDoseFadors

< Trom Table E 1I of Reg Guide 1,109 Intestion Dose Faaors For Adult:

DONE LIVER T.DODY THYROID KIDNEY LUNO GI111 Tel31m 1.730E 4 8 460E 07 7.0$0E 07 1.340E 06 8.570E 06 0.000E460 8.400E 05 Tel31 1.970E 08 8.230E 09 6.220E 09 1620E 08 8.630E 08 0 (00E40 2.790E 09 Tel32 2.$20E46 1630E 4 1.$30E 06 1.8(K)E 06 1.370E45 0.1100E440 7.710E 0$

1130 7.560E47 2.230E 06 8 800E 07 1.890E 04 3.480E4 0.000E+00 1.920E 06 1131 4.160E46 5.950E4E 3 410E 06 1.950E 03 1.020E 0$ 0.000E400 1.370E 4 1132 2.030E 07 $.430E 07 1.900E 07 1.900E 0$ 8650E 07 0 000E+00 1.020E 07 i 1133 1.420E4 2 470E 06 7.$30E 07 3 630E 04 4 310E4 0 000E+00 2.220E 06

, IM4 1.060E47 2 880E 07 1.030E 07 4.990E 06 4.$80E47 ORK)EMIO 2.510E 10

^

113$ 4.430E47 1.lf DE46 4.280E 07 7.650E 0$ 1.860E46 0.000EMO l.310E 06 l Csl34 6.220E 0$ l.480E04 1.210E44 0.000E+00 4.790E 0$ 1.$90E 0$ 2 $90E 06 i i

Csl36 6.$10E4 2.570E 0$ 1.850E 0$ 0 000E+00 1430E 05 1.960E 4 2.920E 06

. Csl37 7.970E 05 1.090E 04 7.140E 0$ ONCEMX) 3.700E 0$ t.230E-0$ 2.110E 06 Csl38 $.520E 08 1090E 07 $ 400E48 0000EMO 8 010E 08 7 910E 08 4.6$0E 13 Da139 9.700E 08 ;"10E 11 2 840E 09 0 000E+00 6 460E 11 3.920E 11 1.720E 07 Dal40 2.030E 0$ . 40E 08 1.330E 06 ORCE+00 8 670E-09 I 460E 08 4.180E 05 Bal41 4 710E 08 3.560E Il 1.590E 09 0.000E+00 3.310E Il 2 020E Il 2.220E 17 Dal42 2,130" a 2.190E fl 1.340E 09 0 000E+00 1.850E Il 1.240EIl 3 ROE 26 12140 2.$ lod 09 1.260E 09 3.330E 10 0 (00EMO OROE+(10 0 00()E400 9.250E 0$

14142 1.280E 10 $ 820E Il 1.450E ll 0 000E+00 0 0(10E+00 0 000E400 4.2$0E-07 Cel41 9.360E 09 6 330E 09 7.180E 10 0 000E40 2.940E49 0 000E+00 2.420E 0$

Cel43 1.6$0E 09 1.220E*6 1.350E 10 OK)0E+00 5.370E 10 OA)0E+fo 4.560E 05 Cc144 4 880E 07 2.040E 07 2 620E 08 0 000E+00 1.210E 07 0OC0E+00 1.650E 04 14143 9.200E 09 3 690E 09 4.560E 10 0 000E40 2.130E 09 0 000E40 4,030E 0$

Prl44 3.010E Il 1.250E Il 1.$30E 12 0 000E+00 7.050E 12 0 000E+00 4.330E It Ndl47 6.290E 09 7.270E 09 4 350E 10 0000E+00 4.2$0E 09 0.00()E+00 3 490E 0$

W187 1.030E-07 8 610E 08 3.010E 08 0.000EMO ORUEMU 0 000E+00 2.820E 05 Np239 1.190E 09 1.170E 10 6.450E Il 0000E+00 3 650E 10 0 000E+00 2 400E 05

l ODCM Rev. 19 Page 102 l 12/97 l Table 11(Conunued)

Li24!d.lbd1&@n from Table E 12 of Reg Guide 1.109 Ingestion Dow facton for Teen:

DONE LIVER T.DODY 'IHYROID KIDNEY LUNO GlLLI ID 0 (KK)E400 LO60E 07 1 (60E 07 1060E 07 1.060E 07 1060E 07 1060E 07 Cl4 4 060E4 8.120E 07 8120E 07 8120E 07 8120E 07 8.120E 07 8120E 07 Na24 2300E4 2 300E4 2 3(CE46 2300E4 23(CE 4 2300E46 2300E416 P32 2.760E 04 1.710E4)$ 1070E 05 0 0(CE+00 MxoE+00 01KKiEMO 2320E 05 Cr$1 0000Eno 01XiOE40 3 600E 09 2 000E 09 ts90E 10 5140E 09 6 050E 07 Mn54 01KK)EHo 5.900E 4 1.170E G 0 (00E40 1.760E46 01xiOE+00 1.210E45 Mn56 0 (KiOE+00 1.580E 07 2 810E 08 0.000EMO 2.000E 07 0 (KiOE+(o 1.040E 05 Fe$$ 3.780E4 2.680E 06 6.250E 07 OM00EMo 0 000E+(o 1.700E46 1.160E46 fc59 5870E 4 1370E415 5.290E 06 0 0'ioE+00 0(K0E400 4 320E 06 3 240E 05 Coss 0 000Eno 9.720E 07 2.240E46 0 (K0EHK) 0 000E+00 0 000E+(0 1340E4)$

Cdo O WKIE400 2 810E4 6330E 06 0 000E*10 0 000E40 0 000E4(x) 3 660E45 Ni63 i 770E 04 1.250E 05 6 t00E46 0 000E +(o o m:0E+(o 0000E40 1.990E 4 Ni65 7.490E47 9.570E 08 4 360E418 01KK)E40 0 000E410 O!KoE4(K) $190E 4 Cu64 0 000E+00 1.150E47 5 410E 08 0 000E4K) 2 910E417 01KK)E+00 8 920E46 In65 5.760E 06 2 (KK)E 05 9 330E 06 01XoF+(0 1.280E 05 0 000EMC 8 470E46 Zn69 1.470E 08 2 800E 08 1960E 09 01KW C 1830E 08 0 000E+00 5.160E418 Br83 0 000E+00 0 000E+00 5.740E 08 01n 1 0000EH10 OIKOE+(0 0 000E+00 Ilr84 0(N0E+00 NKK)E4K1 7.220E 08 0 0(KS 1 0 000E+00 0 000E+00 0 000E+00 Dr85 0 000E+00 01xiOE4 3 050E 09 0 000hWn 0 000EHC 0000E+00 0 000E+00 Rb86 0 000E4m 2.980E 05 1400E 05 0 000E+(x) 0 000EHC 0000E+oo 4 410E 06 kb88 0 000E+(o 8.520E48 4.540E 08 00fK)E410 0 000E40 0 000EHi0 7300E 15 Rb89 O (KiOEdo 5.500E 08 3.890E 08 01KoE40 0 000EMO 0 000E+00 8.430E 17 Sr89 4 400E44 0100E+(0 1.260E 05 0 (KK)E+00 0 000E+00 0 000E+00 5,2405 05 Sr90 8 300E 03 0 000E+00 2 050E 03 0 000E410 0000Edio 0000E+00 23305 04 Sr91 8 070E4 01(CE+00 3 210E4)7 0 000E+(o 0 000EHK) 0 000E+00 3 660E 05 Sr92 3 050E 06 0100EMO 1300E 07 0 000E+00 0 000E400 0 000EMo 7.770E 05 Y90 1370E 08 0 000E+00 3 690E 10 0.000E4K) 0 000E+(0 0 (KoE+00 1.130E 04 Y9tm 1.290E 10 0 000Enio 4 930E 12 0 000E+00 0 000E+00 0100EH10 61>90E 09 Y91 2 010E 07 0 000E40 5390E49 0 000E+00 0 000E+00 0 000E+00 8 240E-05 Y92 1.210E 09 0 000E+00 3.500E Il 0000Edio 01K10E+(n) 0100E+00 3 320E 05 Y93 3 830E49 01KioEMO l 050E 10 0 000EC 0 000EMo 0000EH o 1.170E 04 Zr95 4.120E4x 1300E 08 8 940E 09 0 000EMO 1.910E 08 0 000E+00 3 000E-05 Zr97 2370E 09 4 690E 10 2.160E 10 0 000E+00 7 Il0E 10 0 000EM10 1.270E-04 Nb95 8 220E 09 4 560E49 2.510E-09 0 000E+00 4 420E-09 0 000E+00 1,950E 05 Mo99 0 000E+00 6,030E 06 1.150E 06 0 000E+00 1390E 05 0 0(K1EMK) 1.080E 05 Tc99m 3320E 10 9.260E 10 1.200E 08 OAKoE+(o 1380E-08 5.140E 10 6 080E 07 Tcl01 3100E 10 5120E 10 5.030E 09 0 000E+00 9 260E 09 3.120E 10 8.750E 17 Rul03 2.550E 07 0 000E+00 1.090E 07 0 000E410 8 990E 07 OIKoEMO 2.130E 05 Rul05 2.180E 08 01KoE+00 8 460E49 0 000E4K) 2.750E 07 0.000E+00 1.760E 05 Rul06 3.920E 06 0 000EHK) 4.940E 07 0 000E+00 7.560E 06 01100EWO I 880E-04 Agl10m 2 050E417 1.940E 07 1.180E-07 0100E+00 3.700E-07 OIn)E+00 5 450E 05 Tel25m 3.830E-06 1380E4 5120E-07 1.070E 4 0 000E+00 0 000E+00 1.130E 05 Tel27m 9=670E 06 3 430E4 1.150E-06 2300E 06 3.920E 05 0.000E+00 2.410E 05 Tel27 1380E 07 5 600E 08 3.400E-08 1.090E 07 6 400E 07 0 000E+00 1.220E 05 Tel29m 1.630E 05 6.050E-06 2 580E-06 5.260E 06 6.820E 05 0 000E+00 6.120E 05 Tel29 4 480E 08 1.670E 08 1.090E-08 3.200E 08 1.880E 07 C000EH10 2.450E-07 Tel31m 2 440E4 1.170E 06 9.760E-07 1.760E 4 1.220E 05 0 000E+00 9390E 05

