Text

Offsite Dose Calculation Manual.
	ML20024A650
Person / Time
Site:	Pilgrim
Issue date:	06/10/1983
From:	; BOSTON EDISON CO.
To:	;
Shared Package
ML20024A648	List: ML20024A647; ML20024A650;
References
	PROC-830610, NUDOCS 8306220009
	Download: ML20024A650 (88)
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PILCRIM NUCLEAR POWER STATION OFFSITE DOSE CALCULATION MANUAL A

BY: ENVIRONMENTAL AND RADIOLOGICAL HEAL 1R AND SAFETY GROUP Revision 0 - 6/10/83 I

BOSTON EDISON COMPANY 8306220009 830616 DR ADOCK 05000293 PDR

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PIl4 RIM NUCLEAR POWER STATION OFFSITE DOSE CALCULATION MANUAL

/

Prepared by: J (M> [ g, y,p T.L. So don C.E. Bowman Environmental and Radiological Senior Radiological Engineer Health and Safety Group Leader l

Date of Submittal: June, 1983

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Changes to this document shall be reviewed by the Operations Review Comittee and

' submitted to the Nuc1 car Regulatory Comission within 90 days from the date on

, which the changes become effective. All such changes shall be recorded below.

RECORD OF DoctMENT CHANGES REY. REVISION DOCIMENT SECTION NO. IDENTIFICATION OF CHANGE DATE AND PAGE INITIAL 0 original submittal 6/10/83 All Sections MMg O

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TABLE OF CONTENTS Section.

Page 1.0 Introduction 1-1 2.0 Liziti ; 0::f*:i:ss for Operation and Operational Objectives 2-1 3.0 P.:::::: T: int : 3 Monitor Description 3.1 Radioactive Effluent Release Point Description 3-1 3.2 Radioactive Effluent Monitoring System Description 3-2 3.3 Measurement Method During Releast 3-6 4.0 Calculational Methods 4-1 4.A Concentrations of Liquid Effluents 4-1 4.B Aquatic Foods (Fish, Shellfish) 4-1 4.C Shoreline Deposits 4-2 4.D Camma Air Dose 4-3 4.E Beta Air Dose 4-3 4.F Total Body Dose 4-3 4.C Skin Dose 4-3 4.H Cround Plane Deposition 4-3 4.1 Inhalation 4-3 4.J Leafy Vegetation Digestion 4-4 4.K Milk Ingestion 4-4 5.0 Receptor Locations, Hydrology and Meteorology 5-1 6.0 Monitor Set Points 6-1 6.1 Liquid Effluent Monitor 6-1 l

6.2 Caseous Effluent Monitors 6-1 7.0 Radiological Environmental Monitoring Sample Locations 7-1 8.0 Description of Radvaste Systema 8-1 8.1 Liquid Radwaste Systen 8-1 8.2 Treated Caseous Radvaste Systen 8-2 l

j 9.0 References 9-1 Appendix A Data Required for Effluent Calculations A-1

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Appendix B Definition of the Lower Limit of Detection B-1 iii

LIST OF PIGURES Figure Number Paggt 3-1 Stack Gas Radiation Monitoring System 3-7 3-2 Reacte- *fildin ":nt Radiation Monitoring System 3-8 3-3 Proces: Liquid R:diation Monitoring System 3-9 7-1 Location of offsite Thermoluminescent Dosimeters, Air Particulates and Iodine Monitoring Stations 7-11 7-2 Location of onsite Thermoluminescent Dosimeters, Air Particulates and Iodine Monitoring Stations 7-12 7-3 Location of offsite Monitoring Stations (Water, vegetation and Milk) 7-13 7-4 Typical Mo11use, Algae and Sediment Sampling Stations 7-14 8-1 Liquid Effluent Treatment System Schematic 8-3 8-2 Gaseous Effluent Treatment System Schematic 8-4

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LIST OF TABLES l

Table Number Page 3-1 Radiation Effluent Monitor Data 3-5 5-1 Critical Receptor Locations and Atmospheric Dispersion Factors 5-2 7-1 . Operational Radiological Environmental Monitoring Program 7-2 7-2 Air Par ticulates, Casecus Radioiodine, and Soil Surveillance Stations 7-7 7-3 External Camma Exposure Surveillance Stations (TLD) 7-8 7-4 . Maximum Values for the Lower Limits of Detection (LLD)a 7-10 V

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1.0 Introduction , l s

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I The purpose of the Offsite Dose Calculation Manual is: , ,

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a. to identify the applicabli effluent release limits defined by the s

Pilgrim Nuclear Power Station - Unit #1 (PNPS-1) Technical Specifications, s b.

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. to identify the equipmdnt,9aethods,.equationr, and data used to verify 4

-compliance with these offsite release limits. 3.

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This manual is structured such that it.is unnecessary to refer to other '

documents to perfo're the ' indicated calculations. All of the*A'pplica67e?

equations and data are contained within this document. Reference t'o cthhr '

documents should onlyLbe ' required if the reader needs to verify the appro; priateness of.information contained herein. '

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2.0 Limiting condition for operation and operational objectives Table 2.1 presents a summary of the limiting condition for Operation con-tained in Technical Specification sections 3.8.A. 3.8.C. 3.8.D and 3.8.F and also the operational objectives contained in Technical Specifica. tion sections ,

7.2, 7.3, 7.4 and 7.5. j i

This table is intended to serve as a summary of the contents of the Technical g Specifications and does not, in itself establish limits. The Technical ;

Specifications should be consulted for exact wording and specifics. .

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2-1

Table 2.1 4

Limiting Technical Conditions for Specification ODCH Applicable Exposure I

Operation Section Section(s) Limits Period Required Action Liquid Effluent 3.8.A 4.A 10CFR20 Instantaneous Reetore concen-Concentration tration to within limite Liquid Waste 3.8.C 4.5, 4.C 0.06 mren W.B. Projected for Operate Liquid Treatment 0.2 mren Organ 31 daye Waste Treatment Systen Geseous Effluent 3.8.D 4.F. 4.C. 500 aren/yr Instantaneous Restore release i Dose Rate , 4.H . 4. I W.R. from Noble rates to within 4.J. 4.K gance specificatione 3000 mres/yr Skin from Noble w gasee 0 1500 ares /yr ,

Organ from particulates Caseous Effluent 3.8.F 4.D 4.E 0.2 mrad gamma Projected for Operate Caseous Treatment 0.4 erad beta 31 daye Waste Treatment System Operational Objectives Dose-Liquide 7.2 4.5, 4.C 1.5 mren W.H. Calendar Report if 5 mrem organ Quarter exceeded l

Dose-Liquide 7.2 4.5, 4.C 3 mrem W.B. Calendar Report if 10 aren Organ Year exceeded Done-Noble Casee 7.3 4.D 4.E 5 mrad gamma Calendar Report if l

10 mrad beta Quarter exceeded l

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Table 2.1 - Continued Technical Operational Specification ODCM Applicable Exposure Objectives Section Section(s) Limits Period Required Action i

l Dose-Noble Cases 7.3 4.D 4.E 10 mren gamma Calendar Iteport if 20 mres bets Year exceeded Dose-I-131, I

Particulates, 4.H . 4. I . Calender l'eport if H-3 7.4 4.J. 4.K 7.5 mrem organ Quarter .xceeded Dose-I-131, Particulates, 4.H , 4. I . Calendar ieport if H-3 7.4 4.J. 4.K 15 aren Organ Year exceeded Total Dose 7.5 4.5, 4.C. 25 aren W.R. Calendar Report if 4.D. 4.E. 75 mres Thyroid Year exceeded 4.F. 4.C,

'j8 4.H. 4.1, W

4.J. 4.K NOTE: W.B. means whole body.

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3.0 Release Point and Monitor Description 3.1 Radioactive Effluent Release Point Description (10) 3.1.1 Main Stack Cas Release The processed gases from the unit are routed to the main stack for dilution and elevated release to the atmosphere. The main 66.ca au continuously monitored by a radiation monitor.

uuution air input to the stack is provided to reduce the hydrogen in the air ejector off-gases to a concentration of less than 4 percent by volume. Dilution air is supplied by two full capacity fans located in the filter building at the base of the main stack. The stack is designed such that prompt sixing of all gas inlet streams occurs in the base to provide prompt dilution of hydrogen and to allow location of sample points as near to the base as possible.

The main stack is a pipe with a top elevation of 400 feet MSL*.

The main stack is supported by the filter butiding. The filter building is a reinforced concrete structure which houses the dilution fans, off-gas filters and heaters. The main stack is located 700 feet northwest of the reactor building.

3.1.2 Reactor Building Exhaust Vent Release Air from areas containing potential sources of radioactive contamination such as the reactor building, radwaste building basement and turbine building basement are discharged through the reactor building exhaust vent. Normal airflow is routed from lesser to progressively greater areas of radioactive contamination potential prior to final exhaust.

The operating floor ventilation is normally supplied with 40,000 cfm of filtered and tempered outside air which enters the reactor building through louvers in the east wall. Air is exhausted from the operating floor through ducts located in the roof truss area and the south wall area adj acent to the floor. Additional exhaust ducts are located above the water level in the fuel pool, steam dryer and separator reactor cavity.

Two operating floor exhaust fans, each rated at design capacity, are located in the main fan room cutside the reactor building.

These fans discharge into the main exhaust plenum at the base of the reactor building vent.

Two contaminated area exhaust fans, each rated at d,esign capacity, are located in the reactor building. The fans discharge to the main exhaust plenum at the base of the reactor building. An additional smaller exhaust fan, located in the reactor building.

Mean Sea Level 3-1

exhausts only from the control rod drive maintenance shop and discharges to the main exhaust plenum. Constant volume control is maintained by inlet vanes which are automatically positioned.

The reactor building exhaust vent is square in cross-section extending from the top of the main exhaust plenua to the discharge point at elevation 182 feet MSL.