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

l ODCH Rev. 19 Page 103 l 12/9*/

Table 1 1 (Continued) l L121tidlh!K.fa&D l Frorn Table E 12 of Reg Guide 1.109 Ingestion Doseiactors For Tecn: .

1 IlONE LIVER T DODY '!1IYROID KIDNEY LUNO GI LLI i Tel31 2 790E4)8 1.150E48 8 720E4)9 2.150E418 1.220F.47 0000Eno 2.290E 09 Tel32 1490E4 2.210E46 2 080E 06 2.330E46 2.12GE4)$ OiKiOE+(0 7 000E 05 1130 1.030E 4 2.980E4 1.190E 4 2.430E44 4 590E4 0 000EHC 2 290E4 1131 5 850E4 8.190E46 4 400E4 2.390E 03 1410E45 0 000E40 1.620E 4 1832 2.790E 07 7300E 07 2 620E 07 2.460E 05 1.150E4 0 000EHC 3.180E 07 1833 2 010E4 3 410E4 II40E4 4.760E 04 5 980E 06 OIKK)E+00 2.580E 06 l134 1.460E 07 3 870E47 1.390E 07 6.450E40 6.100E4)7 0(00EHC 5100E 09 1135 6.100E47 1.570E 4 5.820E 07 1.010E 04 2 480E4 0400E40 1.740E 4 Cs134 8 370E 05 1.970E 04 9.I40E4)$ 0 000E40 6 260E415 2390E 05 2,450E4 Csl36 8.590E46 3380E 05 2.270E 05 0 000Enio 1.840E 05 2 900E4 2.720E 06 I

Csl37 1.120E 04 1490E 04 5.190E 05 0(K0E+00 5.070E-05 1.970E 05 2.120E4 Csl38 7.760E 08 1.490E 07 7.450E 08 0 000EHC 1.100E 07 1.280E 08 6.760E Il 13a139 1390E 07 9.780E 11 4.050E 09 0 000E40 9.220E 11 6 740E 11 1.240E 4 Ital 40 2 840E 05 3.480E 08 1.830E 4 0(00E40 1.180E 08 2340E 08 4380E45 Bal41 6.710E 08 5 010E Il 2.240E 09 0 000EH10 4 650E Il 3 430E il 1.430E 13 Ital 42 2.990E 08 2,990E Il I 840E 09 0100E+00 2.$30E Il 1.990E Il 9.180E 20 Lal40 3 480E 09 1.710E 09 4.550E 10 01XK)E+00 0 000EHK1 0 000E40 9,820E4)5 Lal42 1.790E 10 7.950E.l l 1.980E Il 0000E400 0 000E400 0100E+00 2 420E46 Cel41 1330E 08 8 880E 09 1.020E 09 0 0(KiE+00 4.180E 09 0 000E+00 2.540E 05 Cel43 2350E 09 1.710E 06 1.910E 10 0 000E40 7 670E 10 0 000E400 5.140E4)$

Ccl44 6 960E 07 2 880E 07 3.740Edi8 01x0E400 1.720E4)7 0(00E+00 1750E 04 Pr143 IJ10E4* 5.230E 09 6 520E 10 0 000EHo 3.040E 09 0000EMK) 4 310E 05 ir144 4 300E Il 1.760E ll 2.180E 12 0 000E4X) 1.010E Il 0000E40 4 740E 14 Ndl47 9380E 09 1.020E418 6110E 10 0 000EHK) 5 990E-09 0 000E+00 3.680E 05 Wl87 1460E417 1.190E 07 4.170E418 0 000E+(0 0 000E40 0000E40 3.220E 05 Np239 1.760E 09 1660E 10 9 220E Il 0 (Kx)EHo 5 210E 10 0 000E+00 2 670E 05

! l ODCM Rev. 39 [

Page 104 l l 12/97 i Table 1 1 (Conumacd) [

j !

l Liquid From TableDose E 13 ofFa@n Reg Guide 1.109 c Ingesuon Dose Factors for Cldid.

i BONE LIVER TBODY THYROID KIDNEY LUNO GILLI i 10 0(xiOE+00 2 030E417 2 0)0E 07 2.030E47 2.030E 07 2.030E 07 2 030E 07 l Cl4 1.210E 05 2.420E4 2 420E4 2.429E46 2.420E4 2.420E46 2 420E4 !

i Na24 $ 800E 06 5800E 4 5800E46 $RioE4 5.800E 4 5 800E46 5 6 JOE M P32 8 250E4)4 3 860E 05 3.180E4)$ 0 000E+00 0 (KK)E4io 0000EHi0 2.280E 05 Cr$1 OIKK)E@ 0 000E40 8 9(CE 09 4.940E 09 1.350E49 9.020E 09 4.720E 07 l

Mn54 0(00E+00 1070E 05 2 850E 06 0 000E+00 3R10E4 0 (K0EMO 8.980E 06 i l Mn56 0 000E+00 3.340E 07 7.540E 08 0 000E+<0 4 040E47 0 000E40 4 840E 05 ;

fc55 1.150E 05 6,100E 06 1.890E44 0000E@ 0000E40 3.450E 06 1.130E 06 Fe59 1.650E 05 2 670E45 1.330E 05 0100E410 0 000E40 7.740E46 2.780E415 CoS8 0000E@ 1R0E4 5.510E46 0(00E400 0.000EHO 0000EMO 1050E 05 Co60 0000E40 5.290E4 1560E415 0 000E+00 0 000E+00 0000EMKi 2.930E 05 Ni63 5.380E44 2 880E 05 1.830E 05 0 000E+00 0 000E+00 0 000EHO 1.940E 06 ;

Ni65 2120E4 2.090E 07 1.220E417 0 000E+00 0 (KK)E+00 0000E40 2.560E45

' Cu64 0 000Edio 2 450E 07 1.480E 07 0(K0EHC 5.920E417 0.000EHK1 1.150E 05 Zn65 1.370E05 3 650E45 2.270E 05 00(CEdio 2.300E 05 0 000E+00 6.410E4 L Zei69 4.380E 08 6 330E418 $ 850E419 0 000E+00 3 840E 08 0 000EK10 3.990E4 Br83 0000E410 0 000Edio 1.710E 07 0 000E+00 OR OE+00 01K0EMK1 0 000E+00 Br84 0 000E+00 0 on0EMO 1.980E417 OuiOE+00 0 000E+<0 0 000EMK) 0.000EK0 ,

Dr8$ 0 (KK)E+00 ODOEMO 9.120E 09 OAK)E+00 OAiOE+00 0 000E+00 OR0E*00 Rb86 01K0E+00 6.700E 05 4.120E 05 0(KiOE+00 ORK)E+00 0 000EMO 4.310E 06 Rb88 0 000E+00 1.900E 07 1.320E-07 0000EM10 0100E+00 0 000E+00 9.320E 09 Rb89 0 000E4K) 1.170E 07 1040E 07 URK)E40 0 000E40 0 000E+00 1.020E49 Sr89 1.320E413 0100E @ 3.770E 05 0 000E+00 0 000E4K) 0000E400 5.110E 05 ,

Sr90 1.700E 02 OR10EHO 4.310E 03 OD UE+00 ONCEM0 0 000E40 2.290E44 Sr91 2.400E 05 0 000E+00 9 060E417 OKKE+00 0 000E4K1 OR10E+00 5.300E 05 SW2 9 030E46 0 000E+00 3.620E 07 0 000L +00 OR0E+00 0 000E+00 1.710E 04 Y90 4 ll0E 08 0 000E+00 1.100E 09 0 000E+'io OR 0E+00 0 000E+u) 1.170E 04 I Y91m 3 820E 10 000EKK1 1.390E Il OnioE+(O OR10E+00 ORK)E410 7.480E 07 .

Y91 6020E417 0 000E+00 1.610E 08 Ou0E+00 0 000E+00 0 000E+00 8 020E 05 Y92~ 3 600E-09 0 000E+00 1.030E 10 0 000E+00 0000EMC 0 000E+00 1.040E 04 Y93 1.140E418 OniOE+00 3.130E 10 OD UE+00 ORX1EH10 0 000E+00 1.700E 04 Zr95 1.l(OE 07 2.550E 08 2.270E 08 OuoE+00 3.650E 08 OR0E+00 2E0E 05 :

Zr97 6.990E 09 1.010E 09 5.960tv10 0 000E+00 1.450E4)9 0 000E+00 1.530E-04 !

Nb95 2.250E 08 8 760E 09 6 260E4)9 0 000E+00 8.230E 09 0 000E400 1.620E 05 Mo99 0 000E+00 1.330E 05 - 3.290E-06 0.000E+00 2.840E 05 ORK)EMO 1.100E 05 Tc99m 9.230E 10 1.810"09 3 DOE 418 ORCE*10 2.630E 08 9,190E 10 1.030E4 Tcl01 1.070E 09 1.120E 09 1.420E418 OA10EM10 1.910E 08 5.920E 10 3.560E 09 Rul03- 7.310E417 0 000E400 2.810E 07 OD10E+00 1840E-06 0 000E+00 1.890E 05 Rul05 ' 6 450E418 0 000E+00 2.340E48 OR10E+00 $ 670E 07 0100EHC- 4.210E4)$ ~

-Rul06 1.170E 05 0 000E+00 1.460E 4 0 000E40 1.580E 05 0.000E+00 - 1.820E-04 ,

Agil0m 5.390E417 3 640E 0*- 2.910E-07 0 000E+00 6.780E 07 0 000E+00 4.330E 05 Tel25m 1.140E 05 3.090E4 1.520E46 3.200E 06 0.000EM10 0.000E+00 -1.100E05 Tel2im 2.890E 7.780E 06 3.430E4b 6 910E 06 ' 8.240E 05 0.000E+00 2.340F45 Tel27 4.710E-07 1.270E-07 . 1.010E 07 3.260E 07 1.340E44 0 000E+00 1.840E 05 :

Tc129m - - 4.870E 05 1.360E45 7,560E 06 1.570E 05 1.430E44 OR10E+00 5.9J0E 05 Tel29 1.340E 07 - 3.740E 08 3.180E-08 9.560E418 3.920E 07 OuiOE+00 8.?.40E 06 Tel31m - 7.200E 06 - 2.490E-06 2.650E46 5.120E 06 2.410E 05 0000EMO 1.010E 04 l

l ODCM Rev. 19 Page 105 l 12/97 Table 1 1(Contimmed) >

l LiguidIkse From Table E 13Factors of Reg Guide 1.109 Ingestion Ixse Factors For Cldid: '

i i HONE LIVER T BODY THYROID KIDNEY LUNO - GI LLI i

Tel31 8 XCE 03 2.5%)E 08 2 470Le8 6.350E 08 2.510E 07 0 000E40 4.360E 07 I Tel32 1.010E 05 4 470E46 5.400E 06 6.$10E4 4150E-0$ 0 000E40 4.500E 05 1130 2 920E46 1900E 06 3.040E4 6.500E44 8 820E4 0 000EM10 2.760E 06 1131 1.720E 03 1.730E 05 9.830E4 5.720E 03 2.840E 0$ 0.000E+00 1.540E 06 2 1132 8 000E 07 1.470E 06 6.760E 07 6.820E 05 2.250E 06 0000EMX1 1.730E 06 !

1133 $.920E 06 7.320E4 2.770E46 1.360E 03 1.220E 05 0.000EMio 2.950E4 4 1134 4,190E 07 7.780E 07 3.580E 07 1.790E 05 1.190E 4 0.000E+00 5.160E 07 i

> 1135 1.750E46 3.150E 06 1.490E 4 2.790E 04 4.830E4M 0.000E+00 2.400E4 '

Cst 34 2.340E 04 3.840E 04 8.100E 05 0 000EMO 1.190E 04 4.270E 05 2.070E4 i-Csl36 2.350E 05 6460E 05 tl80E 05 0 000EMO 3.440E4)$ 5.130E 06 2.270E4 -

Cal 37 3.270E 04 3.130E 04 4.620E 0$ 0-(KiOE4K1 1.020E 04 3.670E 05 1.960E 4 Csl38 2.280E 07 3.170E 07 2.010E 07 0000FM10 2.230E-07 2,400E 08 1.460E 07

Bal39 4.140E 07 2.210E 10 1.200E 08 0(KE 40 1.930E 10 1300E 10 2.390E 05 Bal40 8 310E4)$ 7.280E48 4 850F4 0 000E40 2.370E 08 4 340E48 4.210E 05 ;

Ba14l 2 000E 07 1.120E 10 6 510E 09 0.000E40 9.690E 11 6 580E 10 1.I40E 07 Bal42 8.740E 08 6 290E Il 4.880E 09 0.000E+00 $.090E Il 3.700E ll 1.140E 09 Lal40 1.010E 08 3.530E4)9 1.190E 09 0 000EHO 0.000E40 0.000EM10 9 840E 05 Lal42 5.240E 10 1.670E 10 $.230EIl 0 000E+00 0.000E+00 00(X)EMO 3.310E 05 Ce141 3.970E 08 1.980E 08 2.940E 09 0 000E+00 8 680L 09 0 000E+00 2.470E415 Cel43 6 990E 09 3.790E 06 $ 490E 10 0.000E+00 1.590E 09 0 000E+00 $.550E 05 Cel44 2.080E4 6 520E 07 1.110F417 0000E40 3.610E 07 0 000EH10 1.700E44 Prl43 3.930E 08 1.180E 08 1.950E 09 0 000E+00 6 390E-09 0000EK10 4.240E 05 l Pr144 1.290E 10 3.990E 11 6 490E 12 0 WiOE+00 2.I10E-11 0 000E+00 8 590E 08 l Ndl47 2.790E 08 1260E 08 1.750E 09 0.000E410 1.240E 08 0.000E+00 3.580E 05 W187 4.290E 07 2.540E 07 1.140E 07 0 000EMO 0.000EMO 0.000E+00 3.570E 05 Np239 - 3.250E 09 3.770E 10 2 650E 10 0.000EMiG l.090E419 0.000EMD 2.790E 0$

4 i

?