3.1.3 Liquid Radiation Waste Effluent Release The liquid radwaste discharge header receives discharge from the chemical radwaste monitor tank pumps, the clean radwaste treated water transfer pumps and the miscellaneous waste drain tank pump. The header provides controlled discharge through either a low flow discharge path or a high flow discharge path. The common discharge from both the low and high flow-paths is moni-tored for radiation.

The monitor trips the discharge pumps, closes the flow control valves, and provides alara on high radiation. The liquid radwaste effluent is finally discharged through an outlet diffuser to the circulating water discharge canal.

In addition, batch releases from sources other than the Radwaste Tanks directly to the environment are permitted provided at least two independent samples are analyzed in accordance with Specifi-cation 4.8.A.1, an independent verification of the release rate calculations is performed and, an independent verification of the discharge valving is performed. Concentrations released to unrestricted areas must be limited to the values specified in j 10CFR20.

l 3.2 Radioactive Effluent Monitoring System Description (8, 9,10) 3.2.1 Main Stack Gas Monitoring System l

l The main stack gas monitoring system (Figure 3.1) consists of two individual channels. Each channel consists of a gamma-sensitive scintillation detector and a log (7 decade log) count rate monitor that includes a power supply and a meter. Both channels are recorded on a two-pen recorder located in the main l control room. Both channels are connected to the 24 volt DC power bus, and to the AC Radiation Protection System via a transfer switch to the emergency diesels.

Each monitor has two upscale trips and one downscale trip. Each trip initiates an alare in the main control room, but no control action is provided. The upscale alarms indicate high radiation, and the downscale alarm indicates instrument trouble.

To monitor the main stack gas effluent, a sample is drawn through an isokinetic probe which is located in the stream assure repre-sentative sampling. The sample passes through two shielded cham-3-2

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

bers where the radiation level of the stack gas is measured by two scintillation detectors, one located in each shielded chamber.

The system also provides for monitoring todine and particulates by the use of filters in the gas sampling monitoring stream.

The filters are routinely analysed in the laboratory.

Each individual channel includes a built-in check source and a

. purge line to purge the stack gas from the sampling chamber.

Both the purge valve and the check source are operated from the main control room. Each channel is calibrated by labe:ctory analysis of a grab sample in the offgas line. Alarm trip circuits can be tested using a test source.

3.2.2 Reactor Building Exhaust Vent Monitoring System 1

The reactor building exhaust vent monitoring system (Figure 3.2) consists of two channels. Each channel consists of a gamma-sensitive detector and a log (7 decade log) count rate monitor that includes a power supply and a meter. Both channels are recorded on a two-pen recorder located in the main control room.

Both channels are connected to the 24 volt DC power bus, and the AC Radiation Protection System via a transfer switch to the emergency diesels.

Each monitor has two upscale trips and one downscale trip. Each i trip initiates an alare in the main control room, but no control action is provided. The upscale alarms indicate high radiation;

, and the downscale alarm indicates instrument trouble.

To monitor the reactor building exhaust vent gas effluent, a l

sample is drawn through an isokinetic probe which is located to assure representative sampling. The sample passes through two l shielded chambers where the radiation level of the gas is measured by two scintillation detectors, one located in each shielded chamber.

l The system also provides for monitoring iodine and particulates by the use of filters in the gas sample monitoring stream. The filters are routinely analyzed in the laboratory.

Each individual channel includes a built-in check source and a purge line to purge the gas from the sampling chamber. Both the purge valve and the check source are operable from the main control room. Alara trip circuits are tested using test signals.

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3.2.3 Liquid Radiation Waste Effluent Monitoring System The liquid radiation vaste effluent monitoring system (Figure 3.3) consists of one channel (7 decade log). This channel is connected to the 24 volt DC power bus.

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The channel includes a scintillation detector, a radiation monitor and a strip chart recorder. The detector is located in a shielded sampler that is located in a section of the radwaste licuid discharge header to minimi se background radiation. The monitor and recorder are located in the main control roca.

The channel has an upscale trip to indicate high radiation level and a downscale trip to indicate instrument trouble. The upscale trin al arm = in the main control room, trips the monitor tank pumps and terminates the discharge. The downscale trip alares ta the asin control room. The waste discharge valve is the isolation control device for the liquid radwaste effluent stress and it is automatically closed when the alare is tripped. There are two waste discharge valves, one is situated on a two inch line and the other is situated on a one inch line. Both valves are located af ter the radiation vaste effluent monitor, but prior to the discharge canal. The valves are air operated valv es . The vaste discharge valves are: A07216A and SV7216A, a 2 inch line; and A07216B and SV7216B, a 1 inch line. The power source is the 24 volt DC power bus.

Alara trip circuits can be tested using test sign al s. The channel is calibrated by laboratory analysis of a grab sample from the liquid radwaste system.

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TAB 12 3-1 RADIATION EFFLUENT MONITOR DATA Effloest Steek Cas taaetor 31da. vent Item % nitore Diannel 1

O annel 2 . mennel A '

m aanal B "IO I"I****

e a Meovfecturer CZ CE SE e CE CE 8

N oel lhaber 194I900CT f194I900C11 194I900C11l194I900C11 194It00c3 krMN&r 6.343.901 FrA '6.SSC.FA6.343 6.342.995 FFA 62 342.790 PRM, , 907 6.5MJ33 e 6.52.789e 6.342.788 FEM Scale eye l eye spo l eye eye Range 10-1-10' 10'I-100 10'I-100 0 i

l10*I -10 10*I-100 r ar 24v. oc jaar,ac 24v. sc j 24v. oc 24v. oc I**'*I'* Panel 910 8 Panel C910 Panel C910 ; Penal C910 Panel 910 see att eeSe*4 Figure 3.1 __ see attached Finure 3.2 ese attached Firure 3.3 Installation Date 8/20/71 8/20/71 9/13/71 f8/20/71 lt/20/71 Surve111amee Test

a. ne11y Chenmal Check Channel Cheek rh anal check

b. noethly Source Chech Source Check --

c. Wrterly Ctmanel Fumettomal Test f h nmal Fenecional Test Channel Fumettomal Test Calibratism a !

a. Omerterly check eeured theek eeure theek somree

b. It months Isown radiet,' ion soaree Eneveradia)tionsoareeKnows radiatioe source Alats Set Potata l l

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. 3.3 Meesurcoent M2thod During Raleces (5, 7,10)

, 1. Caseous Effluent The gaseous effluent radiation level is continuously monitored as it is being vented to the atmosphere.

2. Liquid Effluent Prior to the release of any liquid waste, a sample of the release is collected and analyzed for gross beta and gross gamma activity, and the specific activity of each release is determined by isotopic analysis. The waste discharge tank is recirculated for 60 minutes prior to the collection of a sample. The release of any liquid waste is controlled on a mixed MPC* basis. At least one dilution water pump is to be in operation at the start of the release. The specified waste discharge flow rate must be at least 10% less than the maximum vaste discharge flow rate and not to exceed 200 GPM.

The discharge of the liquid effluent is made from the liquid radwaste discharge header.

3. Limitations

a. Gaseous Effluent

1) PNPS Technical Specifications for gaseous release values

b. Liquid Effluent

1) PNPS Technical Specifications for liquid release values

2) If one pump is used to discharge the liquid waste and fails, the release is immediately discontinued.

3) If the discharge flow rate recorder fails, the release is immediately discontinued.

Maximum Permissible Concentration 3-6

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, 4.0 Calculations Methods This section presents the calculational specifics required to demonstrate compliance with each of the technical specification limits identified in Section 2.

The equations in the section are based on the equations and caleulational methods described in Reference 1. These equations have, in some cases, been presented in a slightly different form in an effort to simplify their use.

4.A Co ............. .! L*3. d Effluents The following equation shall be used to determine the discharge flow rate such that concentrations of radioactive effluents released to unrestricted areas do not exceed the limits shown on Table 2.1 of this manual:

DFR = CW / ( }] Cvi / MPCg )

i where:

DFR = Maximum discharge release rate of liquid effluent (gal / min).

CW = Flow rate of dilution water (gal / min).

C ,1 = Concentration of nuclide i in the liquid waste discharge volume prior to any dilution as determined by analyses or estimates based on prior experience (uCi/ce). .

MPCi = Maximum Permissible Concentration of each nuclide i from Table 2.1 of this manual (uCi/cc).

Doses from Liquid Effluents The following equations shall be used to estimate the dose or dose commitment incurred during any per13d due to the release of a quantity of radioactive liquid effluents during that period.

4.B Aquatic Foods (fish, shellfish)

U, Mp -A tp t Rapj = 1100 - p, Qi B ip Dnipj e i

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Iapj = 110,000 Qg T g D ,gp ) ,e 1-e F t where:

Bgp is the equilibrium bioaccumulation factor for nuclide i in pathway p, expressed as the ratio of the concentration in biota (in pC1/kg) to the radionuelide concentration in water (in pCi/ liter), in liters /kg from Table A-1; Da gpj is the dose factor, specific to a given age group a, radio-nuclide 1, pathway p, and organ j, which can be used to calculate the radiation dose from an intake of a radionuclide, in area /pC1, or from exposure to a given concentration of a radionuelide in sediment, expressed as a ratio of the dose rate (in area /hr) and the areal radionuelide concentration (in pC1/m2), from Table E-6;

F is the average flow rate of the liquid effluent for the '

period in question, in ft /sec; 3 Mp is the mixing ratio (reciprocal of the dilution factor) at the point of exposure (or point of harvest of aquatic food), dimensionless from reference 2, 0.2; Qi is the quantity of nuclide 1, in Curies released during the period in question; Rapj is the total dose to organ j of individuals of age group a from all of the nuclides i in pathway p, in area for the period in question; tb is the period of time for which sediment or soil is exposed to the contan.inated water, 1.31 c 105 hours0.00122 days 0.0292 hours 1.736111e-4 weeks 3.99525e-5 months ; Ti is the radioactive half life of nuclide 1, in days; tp is the average transit time required for nuclides to reach the point of exposure from Table E-15, 0.0 hours0 days 0 hours 0 weeks 0 months ; Up is the usage factor that specifies the exposure time or intake rate for an individual of age group a associated with pathway p, in hr/yr, 1/yr, or kg/yr from Table E-5; W is the shoreline width factor, dimensionless 0.5; Ag is the radioactive decay constant of nuclide 1, in hr-I; 1100 is the factor to convert from (Ci/yr)/(ft3/sec) to pCi/ liter; and 4-2

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110,000 is the factor to convert from (Ci/yr)/(ft 3/sec) to P Ci/11ter and to account for the proportionality constant used in the mediment radioactivity model.