- ._ . , .,__,.c_..,-..,..._._....._..._-., . . . . . . - , - , , , _ . - . _ . _ , ~ . . ..-,_-,._-......m-- . ,.~ --- . , . . _ - _ . . . - - . , . _ _ .

l ODCM Rev. 19 Page 106 l 12/97 Table 1 1 (Conunued) l Lim!1DoseFans From Table E 14 of Reg Guide 1.109 Ingestion Dose Factors ForInfant:

DONE LIVER T.DODY TlWROID }UDNEY LUNG GI-LLI II) 0 000E+(0 3.080E 07 3.080E 07 3 080E417 3 080E47 3.080E4/ 3.080E 07 Cl4 2 370E45 $ 060E4 5 060E 06 5.060E 4 $ 060E 06 $.000E4 5.060E46 Na24 1.010E 05 1.010E45 1010E45 1.010E 05 t010E45 1.010E 05 1.010E 05 l'32 1.700E 03 11K0E 04 6.$90E45 0.000E+00 0(00EKKI OJiOEMO 2300E 0$

Cr$1 0 000EM10 0.000E*00 1.410E 08 9.200E 09 2.010E49 1.790E 08 4.110E417 Mn54 0 000E+00 1.990E0$ 4 $10E 06 0 000EMO 4 410E46 0.000E+00 7310E46 Mn56 0100E+00 8.180E 07 1410E 07 0 0(KIEMK) 7.030E 07 0 000E+00 7 430E/>$

Fe$$ 1390E 03 8.980E46 2 400E46 0.000E+00 0.000EMio 4 390E4 1.140E4 l'c$9 3 080E4)$ $380E 05 2120E45 0 000E400 0000E+00 1.390E 05 2.$70E 05 Co38 0 000E+00 3 600E 06 8 980E 06 0.000E+00 0 000E+00 OIK0EMO 8 970E4 CMU 0.000E+(Ki 1.030E 05 2 $$0E45 0 000E+00 0000EMio 0100E+00 2.570E 05 Ni63 6 340E 04 3.920E45 2.200E 0$ 0.000E+00 0000Ee 0 000E+00 1.950E4 Ni65 4.700E6 $.320E 07 2 420F 07 0 000E400 0 000E+00 0.000E+00 4.0$0E 03 Cu64 0 000E@ 6.090E 07 2 820E 07 0 000E40 1030E 06 0 000EMK1 1.250E 05 7m65 1840E4)$ 6 310E 05 2.910E 05 0 000E@ 3.060E 05 0 000EMK) $330E0$

Zn69 9330E 08 1680E 07 1.250E48 0 000EMio 6 980E 08 00(CE @ 1370E 0$

Dr83 0 000E+00 0(00E400 3 630E 07 0(KoEH10 0 000E+00 0.000EW 0 (KK)EE Dr84 0 000E+(0 0 000E+00 3.820E 07 OIK10E+00 - 0 000E+00 0 000E+oo 0.000E+00 Br85 0 (KK)E+00 0 000E+(K) 1.940E 08 0 000EM10 0 000E+00 0.000E+00 0.000E+00 Rt*6 0AxioE40 1.700E 04 8 400E 05 01100E+00 0 000E+00 0.000E+00 4 350E46 Rb88 0 000EMK) 4.980E 07 2.730E 07 0 0(X)E410 0(KK)EMK) 0 (KK)E+00 4 850E 07 Rh89 0100EMK) 2.860E47 1.970E 07 0 000E+00 0 000E+00 0 000E+00 9.740E 08 Sr89 2.510E413 0 000EM10 7.200E 0$ 0000EMO 0 000E+00 01KK)E+00 $.160E 05 Sr90 1850E 02 0.000EMX) 4.710E 03 0.000E+00 0 000E+00 0.000E+00 2310E-04 Sr91 5.000E0$ 0 000EM0 1.810E 06 0 000E+00 0000EMio 0000E+00 $.920E 05 Sr92 1.920E4)$ 01100E+00 7130E417 0 000EMK1 0 000E+00 0.000E+00 2 070E414 Y90 8.690E 08 0000Enio 2 330E 09 0.000E+00 0 000E+00 6.000E+00 1.200E 04 Y91m 8100E 10 0.000E40 2.760E.ll 0000E+00 0 000E400 0000Emo 2 700E46 Y91 1.130E-06 0 000EMio 3.010E 08 0 000E+00 0000EMio 0000E+00 8100E 03 Y92 7 650E 09 0.000 EMU 2.150E 10 0.000E40 0 000E+00 0 000E+00 1460E 04 Y93 2.430E 08 0 000E+00 6 620E 10 0.000E+00 0 000E+00 01KKiE+00 1.920E 04 Zr95 2.060E-07 5.020E 08 3 560E 08 0 000E+00 $ 410E48 0 000E+00 2.500E 0$

Z97 IE0E48 2.540E 09 1.160E4 9 0 000E400 2.560E49 0.000EMO 1.620E44 Nb95 4.200E 08 1.730E 4 1.000E-08 0 (KX)EMio 1.240E 0.000EMO lEiOE 05 Mo99 0 000E+00 3.400E 05 6 630E 06 0.000E+00 5 080E 05 0 000E400 1.120E 0$

Tc99m 1.920E 09 3.960E 09 5.100E 08 0 000E+00 4 260E 08 2 070E 09 1.150E 06 Te101 2.279E 09 2.860E 09 2.830E 08 0.000E+00 3.400E 08 1.560E 09 4.860E 07 Rul03 1.480E 06 0.000EMO 4 950E 07 0.000E 00 - 3.080E4 0.000EMO 1.800E 05 Rul0$ 1360E-07 0.000E+00 4 580E 03 0 000E+00 ifiO0E 06 0/00E+00 $ 410E 05 Rul06 2.410E-05 01100E+00 3.010E4 0.000E+00 2 850E 0$ 0100E WO 1.830E 04

' As110m 9.960E 07 7.270E 07 4 810E 07 - 0 (XX)E+00 1.040E4 0 000E+00 3.770E 05 Tel25m 2330E 05 . 7.790E 06 3.150E46 7 840E 06 0 000E+00 0 000E+00 1.Il0E 03 Tel27m $.850E 05 1.940E 05 7.080E 06 1690E-03 1440E-04 0 000E+00 2360E 05 Tel27 11100E4 3350E 07 2.150E 07 8.140E 07 2.440E 06 000E+00 2.100E 05 Tel29m 1.000E44 3 430E 0$ 1.540E 05 . 3.840E 05 ' 2.500E 04 C00E+00 3.970E 05 Te129 2.840E 07 - 9.790E 08 6 630E 08 2.380E417 7.070E 07 0 000E+00 2.270E-03 Tel31m 1.520E 05 ' 6.120E 06 - 3.050E 06 1.240E 05 4.210E-05 01:00E40 1.030E 04

i t

l I

l ODCM Rev. 19 !

Page 107 )

l 12/97 -

2 1 f j . Table 1 1 (Conunued)

I j l LiqinidlhuFadors From Table E 14 of Reg Omde 1.109 turAnon Dose Factors For Infant: ;

]

l llONE LIVEll T. BODY TlWROID KIDNEY LUNO Ol LLI !

! Tel31 1.760E47 6.500E48 4 940E48 1.570E47 4.500E 07 0 000E+(0 7.110E4 !

]' Tcl32 2 080E45 1030E4)$ 9.610E46 1.520E 05 6.440E 05 0.000E+00 3.810E 05 i

!!30 6 (K0E46 1.320E45 5.300E416 1.480E413 1.450E 05 0 000E+00 2 830E46 i - 1131 3.590E45 4 230E45 1860E 05 1.390E 02 4.940E 05 0 000E+(K) 1.510E46 :

i 1132 1660E 4 3.370E46 1.200E46 1.580E 04 3.760E4 0 000E+(0 2.730E 06 l 1 1833 1.250E 05 1.820E45 5.330E 4 3.310E 03 2.140E 05 0000E40 3 080E4 i 1134 8 690E417 1.780E 06 6.330E47 4.150E 05 1,990E 4 0100E+00 1.840E46

):

i 1i35 3 640E46 7.240E 06 2.640E4 6 490E 04 8 070E4 0.000E+00 2 620E 06 1 Csl34 3.770E 04 7.030E 04 7.100E45 0(00EHC 1.810E.04 7.420E 05 1.910E 4

]'

Csl36 4.590E 05 1.350E44 5 040E 05 0(00EHi0 5.380E 05 1.100E4)$ 2 0$0E 06 Csl37 $ 220E414 6.110E414 4.330E 05 0.(KK)E+00 1640E 04 6640E 05 1.910E 06 C$138 4.810E 07 7.820E417 3.790E417 0.(XK)E+00 3.900E 07 6 090E 08 1.250E 06 l

Bal)9 8 810E 07 5 840E 10 2.550E 08 0 0fX)E+00 3.510E 10 3.540E 10 5.580E 05 Baldo 1.710E 04 1.710E 07 8.810E4 0.000EHo 4 060E 08 1.050E 07 4.200E 05 ,

' f Baldi 4.250E417 2.910E 10 1.340E48 0.000EMO 1,750E 10 1.770E 10 5.190E 06 "

I Bal42 1.840E417 1.530E 10 9.060E 09 01KiOE+00 8 810E Il 9.260E Il 7.590E 07 3 Lal40 2.110E418 8 320E 09 2.140E 09 0.000E40 0(00E+00 0 (XX)E40 9.770E 05 Lal42 1.100E 09 4 040E 10 9.670E Il 0.000E+('O OIKK)Edio 0 000E40 6 860E 05 i Ce141 7.870E418 4 800E 08 5 650E419 0 000E+00 1,e80E 08 0 (XiOE+00 2 480E 05 i Cel43 L480E418 9 820E4 1.120E419 0 000E+(o 2 860E49 0 000E400 5.730E 05

- Cel44 2.980E4 1.220E 4 1.670E417 0000Eno 4.930E47 0.000E+00 1.710E 04 ;

Prl4) 8130E418 3 040E 08 4 030E 09 0100E+00 1.130E4)8 00'XiEMO 4 290E 05

! Prl44 2.7402 10 1060E 10 1.380E Il 0 000E+00 3 840E Il 0 000EHo 4 930E4 1

Ndl47 5.530E418 5 680E418 3 480E49 0 000EMio 2.190E 08 0000E400 3 600E 05 l Wl87 9 030E417 6.280E 07 2170E417 01XX)E+00 0 000E400 01100E4K) 3 690E 05 Np239 1.110E418 9.930E 10 5 010E 10 0 000E+00 1.980E 09 0000E+00 2.870E 05 i i

L

)

i 5

J I

,=--r-c.-+.w ,- %,. .--ww,,- . , , - . , -w, ,n-. ..mw-, e.,--ru-~ . e A ir-.,---.+c.e+

l ODCM key. 19 Page 108 '

l 12/9

Table 12 From Table E4 of Reg Guide 1.109 DDSEIACIDRSIDRSIMDJN10N SilORELINE 2

Ontemhr per pCVm )

OfR! fill 111111d OnufIll lotal Bodd" 11 3 0.0 Ru 103 3 60E49 C 14 0.0 Ru 105 4.50E49 t

NA 24 2.50E 08 Ru 106 1.50E 09 P 32 00 Ag l10M 1.80E 08 Cr 51 2 20E 10 Te 125M 3.50E li j Mn-$4 5 80E49 Tc 127M 1.10E 12 i

Mn 6 . 1.10E 08 Te 127 1.00E Il ,

Fc 55 00 Te 129M 7.70E 10 ,

, Ie 59 8 00E49 Te 129 7.10E 10 Co58 7 00E 09 Te 131M 8 40E 09 Co 60 1.70E48 Te131 2.20E 09 Ni63 00 Te132 1,70E 09 Nr45 3 70E 09 1130 1.40E 08 Cue 4 1.50E419 l 131 2.80E49 Zn45 4 00E 09 l 132 1.70E 08 Zn49 00 1133 3 70E 09 lit 83 6 40E Il 1134 160E 08 Br 84 1.20E-08 1135 1.20E 08 3

Br-85 00 Cs 134 1.20F 08 Rb-86 6.30E 10 Cs 136 1.50E 08 Rb 88 3.50E 09 Cs 137 4.20E 09 R489 1.50E 08 C5138 2.10E48 Sr-89 5 60E 13 Ba 139 2 40E 09 St 91 7.10E 09 Ba-140 2.10E 09 Sr 92 9110E 09 Ba 141 4.30E 09 Y 90 2.20E 12 Ba142 7.90E49 Y 91M 3 80E 09 14 140 1.50E 08 Y 91 2 40E Il La 142 1.50E 08 Y 92 160E 09 Ce141 5.50E 10 Y 93 5 70E 10 Cc143 2.20E 09 Zr 95 5 00E 09 Cc 144 3.20E 10 Zr97 $ 50E 09 Pr143 0.0 Nb-95 510E 09 Pr 144 2.00E 10 Mo-99 1.90E 09 Nd 147 100E-09 Tc 99M 9 60E 10 W.I87 3.10E 09 Tc-101 2,70E49 Np-239 9.50E 10 l) Dose Factors for the other organs (Bone, Liver, Thpoid. Kidney, Lung GI-LLI) are assumed to be tie same as die Total

, Body Dose Factor (Reference Reg. Guide 1.109. Appendix E. Dose Factor). J

. , , , r ,..v , a w -.9,, , ..,,,,.,.r-- e -e

l ODCM Rev. 19 Page 109 l 12/97 l Table 13 Assumpuorn uwd in Limerick Liquid E!!!uent Dose Evaluation Snitld DOCDFlq0 _Dhr _ Referenctu) 1 Penod of tmildup of actmty in sediment (hr) 1.752E+05 Site Spectfic t, Emtl trainit tinac for water ingesuon thr) 1.200E+01 A 2

t, Emtl trarnit time for fish ingestion On) 2.400P+0! A 3*

t, Emti trrnsit tirne for shore exposure Gir) 0 000E40 Site Specific U,, Water ingestion (llyr) adult 7,300E402 E5 U Water ingestion (1/yr) teen 5.100E+02 E5 U, Water ingestion (1/1) 3 child 5100EW2 E5 U., Water ingestion (llyi) infant 3.300E+02 E5 U, Shore expsure Oirlyr) adult 6(00E+02 Site Specific U,, Shore ex)uure(hrlyr) teen 6100E+02 Site Specific U,, Shore exposure (hrlyr) child 9000Eml Site Specific U., Shore cxysure(hr/yr) infant 0000E+00 Site Specific U,, Fresh water fish ingesuon (kg$v) adult 2.100EM)I E5 U., Fres h water fish ingestion ag/>t) toen iB 0E+01 - E5 U,, fresh water fish ingestion Ag/yr) child 6V0E40 -E5 U., fresh water fish ingestion (kght) infant Olo0E40 E5 W Shoreline Widh Factor (dimensionless) 2.000E 0l A 2*

1) The References refer to tables contained in Regulatory Guide 1.109 unless otherwise specified.

2) Equauon A 2 and A 3 from Reg Guide 1.109, Appendis A.

3) Table A 2 fi.... Reg Guide 1,109. Appendas A.

t

5. , _. .

1 !

! l ODCM Rev. 19 i i Page 110 '

l l 12/97 i

i Table 21 l Dose Factors for Noble Gas from Table B 1 of Reg Guide 1.109 Totalikxty Beta Skin Gamma Air Beta Air Dose l'a: tor Dose Factor Dose Fa; tor Dose Fa: tor Li(mrernjr Ni(mrad)T l Radiormclide Ki(mretnp)t per pCi'm per pCi'm ) Mi(mrad})T per pCi'm per pCi'm')

l Ar 4i 8 ME413 2.69E 03 930E43 3.28E 03 l Kr 83m 7.56E Oh 1.93E45 2.88E 04 l Ki85m 1.17E 03 1.46E-03 1.23E43 1.97E43 l Kr-85 16IE 05 134E 03 1.72E 05 1.95E-03 l Ki-87 5.92E 03 9 73E 03 6.lE 03 1.03E 02 l Kr 88 1.47E02 2 37E 03 1.52E 02 2.93E 03 l Ki-89 I 66E 02 1.0lE 02 1.73F 02 1.06E42 l Kr 90 1.56E42 7.29E413 1.63E412 7.83E 03 l Xe 131m 9.15E 05 4.76E 04 1.56E46 1.llE 03 l Xe 133m 2.51E 04 9.94E 04 3.27E 04 1.48E 03 l Xe-133 2 94E 04 3 06E 04 3.53E 04 1.0$E 03 l Xe-135m 312E-03 7.llE 04 3.36E-03 7.39E 04 l Xc 135 1.81E 03 186E 03 1.92E 03 2.46E40 l Xc-137 1.42E 03 1.22E 02 1.51E-03 1.27E 02 l Xe 138 8 83E 03 4.13E 03 9.21E 03 4.75E 03

l ODCM Rev. 19 Page 111 l 12/97 TABLE 2 2 l INGESTION INDMDUAL DOSE FACTORS OQ for Gaseous Eftluents UNITS FOR DEIOSITION PAT 1{ WAYS (Pathway Nurnters 15)are:

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-l Table 2-2 Rt Dose Factors Age: Infant Pathway: Ground BONE LIVER , THYROID KIDNEY LUNG- GILLI SKIN TBCDY' MAX VAL

H-3 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00' O.000E+00 0.000E+00 C-14: 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00' O.000E+00 CR-51 4.652E+06 4.652E+06 4.652E+06 4.652E+06 4.652E+06 4.652E+06 5.498E*06 4.652E+06 5.498E+06 HN-54 1.384E+09 1.384E+09 1.384E+09 1.384E+09 1.384E+09 1.384E+09 1.622E+09 1.384E+09 1.622E+09 FE-59 2.725E+08 2.725E+08 2.725E+08 2.725E+08 2.725E+08 2.725E+08 3.222E+08 2.725E+08 3.202E+08 CO-58 3.799E+08 3.799E+08 3.799E+08 3.799E+08 3.799E+08 3.799E+08 4.450E+08 3.799E+08 4.450E+08 Co-60 2.227E+10 2.227E+10 2.227E+10 2.227E+10 2.227E+10 2.. 7E+10 2.620E+10 2.227E+10 2.620E+10 (t ZN-65 7.155E+08 7.455E+08 7.455E+08 7.455E+08 7.455E+0B 7.455E+08 8.574E+08 7.455E+0B 8.574E+08 ?

SR-89 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.507E+04 2.160E+04 2.507E+04 SR-90 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.00GZ+00 j i

2R-95 2.453E+08 2.453E+08 '2.452E+08 2.453E+08 2.453E+08 2.453E+08 2.845E+08 2.453E+0B 2.845E+08 .j i

2.089E+07 I-131 1.720E+07. '1.720E+07 1.720E+07 1.720E+0! 1.720E+07 1.720E+07 2.089E+07 1.720E+07 I-133 2.450E+06 2.450E+06 2.450E+06 2.450E+06 7.450E+06 2.450E+06 2.980E+06 2.450E+06 2.980E+06 CS-134 6.917E+09 6.917E+09 6.917E+09 6.917E+09 6.917E+09 6.917E+09 8.070E+09' 6.917E+09 8.070E+09 i CS-136 1.508E+08 1.508E+08 1.508E+08 1.508E+08 1.508E+08 1.508E+08 1.709E+08 1.508E+08 1.709E+08 .I

[

CS-137 7.134E+10 1.134E+10 1.134E+10 1.134E+10 1.134E+10 1.134E+10 1.323E+10 1.134E+10 1.323E+10 I

BA-140 2.054E+07 2.054E+07 2.054E+07 2.054E+07 2.054E+07 2.054E+07 2.347E+07 2.054E+07 2.347E+07 "CE-141 1.365E407 1.365E+07 1.3650+07 1.365E+07 1.365E+07 1.365E+07 1.539E+07 1.365E+07 1.539E+07 j CE-144- 6.958E+07 6.958E+07 6.958E+07 6.958E+07 6.958E+07 6.958E+07 8.046E+07 6.958E+07 8.046E+07"

' I 1

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00+3000 0 00+3000*C 00+3000*O 00+3000 0 00+3000 0 00+3000~0 00+3000 0 00+3000~0 '00+3000*O >>I-33 00+3000 0 00+3000 0 00+3000*O 00+3000*O 00+3000*O 00+3000*O 00+3000 0 OC+3000*O' 00+3000*O ItI-23 00+3000*0 00+3000~0 00+3000*C 00+3000~0 00+3000 0 00+3000*O 00+3000*O 00+3000~0 00t2000*0 Oti-VH 00+3000*O 00+3000*O 00+3000*O 00+3J00*O 00+3000~0 00+3000*O 00+3000*O 00+3000*O 00+3000 0 LEI-S3 I

5 00+3000*O 00+3000*O 00+3000~0 00+3030 0 00+3000*O 00+3000*O 00+3000 0 00+3000*0- 00t2000*O 9EI-S3 3

00+3000*O 00+3000*O 00+3000*O 00+3000 0 00+3000'0 00+3000 0 00+3000*0 00*3000*O' 00,J000~0 kEI-53 l-l 00+3000 0 00+3000*O 00+3000*O 00+3000*O 00+3000*0 00+3000~0 00+3000 0 00+3000*O 00+3000*O EET-I i

j '00+3000 0 00+3000 0 00+3000*O 00+3000*O 00+3000 0 00t3000~0 00+3000*O 00+3000*O 00+3000~0 IEl-I

. '00+3000*O' 00+3000*O 00+3000 0 00+3000*O 00+3000*O 00+30E" i 0 0 + 3.F 'O 00+3000*O 00+3000*O 56-HZ 4 .

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l ODCM Rev. 19 Page 136 I l 12/97 TABLE 2-3 Assumptions Used in L m ek Gaseous l Ef fluent Ri calculations Symbol Description value Reference'8 l fi Fraction of annual intake of fresh, leafy vegetation grown 0.42 Site Spec.

locally f, Traction of annual intake of ptored vegetation grown locally 0.76 E-15 Y, vegetation area density (kg/m') 2.0 E-15 r Fraction of deposited particulates retained on vegetation 0.20 E-15 r Traction of deposited iodines retained on vegetation 1.0 E-15 SF Shielding factor of residential structures 0.7 E-15 t Period of buildup of activity in soil (see) 6.31E08 Site Spec.

tr Transport time milkman (sec) 1.73E05 c-15 tn Delay time for ingestion of stored feed by animals (sect 7.78E06 E-15 tn Delay time f or ingestion of leafy vegetable by man (sec) 8.6E04 E-15 tn Delay time for ingestion of other vegetable by man (sec) 5.18E06 E-15

t. Time between slaughter and consumption of meat animal (sec) 1.73E06 E-15 e Y, Grass yield (kg/m**2) 0.7 E-15 Y. Stored feed yield (kg/m**2) 2.0 E-15

(, weathering rate constant for activity on veg (seed) 5.73E-07 E-15 or Milk cow f eed casumption rate (kg/ day wet) 50.0 E-3 Q, Beef cattle consumption rate (kg/ day wet) 50.0 E-3 Og Goat feed consumption rate (kg/ day wet) 6.0 E-3 K Ground exposure (all age groups) (hr/yr) 8760.0 C-2*

BR Breathing Rate adult (m**3/yr) 8000.0 E-5 BR 3reathing Rate teen (m**3/yr) 8000.0 E-5 BR Breathing Rate child (m**3/yr) 3700.0 E-5 BR Breathing Rate infant (m*'3/yr) 1400.0 E-5

{f; Leafy veg consumption rate adult (kg/yr) 64.0 E-5

{f; Leafy veg consumption rate teen (kg/yr 42.0 E-5

{J; Leafy veg consumption rate child (kg/yr) 26.0 E-5

{jj Leafy veg consumption rate infant (kg/yr) 0.0 E-5

{js, Stored vag consumption rate adult (kg/yr) 520.0 "5-

_ {f s, Stored veg consumption rate adult (kgiyr) 630.0 E-5

{f, 8

Stored veg consumption rate adult (kg/yr) 520.0 E-5

{f, 3

Stored veg consumptien rate adult (kg/yr) 0.0 E-5 U, ' Cow milk consumption rate adult (1/yr) 310.0 E-5 U, Cow milk consumption rate teen (1/yr) 400.0 E-5 U. Cow milk consumption rcte child (1/yr) 330.0 E-5 U, Cow mila consumption rate infant (1/yr) 330.0 E-5 U, Goat milk consumption rate adult (1/yr) 23.0 Site Spec.

U, Goat milk consumption rate teen (1/yr) 29.0 Site Spec.

Un Goat milk consumption rate child (1/yr) 0.0 Site Spec.

U.p Goat milk consumption rate infant (1/yr) 0.0 Site Spec.