Doses from Caseous Effluents The following equations shall be used to estimate the dose or dose commitment incurred during any period due to the release of a quantity of radioactive gaseous effluents during that period.

4.D Canaa Air Dose (Noble gases) 0 D Qg DFf

=3.17x101(b Q y) i 4.E Beta Air Dose (Noble gases) fX) p Dp = 3.17 x 100{ --

( Q, / u l5 Qg DF g 1

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DT = 3.17 x 10' Sy! Qg DFB g i

l 4.G Skin Dose (Noble gases) ,

0 DS = 1.11 *3.17 x 10' S y - Qg DF + 3.17 x 10 1 -

Qg DFS g i i 4.H Ground Plane Deposition (Halogens, Particulates and others)

C T C Dj = 8760 Sy 4 Cg DFGgj 12 . _Agt .

where: C I Qg 1-e 1 (QJ - -

4.1 Inhalation (Halogens, Particulates and others) fXT

= 3.17 x 10' R, J Qg DFA gj, i

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. Dt js a 1 13 8

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C = 1.2 x 10 QT for R - 3 C

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active particulates 4.K Non-Leafy Vegetation Ingestion (Halogens, Particulates and others)

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= 2.2 x 10 p Qg4 for C - 14 C

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active particulates 4.L Milk Ingestion (Halogens, Particulates and others)

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Where:

Ai ty Y

C" = F , C Qp e 1 i C =f p f, CP + (1 - fp ) CS+fp (1 - f,) CS i

j l

where: x C,C8 P = 1.2 x 107 QT --- /H for H - 3 C

7 C,C8 = 2.2 x 10 p 034(- -f for C - 14 C

e l

l 4-5

-A Ei t, -

rDi r 1-e CF = 5.5 x 10 71 ---

IQi --5------------e-- +

t (Qt y y v Ei

-Ati h- -

8, 1 1-o

____.r.____________ -

P Ag -

-A Ei te" Di r 1-e 8

C S = 1.1 x 10 l qi __,____________,_ ,

t Q) (___ y y

- v Ei

-At" ib -

Biy 1-e - A i(90 days)

____m.___________- e P Ag -

where:

Y 6 DFi , DFg are the gamma and beta air dose factors for a uniform semi-infinite cloud of radionuclide i, in arad m 3/pCi-yr; Y

D,D 0 are the annual gamma and beta air doses in arad for the period in question; Qi is the quantity of nuclide i, in Curies released during the period in question; 3.17 x 104 is the number of pCi per Ci divided by the number of seconds per year; X

is the appropriate value of atmospheric dispersion factor l Qc used to estimate group level airborne concentration of t pollutants in sec/m3 (see Section 5);

X is the appropriate value of gamma atmospheric dispersion Qy factor used to estimate ground level gamma dose rate from an elevated or ground level plume in sec/m3 (see Section 5);

D is the deposition rate considering depletion and decay in transit to the location in question, in a-2 (see Section 5);

Q 4-6 l

I Sy is the attenuation factor that accounts for the dose reduction due to shielding provided by residential struc- .

l tures, dimensionless, 0.7; 1.11 is the average ratio of tissue to air energy absorption coefficients; DFSg is the beta skin dose factor for a semi-infinite cloud of radionuclide i, which includes the attenuation by the outer

";. 2" 1.yer of skin, in area-a /pci-yr 3 from Table B-1; DS . ... . kin dose in ares, for the period in question; DFAgj. is the inhalation dose factor for radionuclide i, organ j, and age group a, in eres/pCi from Tables E-7 thru E-10; DFBt is the total body dose factor for a semi-infinite cloud of the radionuclide i, which includes the attenuation of 5 g/cm2 of tissue, in arem-m 3/pci-yr from Table B-1; DT. is the total body dose due to immersion in a seni-infinite cloud in eres for the period in question, s

CG is the ground plane concentration of radionuclide i, in i pC1/m2 ;

DFGi j is the open field ground plane dose conversion factor for organ j from radionuclide i, in mrem-m /pCi-hr 2 from Table E-6; DG is the dose to the organ j from direct exposure to the 3 contaminated ground plane f rom all radionuclides, in area for the period in question; 8760 is the number of hours in a year; and DA ja is the dose to organ j of an individual in the age group a due to inhalation, in area for the period in question.

Where: '

C#, L C,CV are the concentrations of radionuclide i in milk, leafy i i i

,egetables and non-leafy vegetables, respectively, in pCi/kg or pCi/1; D", DL, DY is the dose to the organ j of an individual in age group ja ja ja a froe ingestion of milk, leafy vegetables or non-leafy vegetables, in aren for the period in question.

4-7 g- - , , , , , , ,,---,---ng,--.. ,,,.-~---n,-.. , - - - - . ,, - , . - - - - , -__ , - , - - - - -

. DFIi ja is the ingestion dose factor for radionuclide i, organ j, and age group a, in area /pci from Table E-11 thru E-14; f5, fg are the respective fractions of the ingestion rates of produce and leafy vegetables that are produced in the garden of interest 0.76 and 1.0 respectively; U", UL , yV are the annual intake (usage) of milk, leafy vegetables a a a and non-leafy vegetables, respectively, for individuals in the age group a, in kg/yr or 1/yr (equivalent to U,p) from Table E-5; F. is the average fraction of the animal's daily intake of radionuclide i which appears in each liter of milk, in days / liter from Table E-1; QF is the amount of feed consumed by the animal per day, 50 kg/ day for cows, 6 kg/ day for goats; tf is the average transport time of the activity from the feed into the milk and to the receptor, 2 days; P

C,C S is the concentration of radionuclide i on pasture grass i i and in stored feeds, respectively, in pCi/kg; fp is the fraction of the year the animals graze on pasture 0.5; f, is the fraction of daily feed that is pasture grass when the animal grazes on pasture 1.0; l tb is the time period over which the accumulation is evaluated.

l 15 years; 1 x 1012 is the number of pCi per Ci; R. is the annual air intake for individuals in the age group a, in a 3/yr from Table E-5; Q14 is the release of C-14, in Ci for the period in question; p is the fract,ional equilibrium ratio, dimensionless 1.0; QT is the release of tritium, in Ci for the period in question;

( H is the absolute humidity of the atmosphere, 8.0 g/m 3;

{

t 3,1 is the concentration factor for uptake of radionuclide i from soil.by edible parts of crops, in pCi/kg (wet weight) per pCi/kg dry soil from Table E-1;

4-8 l

1 l

r is the fraction of deposited activity retained on crops, dimensionless from Table E-15; to is the time period that crops are exposed to contamination during the growing season, from Table E-15; th is the holdup time that represents the time interval between harvest and consumption of the food, from Table E-15 hours; P **"a effective " surface density" for soil, 240 kg/m2 (dry soil);

Y, is the agricultural productivity (yfeld), in kg/m2 (wet weight) from Table E-15; A

Ei istheeffectiverymovalrateconstantforradionuclidei from crops, in hr~ , where Ei " i+ w' i is the radio-active decay constant, and v is the removal rate constant for physical loss by weathering w = 0.0021 hr-1; Ag is the radioactive decay constant of nuclide 1, in hr-I i

l l

l 4-9

5.0 Receptor Locations, Hydrology and Meteorology The purpose of this section is to identify those receptor locations which represent critical pathway locations and the methods used to estimate dilution l and dispersion factors for these locations.

For liquid effluent pathways the conservative value of 0.2 is chosen for the a1xing ratio. This value is consistent with the assumptions given in Regula-tory Guide 1.109I and the Pilgris Station Unit 1 Appendix I Evaluation . 2 It tuplieg *k=* *k. a-***-al receptor obtains fish and shellfish from the edge of the initial mixing zone.

For gaseous effluent pathways Table 5-1 lists the critical locations for receptors and conservative atmospheric dispersion factors for each location.

In order to estimate atmospheric dispersion and deposition factors for each of these locations, a computer code supplied by the Tankee Atomic Electric Company was used. The code, AEOLUS 3 , was used to calculate quarterly average values of dispersion and deposition factors.

Meteorological data for a three year period, January 1,1977 to December 31, 1979, were used for these analyses. The most conservative quarterly average values of ground level average atmospheric dispersion factor before depletion, ground level average atmospheric dispersion factor af ter depletion, average gamma dilution factor and average deposition rate for the 3 data years were chosen for the critical receptors.

The technique used to estimate ground level gamma doses from an elevated or ground level plume is based on the sector average finite cloud model of Regulatory Guide 1.109 1

. The equation has been rearranged into a form similar to the standard semi-infinite cloud equation thereby allowing the use of a

" gamma Chi /Q" which include the ef fects of plume dimensions, gamma energy mix, atmospheric and geometric attenuation, etc. (See Reference 3 and 4 for a detailed discussion).

A 5-1 l

Table 5-1 Critical Receptor Locations and Atmospheric Dispersion Factore Atmospheric Dispersion Factor

1) Reactor Ru11 ding Vent

2) Main Stack Technical Specification X_ X X_ D_

Section Qc Q DEP Qy Q 4

3.8.D Gaseous Effluent Dose Rate a Site Boundary (I) 7.40 x 10-6 7.04 x 10-6 4.69 x 10-6 5.22 x 10-8 4.69 x 10-7 4.69 x 10-7 1.68 x 10-6 2.92 x 10-9

' Nearest Garden (2) 7.40 x 10-6 7.04 x 10-6 4.69 x 10-6 5.22 x 10-8 4.69 x 10-7 4.69 x 10-7 1.68 x 10-6 2.92 x 10-9 Y

ha Nearest Milk Antual(3) 4.29 x 10-7 4.21 x 10-7 1.70 x 10-7 7.93 x 10-10 3.73 x 10-8 3.70 x 10-8 3.22 x 10-8 2.46 x 10-10 3.8.F Gaseous Effluent Treatment Site Boundary (I) 7.40 x 10-6 N/A 4.69 x 10-0 N/A

4.69 x 10-7 N/A 1.68 x 10-6 N/A i

I 7.3 Dose - Noble Canes i

Site Boundary (I) 7.40 x 10-6 N/A 4.69 x 10-6 N/A 4.69 x 10-7 N/A 1.68 x 10-6 N/A 7.4 Dose - I - 131 and Othere Site Moundary(I) 7.40 x 10-6 7.04 x 10-6 N/A 5.22 x 10-8 4.69 x 10-7 4.69 x 10-7 N/A 2.92 x 10-9

Table 5-1 Critical Receptor Incations and Atmospheric Dispersion Factors (Continued)

Atmospheric Dispersion Factor

1) Reactor Building Vent

2) Main Stack Technical Specification X X X D Section Qc _ Q DEP Qy

(

Nearest Garden (2) 7.40 x 10-6 7.04 x 10-6 N/A 5.22 x 10-8 4.69 x 10-7 4.69 x 10-7 N/A 2.92 x 10-9 Nearest Milk Animal (3) 4.29 x 10-7 4.21 x 10-7 N/A 7.93 x 10-10 3.73 x 10-8 3.70 x 10-8 M/A 2.46 x 10-10 7.5 Total Dose u' Site Boundary (I) 7.40 x 10-6 7.04 x 10-6 4.69 x 10-6 5.22 x 10-8 b 4,69 x 10-7 4.69 x 10-7 1.68 x 10-6 l 2.92 x 10-9 Nearest Carden(2) y,40 x 30-6 7.04 x 10-6 4.69 x 10-6 5.22 x 10-8 4.69 x 10-7 4.69 x 10-7 1.68 x 10-6 2.92 x 10-9 Nearest Milk Animal (3) 4.29 x 10-7 4.21 x 10-7 1.70 x 10-7 7.93 x 10-10 3.73 x 10-8 3.70 x 10-8 3.22 x 10-8 2.46 x 10-10 NOTES:

(1) " Site Boundary" means the location at or beyond the boundary of the restricted area with the highest calculated dispersion and/or deposition factor.

(2) " Nearest Carden" is considered to be the name as the site boundary due to the abundance of small gardens near Pilgrim Station.

(3) " Nearest Milk Aninni" in presently considered to be at the Plymouth Plantation 2.2 Miles West of Pilgrim Station.

6.0 Monitor het Points 6.1 Liquid Effluent Monitor The set point for the liquid effluent monitor is established as follows:

1) Prior to a liquid batch release, the waste discharge tank is recirculated for 60 minutes and a sample is taken.

2) This sample is analyzed to determine the concentrations of each detectable isotope in uCi/cc. (See Appendix B for the definitions of IdGer limit of detection.)

3) The efficiency (in counts /sec per uCi/ce) of the liquid discharge monitor is calculated for the isotopic mixture observed (or the efficiency is estimated based on prior release experience).

4) The setpoint for the liquid effluent monitor is calculated as follows:

S3=E*C+B g where:

S1 = Liquid monitor setpoint for steady-state, equilibrium discharge (counts /sec).

E = Efficiency of liquid discharge monitor in counts /see per uC1/cc for the mixture of isotopes observed in the grab sample.

C = Total specific gamma activity of the grab sample.

Eg = Measured background count rate of the monitor with no sample present (counts /sec).

The setpoint will ensure that the concentration of liquid effluents discharged does not increase above the value for which the maximum permissible discharge flow raea was established (see Section 4.A of this manual).

6.2 Caseous Effluent Monitors The only components of the station's gaseous effluent discharge con-tinuously monitored are the noble gases. The method of determining the monitor Ri and Hi-Hi alarms is as follows:

1) At the time a gas grab sample is taken at the discharge point, the gross monitor reading is recorded (in counts /sec).

6-1

2) The results of the isotopic analyses on this sample in terms of

, uC1/cc of each isotope detected are used along with estimates of gaseous discharge flow rate (SCFM) to determine the current release rate of each detected isotope in uCi/sec.

3) These calculated release rates (in uCi/sec) are used along with the equations given in Section 4.D of this manual to calculate the maximum offsite dose rate due to noble gases.

4) Tha -=**a at this calculated dose rate to the instantaneous dose rate limit (500 ares /yr for the total body and 3000 area /yr fn- th- =bfa, or some fraction thereof) is used to scale the observed monitor reading at the time at which the grab sample was obtained as follows:

DR Lg it Sc = (C .- B g ) ------------ + B g DRC alculated where:

Sg = gaseous monitor setpoint corresponding to 500 area /yr to the total body or 3000 area /yr to the skin whichever is more limiting (in counts /sec)

Rg = measured background count rate at the sampler with no sample present (in counts /sec)

C, = observed monitor reading at the time of the grab sample (in counts /sec)

DRLimit = the applicable dose rate limit 500 area /yr for the total body or 3000 mrea/yr for the skin or some fraction thereof DRCal = the most restrictive calculated dose rate from the methods of Section 4.D of this manual using the release rates determined from the grab sample, area /yr.

The resulting setpoint will be valid until the next grab sample is taken from the release point.

This method will be used to establish the Hi-Hi alarm at 500 area /yr to the total body or 3000 area /yr to the skin, whichever is more restrictive.

Since two release points exist for noble gas effluents, the set points may be varied to allow greater release rates from one point than the other, provided the total limit is belov

, 500 mrea/yr for the total body or 3000 mrea/yr for the~ skin, l whichever is more restrictive.

l 6-2 1

The Hi-Ri alarm setpoint for the gaseous monitors will be based on the equation in this section. The Mi alara setpoint may be set at or below, but in no case above, the Hi-Hi alara setpoint.

e e

1 1

i W

6-3 I

l l

7.0 Radiological Environmental Monitoring 3 ample Locations The sample type and location of each sample collected and analyzed in

. compliance with the Radiological Environmental Monitoring Program Technical Specification is given in Table 7-1 through 7-4.

~

In addition the following area maps are provided to graphically indicate the location of each sample station:

Sample Type ,

Tigure No.

Offsite Thermoluminescent Dosimeters, Air Particulates and Iodine 7-1 Onsite Thermoluminescent Dosimeters, '

Air Particulates and Iodine 7-2 Water, Vegetation, and Milk ,

7-3 Typical Mo11use, Algae and Sediment Sampling Stations 7-4 ,

e S

W

\

e 7-1

'- ~

TABLE 7-1 1

OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROCRAM

. . e j Locatione l . /uposure Pathuey (Direction-Dietance) Sampling s'd n Type and Frequency

, or Sample Type from Reactor Collection Frequency of Analysis AIRBORNE j Particulates 11 (See Table 7-2) Continuous sampling over Crose beta radioactivity one week at least 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after l f11ter change. (a) Quar-terly composite (by loca-j tion) for geene isotopic

(b).

Radioiodine 11 (See Table 7-2) Continuous sampling with Analyse weekly for 1-131.

cantater collection weekly w

I l

w DIRECT 40 (See Table 7-3) Quarterly Caema exposure quarterly Plymouth Beach and (1)

, Priscilla/ White Morse Annually Canna exposure survey (1)

Beach i i WATERBORNE Discharge Canal Contimsous Composite Gamma isotopic (b) mon-l (Surface Water) Sample thly; and composite for Bartlett Pond Weekly grab sample M-3 analysie quarterly,

~

(SE-1.7 al.) (c).

Powder Point Weekly grab sample t (NNW-7.8 mi.) (d)

AQUATIC Shellfish Discharge outfall Quarterly (at Cnema footop'ic (b);

(clama, museele Duxbury nay approximate 3 month also see note (f).

or quahogo no Manomet Pt. intervala) ,

available) Plymouth or Kingston !

Harbor I Marnhfield (d) i i

i TABLE 7-1 (Continued)

OPERATIONAL RADIGIACICAL ENVIRONMEWfAL MONITORINC PROGRAM e

Locatione n>eure Pathesy (Direction-Distance) Sampling and Type and Frequency i e _ p Sample Type from Reactor Collection Frequency _,

of Analysis i

j .,beter Vicinity of discharge Four times per season C4 man isotopic (b) point os ed ble portione.

Offshore (d) Once per season

Fish Vicinity of discharge Quarterly (when Cruns istopic (b) on ,

point particular species er ible portions (e).

Offshore (d) available), Groupe I and i

II (e) in season Croupe III and IV (e)

Annually, each group 4

Y Sedimente Rocky Point Semi-annually Camma footopic (b) b' l Plymouth Harbor (c), see also note (g).

Duxhury Bay Plymouth Beach Menomet Pt.

Marshfield INCESTION (Terrestrial)

Milk Plymouth County Farm

Semi-monthly during Camma isotopic (b);

(W-3.5 mi) (h) Whitman periods when animale are radiotodine analyste, l

Farm (NW-21 mi.) (d) on pasture, otherwise all samples.

monthly Cranberries Manomet Pt. Bog At time of harvent Camma footopic (b) on (SE-2.6 mi.) edible portions.

Bartlett Rd. Bog (SSE/S-2.8 mi.)

Pine St. Rog (WNW-17 mi.) (d)

When available.

TABLE 7-1 (Continued) -

OPERATIONAL RADIO 14CICAL ENVIRONMElfTAL MONITORING PROCRAM

Locatione Exposure Fathony (Direction-Dietance) Sampling and Type and Frequency or Sample Type from Reactor Collection Frequency of Analysis Tuberous and green Plymouth County Farm At time of harvest Canna footopic (b) on leafy vegetables (W-3.5 mi.) (h) edible portions.

Bridgewater Farm (W-20 mi.) (d) i Beef Forage Plymouth County Fara Annually Gamma footopic (b).