U, _ _ Meat consumption rate adult (kg/yr) 110.0 E-5 U, Meat consumption rate teen (kg/yr) 65.0 E-5 U., . Meat consumption rate child (kg/yr) 41.0 E-5 U, Meat consumption rate infant (kg/yr) 0.0 E-5 fr Fraction of year animals on pasture 0.75 Site spec.

f. Traction of feed from pasture when on pasture 0.39 Site Spec.

H Atmosphere absolute humidity (gm/m**3) 8.0 (4) l NOTES:

1) R6 values are calculated in accordance with the methodologies given in NUREG-0133.

2) The References refer to tables contained in Regulatory Guide 1.109 unless otherwise specified.

3) From Reg. Guide 1.109, Appendix C, Equation C-2

__ 4 From NUREG-0133, Section 5.3.1.3.

l l

l ODCM Rev. 19 i Page 137 i l 12/97 TABLE 2-4 Nearest Gascous Efiluent Dose Reaptor Distances (Meters)

Plure Grourxl inhalabon Vegetation Meat Cow Goat Dtrefu90 Pathums Egthway Pathway Pathway Pathum N %5 2574 3414 7562 0 NNE 805 805 1585 0 0 NE 1287 2414 1097 0 0 ENE %5 2896 3871 0 0 E %5 1770 1890 0 0 ESE 805 1931 4511 1770 1770 SE 1609 1770 7241 0 0 SSE 1609 1931 7224 7562 0 S 1287 1931 3018 2701 0 SSW 1609 2253 1433 2896 0 SW V4 %5 2835 4827 0 WSW 12o. 1287 2134 4505 0 W %5 3540 4084 0 0 WNW 1126 1126 0 0 0 NW 2092 2574 6660 0 0 NNW 1448 1931 6325 0 0 l

i l

- l- ODCM Rev. 19 Page-13:

5 l- 12/97 s

1 f

9 4

(

4 i

t 4

9 R

i APPENDIX A 9

5 e

i 1

e a

J J

.d 4

4 ..

1 4

i 4

i i

t i

4

l ODCM Rev. 19 Page 139 l 12/97 I

TABLE A 1 Technical SpeedicationODCM Matrix ODCM ODCM Techr.ical Section l Equation Specification

Requirement Section 11 3.3.7.1 I 3.2.1 I1 I2 1-3 14 1 3.7.12 3.3.I 21 (or 2 9) 2-2 (or 2 9) 24 (or 210) 2-5 (or 210) 3.I1.1.1 3.2.2 11 12 13 14 3.I1.1.2 3.2.3 15 1-6 17 3 11.1.3 3.2.4 1-8 1-9 3.I1.2.I 3.3.2 2 22 2-23

3. I 1.2.3 3.3.4 2 26 2-27 2-28 3.I1.2.2 3.3.3 2 24 2-25 3.I1.2.4 3.3.5 2-33 3.I1.2.7 3.3.6 24 2-5

Parts of, or the. entire Tech. Spec. Section, has tren transferred to ODCM sia T.S. amendment # 48 for Unit I and 11 for Unit 2.

l ODCM Rev. 19 '

Page 140 l 12/9'1 TABLE A-1 Technical SpecificationODCM Matrix ODCM ODCM Technical Section 1 Equation Enectfication' Reauirement Section.Il 6.9.1.8 3.6 1-5 1-6 17 2-24 2 25 2 26 2 27 2-28 3.I1.4 3.3.7 31 3.12.I 3.4.1 Section 11 App. B 6.9.1.7 3.5 15 3 12.3 3.4.3 16 1-7 2-29 2-30 2-31 2-32 3-2

Parts of, or the entire Tech. Spec. Section, has been transferred to ODCM via T.S. amendment # 48 for Unit I mxt 11 for Unit 2.

l ODCM Rev. 19 ;

Page 141 l 12/97 APDENDIX B PADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM -

SAMPLETYPE, LOCATION, AND ANALYSIS

l ODCM Rev. 19 Page 142 l 12/97 TABLE B-1 PageIof4 ODCM - Limerick Generating Station Fadiological Emironment,1 Monitoring Program Pathuar Station Code cation Collection Metixx! A nahy-Ic Direct '36S2 3.lka leet N of site I set of four (4) TLDs Gamma dose quarterly Site Botmdary 3SI 2,301 feet NNE of site from each location at (St 2,350 feet NE of site least quarterly 7S1 3 099 feet ENE of site 1053 2,648 feet F of site 11S1 2,017 feet ESE (.f site 1352 2,149 feet SE of site 14S1 3.319 feet SSE of site 18S2 1,390 feet S of site 21S2 977 feet SSW of site 23S2 2.793 feet SW of site 25S2 2,445 feet WSW of site 2653 2,088 feet W of site 29SI 2.886 feet WNW of site 3151 1,395 feet NW of site 3452 3,071 feet NNW of site Intermediate 36D1 18.527 feet N of site Distance 2El 25,112 feet NNE of site 4El 25,221 feet NE of site 7El 22,489 feet ENE of site 10El 20,R26 feet E of site 10F3 29,442 feet ESE of site 13E1 22,772 feet SE of site 16FI 26.603 feet SSE of site 19DI 18,439 feet S of site 20F1 27.648 feet SSW of site 24DI 20,972 feet SW of site 25DI 21,044 feet WSW 06 site 2MD2 20,231 feet W of site

'29El 26,110 feet WNW of site 31D2 20,446 feet NW of site

l ODCM Rev. 19 Page 143 l 12/97 i TABLE B-1 Page 2 of 4 F

Pathway Station Code Location Collection Method Analyses .

Intermediate 34El - 24.243 feet NNW of site Distance (cont'd)

Distant $111 C 130,742 feet NE of site and 6CI i1,305 feet NE of site Special . 9CI I1.377 feet E of site Interest 13Cl 14,980 feet SE of site ISDI 16,877 feet SE of site 1781 8,462 feet S of site 20DI 16,157 feet SSW of site 31DI 15,853 feet WNW of site II. Airborne Particulates 1053 2,648 feet E of site Approximately I efm Gross beta analysis 1151 ' 2,017 feet ESE of site continuous flow through on each neckly 14Si 3,319 feet SSE of site glass liber filter sample. Gaman 13Cl 14.980 feet SE of site which is collected spectrometry shall be 22GI C 93,619 feet SW of site weekly. done when gross beta exceeds ten times the yearly mesn ofcontrol station value.

Gross beta analysis done *24 hr after sampling to allow for -

Radon and Timron daughter decay.

Gamma Spec on quarterly composite.

j. ODCM Rev. 19 Page 144 _

l 12/97 ;

TABLEB-1 Page 3 of 4 Patimay Station Code Location Collection hiethod Analvsu lodine 10S3 2/>48 feet E of site A TEDA impregnated Iodine 131 1ISI 2,017 feet ESE of site flow-through cartridge 1451 3.319 feet SSE of site is connected to air 13Cl 14.980 feet SE of site sa npler and is 22G1 C 93,619 feet SW of site collected weekly at site filter change.

111. Water Curface 24SI C 1.058 feet SW of site Sampic collected from Gamma isotopic '

1381 9,225 feet SE of site a continuous water analysis monthly:

sampler, monthly. In event sampler is 11-3 on quarterly inoperable, neckly grab composite samples will be collected until sampler returned to senice.

Se liment 16C4 !),510 feet SSE of site A sediment sample is Gamma isotopic taken down stream of analysis each discharge semi-a.mually sample IV. Ingestion h1 ilk 1081 5,725 feet E of site Sample of fresh milk is Gamma isotopic and 1981 10,317 feet SSW of site collected from each I-131 analyses on 21B1 9,263 feet SSW of site farm biweekly when cows each sample 9GI C 62,30 8 feet E of site are on pasture (April) through October),

monthly at other times.

J.

.l ODCM Rev. 19 Page 145 l- 12/97 TABLE B-I Page 4 of 4 Pathway Station Code Location Collection Method Analpes Drinking 15F7 33,400 feet SSE of site Sample coi*ced from a Gross beta and gamma 15F4 45,514 feet SE of site continuous water isotopic monthly, 16C2 14.034 feet SSE of site sampler monthly In 28F3 C 30,81I feet WNW of site event sampler in H-3 on quarterly inoperable, urekly grab composite samples will be collected until sampler returned to senice.

Fish 16C5 9,25i feet SE of site Two species of Gamma isotopic 29CI C 13,725 feet WNW of site recreationally analyses on edible important fish portions.