(W-3.5 mi.) (h)

. Whitman Farm (NW-21 mi.)

(d)

Y.

a I

TABLE 7-1 (Continued)

NOTES (a) -If gross beta radioactivity is greater than 10 times the control value, gamma isotopic will be performed on the sacple.

(b) Gamma irete-t :::.: the identification and quantification of gamma-j omitting radionuclides that may be attributable to the effluents from the facility.

(c) If integrated gamma activity (less K-40) is dreater than 10 times the control value (less K-40), strontium-90 analysis will be performed on the sample.

(d) Indicates control location.

(e) Fish analyses will be performed on a minimum of 2 sub-samples, consisting of approximately 400 grams each from each of the following groups:

I. Bottom Oriented II. Near Bottom III. Anadromous IV. Coastal Distribution Migratory Winter flounder Tautog Alewife Bluefish Yellowtail flounder Cunner Rainbow smelt Atlantic herring Atlantic cod Striped bass Atlantic menhaden Pollock Atlantic mackerel Hakes (f) Mussel samples from four locations (immediate vicinity of discharge outfall, Manomet Pt., Plymouth or Kingston Harbor, and Creen Harbor in Marshfield) will be analyzed quarterly as follows:

j One kilogram wet weight of mussel bodies, including fluid within shells will be collected. Bodies will be reduced in volume by drying at about 100*C.

Sample will be compacted and analyzed by Ge(Li) gamma spectrometry or alter-nate technique, if necessary, to achieve a sensitivity ** of 5 pCi/kg for Co-134. Cs-137, Co-60, Zn-65 and Zr-95 and 15 pCi/kg for Ce-144 The mussel shell sample from one location will be analyzed each quarter.

One additional mussel shell sample will be analyzed semi-annually.

Unscrubbed shells to be analyzed will be dried, processed, and analyzed

ofmilarly to the mussel bodies.

l I . ,

l l ** Sensitivity values are to be determined in accordance with a 95% confidence

, level on Ka; 50% confidence level on Kg (See MASL-300 for definitions).

l l

7-5

TABLE 7-1 (Continued)

NOTES Because of the small volume reduction in pre-processing of shells, sensi-tivities attained will be less than that for mussel bodies. The equipment and counting times to be employed for analyses of shells will be the same or comparable .to that employed for mussel bodies so that the reduction in sensitiviti.. (.;1;:17: t those for mussel bodies) will be strictly limited to the effects of poorer geometry related to lower sample volume reduction.

Shell sample. net sciedaled for analysis will be reserved (unscrubbed) for possible later analysis.

If radiocesium (Cs-134 and Cs-137) activity exceeds 200 pCi/kg (wet) in mussel bodies, these samples will be analyzed by radiochemical separation, electrodeposition, and alpha spectrometry for radioisotopes of plutonium, with a sensitivity of 0.4 pCi/kg.

(g) Sediment samples from four locations (Manomet Pt., Rocky Pt., Plymouth Harbor, and head of Duxbury Bay) will be analyzed once per year (preferably early summer) as follows:

Cores will be taken to depths of 30-cm, minimum depth wherever sediment conditions permit by a hand-coring sampling device. If sediment conditions do not permit 30-en deep cores, the deepest cores achievable with a hand-coring device will be taken. In any case, core depths will not be less than 14-ca. Core samples will be sectioned into 2-cm increments, and surf ace and alternate increments analyzed, other reserved. Sediment sample volumes (determined by core diameter and/or number of individual cores taken from any single location) and counting technique will be sufficient to achieve sensitivities of 50 pCi/kg dry sediment for Cs-134, Cs-137, co-60, Zn-65,

' and Zr-95 and 150 pCi/kg for Ce-144. In any case individual core diameters will not be less than 2 inches.

The top 2-en section from each core will be analyzed for Pu isotopes (Pu-238, j Pu-239, 240) using radiochemical separations, electrodeposition, and alpha spectrometry with target sensitivity of 25 pCi/kg dry sediment. Two additional core slices per year (mid-depth slice from two core samples) will be similarly analyzed.

l (h) These locations may be altered in accordance with results of surveys dis-cussed in paragraphs 8.1. A-3 and 8.1.A-4 of the Technical Specifications.

(1) Minimum sensitivities for gamma exposure measurements are as follows:

- Camas exposure - 1pR/hr average exposure rate.

Camma exposure survey - 1 p R/hr exposure rate.

7-6 r --, --- mm . - - e-- - --y . , . , _ - , . . - -, , - - , . . . , . - - - , , , - - ~ - -- _ - - _ _ . - - - - --- - - - - - - -

TABLE 7-2

. AIR PARTICUIATES, CASEOUS RAD 1010 DINE AND SOIL SURVEILLANCE STATIONS Sampling Location Distance and (Sample Designation) Direction from Reactor Offsite Stations ,

East Weymouth (EU)* 21 miles NW*

l Flymouth Center (PC) 4.0 miles W-WNW Manomet Substation (MS) 2.5 miles SE Cleft Rock Area (CR) 0.9 miles S Onsite Stations Rocky Hill Road (ER) 0.8 miles SE Rocky Hill Road (WR) 0.3 miles W-WNW Overlook Area (OA) 0.03 miles W Property Line (PL) 0.34 miles NW Fedestrian Bridge (PB) 0.14 miles N l East Breakwater (EB) 0.35 miles ESE l

Warehouse (WS) 0.03 miles SSE t -

Control Station 7-7 e -- - -

TABLE 7-3 EXTERNAL CAMMA EXPOSURE SURVEILLANCE STATIONS (TLD)

Distance and Dosimeter Location (Designation) Direction from Station ONSITE STATIONS Property Line (D) 0.17 miles NNW Property Line (F) 0.12 miles NW Property Line (1) 0.14 miles W Property Line (G) 0.20 miles WSW Roc'ky Hill Road (A) 0.12 miles SW Property Line (H) 0.21 miles SSW Public Parking Area (PA) 0.07 miles N-NNE Pedestrian Bridge (PB) 0.1 miles NE Overlook Area (DA) . 0.03 miles W East Breakwater (EB) 0.26 miles ESE Property Line (C) 3.3 miles ESE-SE Property Line (HB) 0.34 miles SE-Rocky Hill Road (B) 0.26 miles SSE x

Microwave Tower (MT) 0.38 miles S Emerson Road (EM) 0.68 miles SE-SSE White Borse Road (WH) 0.89 miles SE-SSE Property Line (E) 0.75 miles SSE-S Rocky Bill Road (WR) 0.3 miles U-WNW Property Line (J) 1.36 miles SSE-S Property Line (R) 1.42 miles SSE-S Rocky Hill Road (ER) 0.8 miles SE Property Line (L) .. : r.iies E 7-8

TABLE 7-3 (Continued)

EXTERNAL GAMMA EXPOSURE SURVEILLANCE STATIONS (TLD)

Distance and Dosfueter Location (Designation) Direction from Station ONSITE STATIONS (Continued)

Warehouse (WS) 0.1 miles SE Property Line (PL) 0.3 miles W OPPSITE SIAT10NS Duxbury (SS) 6.25 miles SSW-SW Kingston (KS) 10 mile. WNW North Plymouth (NP) 5.5 miles WNW Plymouth Center (PC) 4.0 miles W-WNW South Plymouth (SP) 3 miles WSW Bayshore Drive (BD) 0.7 miles W-WNW Cleft Rock Area (CR) 0.9 miles S Manome t (MP) 2.25 miles ESE-S Manomet (ME) 2.5 miles SE Manomet (MS) 2.5 miles SSE Manome t (MB) 3.5 miles SE-SSE College Pond (CP) 6.5 miles SSW-SW Sagamore (CS) 10 miles SSE-S Plymouth Airport (SA) 8 miles WSW East Weymouth (EW)* 21 miles NW

. ,Saguish Neck (SN)** 4.6 miles NNW

Control Station

*TLD's for this location will be provided to a third party and will be analyzed for gamma exposure whenever returned to BECo.

l 7-9 y y _ , -

w - - - - -

d i

TABLE 7-4 ,

MAXIMUM VALtlES FOR THE LOWER LIMITS OF DETECTION (LLD)e '

' Airborne Particulate Water or Cao Wet Solide Milk Food Products Dry Solide Analysis (pC1/kg) (pC1/m3 ) (pC1/kg, wet) (pC1/kg) (pC1/kg, wet) (pC1/kg. dry) groes beta 4b 1 x 10-2 3H 2000 54Mn 15 130 59Fe 30 260 58,60Co 15 130 50 65Zn 30 260 w

50 95 Zr 15 h 50 131 g Ib 7 x 10-2 1 60 C 134,137 Ce 15, 18 1 x 10-2 130 15 60 50 140g , 15 d g$ d 144Ce 150 TABLE NOTATION

a. Refer to ODCM for LLD definition.

b. LLD for surface water.

c. I.LD for leafy vegntables.

I

. J

l se g

%s, l

w cw

- Apr

mm 88 l Armeva 6 se a

s. t *.

ew 8

. pasmatensrrtas

... ~ m

/

s .I s

~

LEGEND 1 DUXBURY (SS) 9 MANDET (E) 2 KINGSTON (KS) 10 MANDET (MS) 3 NORTH PLY 2 UTH (NP) 11 MANDET (2) 4 PLY @UTH CENTER (PC) 12 COLLEGE POND (CP) 5 SOUTH PLY 2 VTH (SP) 13 SAGAERE (CS) 5 BAYSHORE DRIVE (BD) 14 PLY 2UTH AIRPORT (SA) 7 CLEFT ROCK AREA '(CR) 15 EAST WEY2VTH (EW) 8 Itul0ET (W) , 16 SAQUISH NECK (SN)

Figure 7-1. Location of Offsite Thermolurninescent Dosimeters, Air Particulates and Iodine Monitoring Stations 7-11 e., - - o ,-

. g-..,e, - , , , , - - - - _ . ,- _ ,, , - - ,

,e , g

- vg m i e f

7 -), J am m

"$ni,, N "' E" M~

4 ('

.- . F os hl 4 y

l ' Y'Y. ~ . ::,.

~~

+ . , , ,

i m

J pW

- se e is NeN t-

/ ,

E i

i.

. d y, ,

' _$b _

l LEGEND 1 PROPERTY LINE (D) 13 ROCKY HILL ROAD (B) 2 PROPERTY LINE (F) 14 MICROWAVE TOWER (MT) l 3 PROPERTY LINE (1) 15 EMERSON ROAD (EM) 4 PROPERTY LINE (G) 16 WHITE HORSE ROAD (WH) 5 ROCKY HILL ROAD (A) 17 PROPERTY LINE (E) 6 PROPERTY LINE (H) 18 ROCKY HILL ROAD (WR) 7 PUBLIC PARKING AREA (PA) 19 PROPERTY LINE (J) 8 PEDESTRIAN BRIDGE (PB) 20 . PROPERTY LINE (K) 9 OVERLOOK AREA (0A) 21 ROCKY HILL ROAD (ER) 10 EAST BREAKWATER (EB) 22 PROPERTY LINE (L) 11 PROPERTY LINE (C) 23 WAREHOUSE (WS) 12 PROPERTY LINE (HB) 24 PROPERTY LINE (PL) 0 D0SIETER (TLD)

! A AIR PARTICULATES AND DOSIETERS (TLD)

Figure 7-2. Location of Onsite Thermoluminescent Dosimeters, Air Particulates and Iodine Monitoring Stations 7-12

di

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U 4by,

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&w els , c,,, c,,,

S0Y e is Y E ar==wo seses, 4 % h 8her My Dw 1h8 g$ 5 3, s

== 1. g w

.S B

* .ii MO i

~ .: - .. . .,

j O DOMESTsc AND RECRE ATsON AL WATER O SE AWATER [ , gm 3 DIOPS i myear

& GWLK

! LaGEwD 1 DISCHARGE CHAWetEL IDCI 12 DEEP W ATER PUMP 1kG ST ATs0er - LOUT POesO fil 2 COOLinsG w&TER INTAstt itCitt) Ort LL AteD LITTLE SOUTM POMO (Lwl PLYMOUTM 3 POwCER POtWT DU19URY FPI 13 PLyneO.rTM COvetTY FARM ICFI (1) 4 PLYneOUTM SE ACM PLSill! 14 SOUTM P0seO11) i S PRtSCILLA DE ACM PRS) 16 COLLEGE P0neD ICPit31 4 urMITE MO8tSE DE ACM Wrtti 14 BRIDGEW ATER ST ATE F ARM isF) 1 SE AVER DAM RCAD DOC (Smill! 17 ORE AT POND PUMPamG ST AT80ss 40Pt(11 8 LOseG P0esD ROAD 30G til SOUTM wt Yts0UTM e M AmoMET PT. ROAD DOS (MRI 18 Pswt ST SOC MALep Ax PSI

$$ SARTLETT ROAD DOC mR) 10 wniTM AN F ARM (wF) 11 WARNER 1PoesD PWMP188G STATees(1) 30 t ARTLETT POND 1988(21 asAgoesg7 gyggt egy 21 GRE teswoDD G ARDEh (SEI (2)

, til 880 LONGER REOutRED AS OF TECHNICAL SPECIFICATION REvtslON 4/19m i

O! REOulRED BY TECHNICAL SPECIFICATION REVISION OF 4 tism l

On OFTION AL RECREATIONAL tvATER Figure 7-3. Incation of Offsite Monitoring Stations (Water, Vegetation and Milk) 7-13 r --,--es- - ---- -

y .,- -yyw e--y ,--e y

M .

i Green Mareer A

Oe Cape Cod y 83Y Ows8vry Y .

0 1 2 3 a O Ci ten *

! Mrmm W 'C^'t * "as l

Mocky hint u nen a cow C ea jCmraa ans stap l

LEGEND D IRISH MOSS Ene~m'//e O SOFTSMELL CLAMS #woor l e MUSSELS A SEDIMENT 3 QUAMOG5 Figure 7-4. Typical Mo11use, Algae and Sediment Sampling Stations 7-14

>r._,,_.,-_ . _ _ _ , , _ . _ . - -.. _~ r___-_,__--. . - - . - - - - - - - _ - - - , - - - - - - - - - - - - - - - - , -

8.0 Description of the Radwaste Systems 10 1

8.1 Liquid Radwaste Systes Liquid wastes from any BWR come from a variety of sources which have a considerable disparity in chemical and radio-chemical composition and concentration. Normally these wastes are collected and treated seoarar*1v. Tha Ifouid wastes fall into the following categories:

1) Rieh Parfew

! 2) Low Purity l

l 3) Chemical

4) Detergent i High-purity wastes may have high or low solids content and generally have low conductivity, and variable radioactivity. They come from equipment drain sumps, frce URC* operation and from the backwash and resin transfer water used to change out the condensate demineralizers.

Liquid wastes collected in the turbine building equipment drains may sometimes be included with the high purity waste stream; more frequently,

they are returned directly to the main condenser hotwell. Reuse of processed high purity waste is highly desirable.

Low-purity wastes have moderate conductivity and solids content. They come from building floor sumps and are generally high purity wastes which have been contaminated by dirt, oil, etc. When processed, this stream may or may not be reused depending on the water balance in the plant and the quality of the product.

The chemical wastes, which come from condensate resin regeneration and laboratory drains, contain higher solids, and relatively higher radioactivity, should be segregated from the other waste streams, although they have sometimes been combined with the low-purity wastes for treatment. If treated separately, it is likely that the product would be discarded rather than reused.

A schematic of the cost beneficial system as determined in reference 2 is shown in Figure 8-1. In the system, the High Purity waste is collected in one of two 15,000-gal clean vaste tanks, and processed through mixed bed ion exchangers. The processed liquid is collected in one of four 18,000 gal. treated water holdup tanks. It is reused

, to the greatest extent possible.

Ultrasonic Resin Cleaner 8-1

8.2 Treated Gaseous Radwaste System At Pilgria I, the air ejector off-gas is put through a catalytic recombiner (to reduce the stociometric quantities of H2 and 02 to water reduce the gas volume and improve processing efficiency), a condenser, a drier, and then through massive beds of charcoal which serve to hold up the noble gases, krypton and xenon, for periods of

., from hours to days allowing the shorter lived noble gases to decay prior to release to the atmosphere. This processing also effectively removes the iodine isotopes from this stresa.

The cost-beneficial system as determined in reference 2 for handling gaseous waste at Pilgrim I is shown in Figure 8-2.

9 1

{

l l

l 8-2 l

l

l.

,' ste pgRITT _

~

Dioc_herge or precycle WA5TE ST5TWI Clean Weste Mixed' Bed Trested Water Tanks lonex Tanks i

I lAN DURITT Discharge WA5TE 5T5T98 7 F

! Y --

W Chemical Weste 1

Tanks 1

l l

i IIETERGENT l WA5TE SYSTWI Discharge 1

(Decon Arees) l , Mise Unete

! Tanks l

l Figure 8-l. Liquid Ef fluent Treatment System Schematic i

l

" rom

' to Stock

O

^

- SJAE cio Condenser Recombiner Condenser Drier Charcoal to Stack g from .

$g lurbine l land Seals 1.7-minute Holdup

I to Stack ]

tras MECHAN 1(e pin VACULH PUMP

ondenser l

to Vent ros ; REACTOR Reactor BUllDIN-

' olds tras to Vent r DRYVEL8 Drywell -

IN to Vent

'sdwaste gggg 143 BC11rL i

i f*?oe to Vent

TURBIN!

{ arbine BVllEIC Sida

No significant effect in reducing offsite doses when compared to transit time required for releases to reach site Soundary.

Figure 8-2. Gaseous Effluent Treatment System Schematic I

l i

l l 8-4

= e-e a . . . . . .

~

9.0 References

~~

1) NRC Regulatory Guide 1.109, revision 1, October,1977.

2) Pilgris Station Unit 1 Appendix I Evaluation, April, 1977.

3) J.N. Hamawi, "AEOLUS", Tankee Atomic Electric Company YAEC - 1120, 1977.

4) J.N. Hamavi, "SKIRON", Tankee Atomic Electric Company YAEC 1138, 1977.

5) PNPS Technical Specifications, April,1983.

6) PNPS Operations Manual, Volume 8, Book 8: Surveillance.

7) PNPS Operations Manual, Volume 7, Book 2: Chemical and Radiochemical Procedures.

8) Pilgrim Process Radiation Monitoring System Manual GEK-32445A, General Electric.

9) PNPS Maintenance Department Recalibration and Malfunction Records.

10) PNPS Final Safcty Analysis Report, Volumes II and III.

11) NUREG-0133, Preparation of Radiological Ef fluent Technical Specification for Nuclear Power Plants, Revision 2, May,1982,

12) U.S. Nuclear Regulatory Commisssion, " Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Boiling Water Reactors (BWR-GALE Code)," USNRC Report NUREG-0016, Washington, D.C. 20555, April, 1976.

13) Letter from Thomas A. Ippolito, Chief, Operating Reactors Branch #3, Division of operating Reactors, to G.C. Andognini, Boston Edison Company, dated January 23, 1979, including guidance on the General Contents of the ODCM.

0 e

9-1 l . _

9 4

- APPENDIX A DATA REQUIRED FOR EFFLUENT CALCULATIONS i

I l

l t

O I

~

t i

?

A-1 l

I l

s .

- 1R3LE A.1 3104:C1PtJL&T10h FA TOR $ TO St USED in ht 435tw:t Dr SITE.S*tC1 Fit DETA

~

(6 1/kg per p[l/11 gee}

FESPAATft SALTWTER ELDOff g twytaitanAft g prvitTrgmatt

. E 3.E4 9.E4 9.st.81 9.E4 T.