(Predator and bottom feeder) sampled in season or semiannually if not seasonal. !

Food Two ofTsite locations of highest Samples of three (3) Gamma isotopic Products predicted annual arcrage ground different kinds of analysis i level D/Q and one location (15- broad leaf vegetat.on 30 km distance)in the least monthly when available ,

prevalent uind direction as if milk samplings is not I determined using the results of perfi>rmed. ;

the most recent annual Landuse '

Survey.

C = Control Location .

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

l ODCM Rev. 19 Page 146 '

l 12/97 0

t APPENDLX C 1

4 5

l ODCM Rev. 19 Page 147 l

12/97 ODCM Resision Process

1. REVISION PROCESS

a. The preparer shall ensure the ODCM contains program elements described in Technical Specifications 6.8.4 d,e and f.

b. All pages affected by the change shall contain resision bars in the margin indicating the area of the page changes and the date (month and year) of the change. Revision bars from previous revisions shall be removed.

c. Initiate an ECR in accordance with MOD C 9.

d. In addition to the requirements of LR-C 9. the following shall also be performed:

1. The preparer af the proposed change shall assemble an 00CM revision r -ckage. This package should contain:

a. Proposed page changes.

l b. Sufficient infonnation. appropriate analysis or evaluation to support the change.

c. A determination that the changes will maintain the level of effluent control required by 10CFR20.1301,10CFR20.1302,40 CFR Part 190,10CFR50.36a and Appendix ! to 10CFR Part 50.

d A 10CFR50.59 review prepared in accordance with administrative procedures.

e. Other documentation as required by administrative procedures.

2. The preparer shall obtain review of the ODCM revision package utilizing the SQR process in accordance with administrative procedures. This review should include:

l a. Branch Manager l b. Cross-disciplinary review (i e., HP, Chem, R/W, Nuclear Eng. Div. Programs Branch. EP). if required and l c. Review by Responsible Superintendent

3. Upon satisfactory completion of the SQR and responsible Supermtendent reviews, the preparer shall obtain PORC approval of the ODCM revision package.

11. APPROVAL

a. Upon satisfactory completion of PORC review and appropriate review / approval forms, the

! resised ODCM shall be forwarded to the Plant Manager for approval signature on the ODCM Cover sheet.

1

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

l~ ODCM Rev. 19 Page 148 l 12/97

!!!. ISSUANCE

a. The ODCM shall be issued as a complete document. Issuing page changes is not pennitted,

b. The ODCM shall contain a cover sheet indicating the ODCM revision number and a Table of Contents All pages of the ODCM shall be marked with the revision number and date.

c. The preparer shall forward the following to the Document Control Center:

1. Original ODCM for issuance.

4

2. The ODCM revision package.

3. 10 CFR$0.59 reviews.

4. All appropriate review / approval forms.

V. IMPLEMENTATION

a. Changes to the ODCM shall become effective upon approval of the Plant Manager.

l b. A copy of the complete ODCM shall be submitted to the NRC with th? Annual Radioactive Release Report for the period of the report in w hich the change to the ODCM was made.-

l I

1

4, l ODCM Rev. 19 Page 149

l 12/97 I

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ODCM, Rev. 19 Page 151 l 12/97

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REFERENCES
1. Regulatory Guide 1.109,
Calculation of Annual Doses to hian from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CTR Part 50, Appendk 1,* Resision I, U.S Nuclear Regulatory !
1 Commission. Washington. D C. 20$$5, October 1977.
2. Regulatory Guide 1.111, *hiethods for Estimating Atmospheric Transport and Dirpersion of Gaseous Emuents in Rouune Releases from Light Water-Cooled Reactors? Resision I, U.S. Nuclear Regulatory Commission.
Washington, D C. 20$55, July l'n7.
J A Regulatory Guide 1.112,
Calculation of Releases of Radioactne hiatenals in Gaseous and Liquid Emuents from i Light Water Cooled Power Reactors? U.S. Nuclear Regulatory Commission. Washington, D C. 20555, April 1976.
4. Regulatory Guide 1,113,
Estimating Aquatic Dispersion of Emuents from Accidental and Routine Reactor Releases for the Purpose of linplementing Appendix I? Revision 1. U.S. Nuclear Regulatory Cornmission.
Washington, D C. 20555, Apnl 1977.
5. U.S. Nuclear Regulatory Commission
Calculation of Releases of Radioactive hiaterials in Gaseous and Liquid Emuents from !! oiling Water Reactors (llWR GALE Code)? USNRC Report NUREG 0016, Washingtm, D C.
20$55, April 1976
6. U.S. Nuclear Regulatory Commission, *X0QD00, Program for the hiethodological Evaluation of Routine Emuent Releases at Nuclear Power Stations? USNRC Report NUREG-0324. Washington, D C. 20555, September,1977.
7. Title 10. " Energy," Chapter 1. CG1LofhdtIAUitgulau2M, Part 20. Appendix D. U.S. Government Printing Omce, Washington. D C 20402, January 1,1977.
H Title 10,
Energy,* Chapter 1 Code of Federal Heculaugg Part 100, U S. Government Pnnting Omcc, Washington. D C. 2n404, January 1,1977.
9. Title 40,
Protection of Environment? Chapter 1. Code of Federal Reculatiem. Part 14), U.S. Gmenunent Printing Omce, Washington, D C. 20402, January 1,1977.
10. Regulatory Guide 1.21, 'hleasuring, Es aluating, and Reporting Radioacthity in Solid Wastes and Releases of Radioactive hiaterials in Liquid and Gaseous Emuents from Light Water Cooled Nuclear Power Plants
Revision
1. U.S. Nuclear Regulatory Commission, Washington. D C. 20$55, June 1974.
II. Title 40, " Protection of Emironment? Chapter 1, Code of Federa!.Rerulations. Part 190, federal Register, Vol 42, No 9 Washington, D.C. 20402, January 13,1977.
12. U.S. Nuclear Regulatory Commission, "Short Tenn Diffusion Estimates? Section 23.4. Sandard Review Plarifer dit.Rguew of Saftty Anahsis lltports for Nutkar Power Plants LWR Edtugn. USNRC Report NUREG 75/087 Washington, D C. 20555, November 1975.
13. U.S. Nuclear Regulatory Conunission, Preparation of Radiological Emuent Technical Specifications for Nuclear Power Plants? USNRC Report NUREG-0133, Washir Ston, D C. 20555 October 1978.
l 14. Letter From Thomas E. hiarle), Director Omce of Nuclear Reactor Regulations. To Thomas E. Tipton Vice President and Director Operations, Nuclear hianagement and Resources Council,6/30/93,
i l
' ODCM Rev. 19 Page 163 12/97 I l l 1
t REFERENCES
15. ANSI N42.14 1991 (Rnision of ANSI N42.14 1978)
Calibration and Use of Germanium Spectrometers For the Measurement of Ganuna Ray Emission Rates of Radionuclides', Sect. 6.2.2 l
16. EML Procedures Manual, H L. Volchok and 0 dePlangue, Editors U S. Dept. Of Energy (Rnised Annually)
17. L A Curne, " Limits For Qualitative Detection and Quanutative Determination . Application to Radiochemistry *,
Analytical Cl;mistry, Vol. 40, pp $86 593 (TAllLE !!),1968 18 NUREG/CR 4(H)7, " Lower Limit of Detectiori: Definition and Elatorat;on of a Proposed Position for Radiological Effluent and Emironmental Measurements", prepared by NRC by L A. Cume (Chapter !!, Sect. D.2; Chapter 111, Sect. C,1), September 1984
19. Tech Spec. Section 1.24 (Definitions) ,
l
20. USNRC Genene Letter,89 01 i
{
1
] 21. Tech Spec. Section 6.14.
j 22. Tech. Spec. Section 6.5.1.6m,
23. Tech Spec. Section 6.5.3.
24 Tech. Spec. Section 6 8 4d, e and f. ,
25. Tech. Spec. Secuon 6.9.l.8/ODCM Control 1.3.6.
(
26 Tech. Spec Section 610.3m and n 4
27. UFS AR, Section i1.5 6.
28. Ilechtel, Inc.," Dilution Studies for Routine and Accidental Releases from Limerick Nuclear Plant into the Schuylkill River", March,1996. .
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