E $3

. 9.1E N 1.tt W 1.at a 8.M.et 1.gt @

' . E 1.E St 8.E N

F 1.E OS 1.E W t.E 08 3.E M ER 1.E 82 1.E 33 4.0L E 1.0E M E 4.E St 9.E 08 5.E E 4.E 02 R 1.E et 3.E a 3.E W t.E os W 5.E 91 2.K E 1. EAR 1.ct 93

~

m 1.E Of 1.E et 1.et E 3.5E et W S.E 01 4.E E 6.M St 1.M E3 ts 1.E 83 1.E M 2.et B E M 08 4.E Et 3.E E 1.E.82 3.1t 80 3 1.M 01 B RE N 1.E 33 4.E to

~

S 3.E m 1.E E tA to 2.E c1 T 3.E fl 1.E B 2.E 01 1 4 83 3 3.E N 5.M m R A et 8.cl51 3.E M 1 4 02 35 08 1.0E Of 5

1.E m 1.E m 1 A 81 1.8E 01 B

1.E 81 SE 80 1A m 5.et 91 W

1.E 01 3.E O2 S E ID 1.E 03 i

W 1.E S1 3.8E E 1.E 81 2.0E 03 WI W 4.E E 4.1E W 1.E R 1402

,3 1.E m 5.E a i s s1 S E s1 8.E 93 1.E W 4 A 51 1.E 81 es 4.E to LE E 1.E 01 1M N but 2.E 01 1A B 2 2 51 1.EE B LA B 1.E e 1A a ,

1.E WI 5.E st LE 01 ~ 1.E N 1 2 51 1.E 03 R

1.E B LEE 81 1.E 83 B 1.E 01 12 51 3.E WI 3.E 01 g .1.E 33 p 1.E 01 4.E E 12 51 1.E 51 e

e 1 A-2 t

i

- - - - - - _ , , ,---,--_,, mea -am ,-. - - - - , . - - - e ----.--w-g--w w-- - - - -,- - -,- - - - - ,,

. . TABLE 0-1 DOSE FACTOR 5 FOR EIP05Unt TO A SEMI-laFtalTE CLOUD OF 30BLE SA5ES a-Stim **(DF5g ) s-Body **(OFBg )

Rec 194g s-etr*(DFl) v-Afr*(OF})

Er-03m 2.tSE-94*** --- 1.93E-05 7.56E-08 Er-8 5e 1.97E-03 1.46E-03 1.23E-03 1.17E-03 Er-85 1.95E-03 1.34E-03 1.72E-05 1.61E-05 Er-87 1. 0"3E-02 9.73E-03 6.17E-03 5.92E-03 Er-88 2.93E-03 2.3?E-03 1.52E-02 1.47E-02 Er-89 1.96E-02 1.01E-02 1.73E-02 1.66E-02 Er-90 7.83E-03 7.29E-03 1.63E-02 1.56E-02 to-131m 1.11E-03 4.76E-04 1.56E-04 9.15 E -05 Ie .133a 1.48E-03 9.94E-04 3.27E-04 2. 51 E -04 Ie-133 1.05E-03 3.06E-04 3.53E-04 2.94E-04 Ie-135e 7.39E-04 7.11E-04 3.36E-03 3.12E-03 .

Ie-135 2.86E-03 1.86E-03 1.92E-03 1.81E-03 Ie-137 1.27E-02 1.22E-02 1.51E-03 1.42E-03 l Ie-138 4.75E-03 4.13E-03 9.21E-03 8.83E-03 Ar-41' 3.28E-03 2.69E-03 9.30E-03 4.84E-03 l

3 pes 4-s pct-pr pree-e 3 pC1-pr ,

- - 2.88E-04 = 2.88 s 10*8 A-3

9 4

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STAtit ELDerwt inAnsrp esta S,g F,(Cow) F, h fenfleft RH1h (4/a) Heat f4/ta) e-- ..es w 1.0t-02 1.N-02 t** 8.St to 1.31-02 3.1t-02

m. s st-e2 4.0t-02 3.0[42 P 1.It 90 2.M-02 4.M-42 Cr 2.M-08 f.N43 3.4t 03

, h 1 K-42 2.M.M S.0E-04 Fe S.St-08 1.21-03 4.0E-02 l . Op 9.4t43 1.0E-03 1.M42 31 1.0E-02 S.M-03 5.M42 Cs 1.H41 1.4E-02 0.0(-03 ta 4.0t41 3.0E-02 3.0t-02

& 1.M-01 3.0E42 3.1E-02 Sr 1.?t-02 S.0C-08 S.0E-04 i

T 3.N-03 1.0E-05 4.E-03 tr 1.7t-Os S.0E-05 3.4t-02 h 9.4t-03 2.5(43 f.E-01 As 1.M-01 7.It-03 0.K43 1c 2.M41 f.K-02 4.K-01 Os S.W-02 1.0C-05 4.0C-41 h 1.E 01 -

1.ct-02 1.5t-03 At 1.0E-01 S.0C-02 1.7t-02 1e 1.E 00 1.0E-03 -

7.7E-02 3 3.0(42 S.M-03 3.0E-03 Cs 1.St-02 1.tt-0? 4.0t-03 Sa 5.0t43 4.0E-04 3.N43 La 3.M43 S.0E-Or 1.0E-Os Ce 2.0E-03 1.K-04 1.M-03 Pr 2.M-03 S.W-05 4.7E-03 ed 2.4t-03 S.0E-05 3.M-03 W 1.0E-02 S.0C-04 1.M-03 4 2.E43 S.0E-05 f.K-Oen W

. A-4 f

s TABLE E4 W C110t TRAM 5 m PARANTERS FDs goat'S N!LE p, F,(days /11ter) 3 0.17 C 0.10 9 0.5 Fe 1.E 04 Ce 0.013 Sr 0.014 I 0.06 Cs 0.30 l

i A-5 i -.

1

TAILE I 5 IEcomL@@ VALuis FOR U,, TO M V5G FOR THE EXI4JM DP050 telv!Du4L la LitV 0F $ITE-StictFIC ORTA

.P.A.MMI 18!!.*!!L E!Hf. ISE* M

- r,v ee. .~..u a

$20

$30 ysta (kg/p) . SED Lui e w h1 35 42 04 (kg/pr) -

330 400 310 Allt(a/pe) 330 Neat & poultry 110 (kg/pr) - 41 65 Fish (fresh or asit) 6.9 16 21 (kg/pr) -

Otherseefood(kg/yr) - 1.7 3.0 $

510 510 730 Drinking s tar (s/pe) 330 Shoreline recreation 67 12 (hr/p) - 14

!ahalatf an (sI /pr) 1400 3700 0000 0000 l

l O

O o

1RELE E4 DTEtut 905E FACTOR 5 FOR STAwolic Oh EDhiAM1 MATED MM (ersm/hr per pC1/mI )

Element Total Body j,,ht t

aks S.O 5-14 0.0 0.0 0.0 E P4 2.80E 4 2.90E 08 t- 9.0 0.0 EfE51 2.IDE-10 ID 54 2.60E-10

5.30E-09 6.00E-09 th M 1.10E-0B Fe56 1.30E-0B S.O 9.0 Fe4t 8.00E 09 9.40E-09 Cels 7.00E-09 8.20E-09 to-46 1.70E-0B 2.00E-08 3143 0.0 0.0 nl-85 3.70E-09 4.30E-09 ga 1.50E-09 e5 1.70E-09 4.00E-09 4.60E-09 In-49 0.0 Sr43 0.0 6.40E-11 9.30E-11 tr-04 1.20E-08 3r-85 1.40E-08 0.0 9.0 b e6 5.30E-10 b 88 7.20E-10 3.50E-09 4.00E-09 b-89 1.50E-0B Er-09 1.30E-Os

! 5.60E-13 6.50E-13 Sr-91 7.10E-09 l Sr-92 8.30E.09 9.00E-09 1.00E-08 l T-90 2.20E-12 T-91M 2.00E 12 3.00E-09 4.40E-09 T-91 2.40E-11 T-92 1.70E-11 1.60E-09 1.90E-09 T-93 5.70E-10 7.gDE-10 Ir-95 5.00E-09 Zr-97 5. ODE-09 5.50E-09 6.40E-09 4 95 5.10E-09 80s-99 5.00E-09 1.90E-09 2.20E-09 Tc-9F 9.60E-10 Tc-101 1.10E-09 2.70E-09 3.00E-09 b 103 3.00E-09 Sw-105 4.20E-09

- 4.50E-09 5.10E-09 tv-106 1.50E-09 Ag-litst 1.gDE-Og 1.SOE 09 3.1g-gg Te-125 3.50E-11 70-12M 4.00E-11 1.1R-12 1.30E-12 70 127 1.00E-11 7e-125 1.10E-11 7.70E-10 9.00E 10 Te-129 7.1R-10 fe-13M 8.40E-10 8.40E-C- 9.90E-09 10-131 1.30E 4 ,'

fe-132 2.00E 05 1 70E-09 2.00E-05 3 130 1.40E-08 3-131 1.70E-8B 2.00E-09 3.40E-ee 3-132 1.70E-8B 3-133 3.70E-8B 2.NE4 3-1 39 4.gDE.es 1.00E-OB 1.90E.m 3-15 1.30E es 1.a0E.gg i

A-7

, TAaLEt-6(Continued)

Dement Total todr g Ca.138 1.20E-00 1.40E-08 Cs-138 1. lot-08 1.70E-4B -

Cs-137 4. tot-09 4.90E-00 Cs-15 1.15 4 1.40[ 4 Se-139 1.40t-09 2.70E-09 to-140 3.1cE 0D 2.40t-09 Se-141 4. 30E-09 4.90t-00 Be-142 7.30E-Og 3.00t-Os to-140 1.50E-4B 1.70E-08 La-let 1.50E-00 1.00[-0B -

Co-141 S.50E 10 6.30E-10 Co-143 2.20E-09 1.50E-09 Co-144 3.20E-10 3.70E-10 Pr-143 0.0 0.0 Pr-144 2 00t-10 2.30E-10 34-147 1.00t-09 1.20E-09 W-187 3.10E-09 3.6CE-09 NP-239 9.50(-10 1.10t-03 l

l I

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740LE E-F FAGE 1 0F 3 I teet&Lafl04 DOSE F ACT0as Fna asuLTS l

.1*ata PEA ett 14MALEDI l 7.h0CT TMTaclD E1DesE7 LU4G St-LLI

WCL ID2 004g Liven I

Il 3 he DATA 1.SDE-07 1. 98f =47 1 58E-37 3 58E-0T 1.SSE-07 t.SSE-07 5 to 2 27E-06 4.26E-07 4.26E4 7 4.26&-07 4.261-07 4.26E-07 4 26E-07 1A to 2 2tE-06 1 281-M 3.2 SE-06 t.2tE-06 t.Itt-06 1.2SE-06 3.28E-06 _

seC DATA kn DATA 1 08E-DS P S2 3 6SE-04 9.64E-06 6.26E-06 080 DATA f Ca 51 NO DATA 40 04TA 12SE48 7.44E-09 2.SSE-09 1 00E-06 4.1SE-07 r

lu0 D&TA 4.9&E-D6 F.t it-e t se0 DATA t.23E-06 1.75E-04 9.67E-06 met 54 l

080 DATA 2.SSE-10 2 29E-11 90 DATA 1 63E-10 1 1tf-06 2 53E-06 I som 56 40 DATA 9.01E-06 7.54t=0T Ff"SS 3 0TE-06 2 12E-06 4.91E-0 7 see DATA NO DATA 1 27E-04 2 3SE-05 FE 59 1 47E-06 3 47E-06 1 32E-06 se0 DATA 1.9tE-07 2.59E-07 se0 CATA #C DATA t.16E-04 1.33E-05 CD $8 40 DATA noe DATA 7.46E-04 1.56E-05 j

CC 60 800 DATA 1 44E-06 t . S t t-4 6 40 DATA mc D&TA 2 23E-05 1 67E-06 i

til 6 3 S.40E-05 3.93E-06 3 81E-06 see DATA l 7.00E-07 1.54E-06 WC DATA 1

91 65 1.92E-10 2 62E-11 1 14F-11 20 DATA ).T8E-10 9.48E-0T 6.12E-06 CU to NO DATA 1.tJE-10 7.69E-11 100 DATA 8 62E-06 1 0tE-04 6.6tE-06 i

28 65 4.0$E-06 1.29E-05 6. 82 E-0 6 se0 DATA _

l .. .

4.23E-12 0 14E-12 S.6SE-13 see DAT6 S.27E-12 1 15E-07 2.04E-09

! 29 69 100 DATA te0 DATA 2.90E-08 08 43 NO D&TA 10 DATA

3 01E-48 see DATA see DATA te0 DATA 2.0SE-11

( ta to as0 DATA 20 DATA S.91E-08 8e0 S&T4 _-

l' .._ - =

see DATA L7 E-24 II0 DATA 1 60E-09 8ec DATA se0 DATA St SS 8e0 DATA 20 DATA es0 DATA 2. cst-06 tt to see DATA 1 69E-05 7.3FE-06 esO DATA sec D&T A tec DATA 4.18E-19 48 at Is0 DATA 4.84E-08 2 41E-38 sec DATA =

NO DATA se0 DATA 1.16f-21 48 39 880 DATA 3.20E-08 2.12E-et 20 DATA #C DATA 1 75E-04 4.37E-05

&a 29 3 00E-05 850 D674 1.09E-06 esO DATA

! 7.62 E4 4 es0 Data sec DATA 1 20E-03 9.02E-05 SA 90 1 24E-02 '40 DATA l

3 15E-10 see DATA see DATA 4.56E-06 2.39E-05 I

.Sa 91 7 74E-09 see D&TA see DAfa 2 06E-06 S.3tE-06 Sa 92 8.43E-10 see D&T A 8. 64 E-11 se0 DATA 2 12E-05 6.32E-05

7. 01E-0 9 20 DATA see DATA Y 90 2 61E-07 800 DATA 1.2 T E-12 40 DATA NC DATA 2 40E-07 1.66E-10 Y 91m 3 26E-11 no DATA 1.SSE-06 as0 DATA see DATA 2 13E-04 4.81E-05 Y 91 S.TSE-OS se0 D4TA 4ec DATA 1 96E-06 9.19E-06 Y 92 1 29E-09 180 DATA 3 77E-11 40 DATA

=_

l D

4 e

! 1 A-9 t.

TABLE 8-7. E04T*D

,, P AS E 2 OF S

Iww&Lafl04 Dolf FAC70a5 Foa ADULTS E* rep PE6 PCI Iss=ALEDI

, seuCList DOet ,Llyta T.tcar tuvaplD E!DefE 7 4U46 O!-LLI

. =-

s.ier-no em neta 9 es 3.26E-19 880 Defa te0 0474 la 96 3 34E-96 4.30E-04 4.06E-06 S.2?f-05

2. 91 E-0 6 80 Dafs 4.??E-06 2.21E-04' 8.ast-05 24 97 8 21E-08 2.4SE-99 3. l M-09 18 DATA 3.ftt-D9 f.84E-04 6.54E-05 I h6 95 9 76E-N 9.??E-97 S.26E-07 es0 Da7A 9.67E-07 4.3tt-Ob t .30 E-05 etc 99 esO DATA 3.llE-98 2. t ?t-0 9 Is0 Defa 3.64f-08 1 14E-OS 3 10E-OS

, IC 99* 3 29E-13 3.64E-13 4.63E-12 ese DATA . S.522-12 9.SSE-On S.20E-07 l

TCl01 S.22E-15 7.52E-16 7.3st 14 ese SATA 3.35E-Il 4.99E-06 E.36E-21

. e9103 8.91E-07 leo DafA 0 2 AE -08 esc DATA 7.29E-07 6.3tE-05 1.30E-05 i

awl 95 9.OBE-11 teC CATA 3.99E-11 te0 DATA 1.271-10 3.3?f-06 6. 02 E -06

! RUl06 8.64E-06 see DATA l . S tt -0 6 sen Data 3.67E-05 3.17E-03 1.14E-04 AC110P I.35E-06 3.2SE-D6 7.4 AE-0 7 880 DATA 2.46E-06 S.79E-04 3.78E-OS I 1E1254 4 27E-07 8 9tE-07 S. s* E-0 8 1.3tE-07 8.551-06 3.92E-05 f.83E-06 TEl27P 1.lBE-04 7.21E-07 1.96E-07 4 31E-07 S.72E-04 1.20E-De I.BTE-OS Test? 3 75E-10 8 018-11 3. 8 ? E -11 1.12E-IC' 6.37E-10 9.14E-07 7.1 ?E-04 EE129* 1 22E-D6 S.64E-07 3.98 E -0 7 4.30E-07 4.S?t-06 1.4SE-04 4.791-09 i TElft 6 22E-32 2.99E-12 1. 91b E-12 4. 8 7E-12 2.34E-11 2.42E-07 1.96 E-te l 1E1314 8.T*E-09 S. 4 S E- 09 3.63F-09 6.8BE-09 3.96E-00 1.82f-05 4.95E-05 l SE131 8.S tt-11; 7.44E-13 4.4 9E-13 1.17E-12 S.46E-If S.741-07 2.30E-09 TE132 3.25E-08 2.69E-08 2. 02 E-0 8 2.37E-08 8.82E-07 5.60E-05 6.3?E-05 3 330 9.726+07 1 6BE-06 6. 60E-0 7 I.42E-04 2.61 E - te MD 9414 9.41E-07 I Ill ,3.15t-06 4.47E-D6 2. 56t-06 1.49E-03 7.66E=J6 100 Saft 7.BSE-07 i

I 132 - 1 4SE-07 4 07E-97 8. 4 bE-0 7 3.43E-05 4.4BE-07 sec 9 i14 S .Q tF-08 3 333 1.00E-06 2.tlE-06 S.6SE-07 2.69E-04 3. 2 8t.-96 ear D nta 3 11E-06 l 8 134 0.0SE-00 2 16E-07 7.69E 40 3.73I-06 3.44E-07 tuO D&74 8 06E-10

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

.;-- - ===-

i I 135 3. 3 H-07 0.73E-97 3. 21 E-07 S.60E-Of. I.39E-06 180 DATA 6.h E-07 CS134 4.66E-05 3.06E-04 9.IDE-05 180 DATA 3.59E-DS 1.22E-05 1.10 E-06 CS136 4.89E-96 1.03E-05 t . 3 B E-O S ese DATA 3 07E-05 l.SDE 04 1 46E-06 CS137 S.98E-95 7.76E-95 S.35E-OS fa0 9474 2 7BE-05 9.40E-56 1 95E-06 CSISS 4.14E-98 7.76E-08 4.85 E-0 8 800 DATA 4.60E-OS 6.07E-09 2.BBE-13 04139 3.37E-10 9.32E-14 3.42 E-12 NO DAVA 7.78E-14 4.70E-07 1 12E-07

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

e P

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4 TABLE E-15 RECWW H OED VALUES FOR OTHER PARAE TER$_

l Peremeter Values

$sukel Deflattien Fraction of produce ingested grown in garden of Interest 0.76

f, .

Fraction of leefy vegetables grown in garden of Interest 1.0 l f, t

Fractlen of deposited activity retained on crops. leafy 0.25 r

vegetables, or pasture grass 1.0(forledines)

, 0.2 (for other particulates) i Attenestion facter accounting for shielding provided by 0.7 (for menteum Sy individual) 2n residential structures 0.5 (for ,eaerei 4, populetten) w i ..

T20 hrs (30 days.

period of ct9p. leafy vegetable, or posture grass I

i t' espesure during growing season for grass-cow ellk.

men pathuey) 1440 hrs (60 days, for crop /ve9etetten.

men pathuey) 1 2 days (for menteus tg Trensport time from enleel feed-allk-man Individuel) 4 days (for genere) population)

TAGLEE-15(Continued)

Peremeter Je.]gg Speel _ Definition _

l fles delay between hervest of vegetetten er crops and l' t h

investion i

fere (for posture .

1) For ingestten of forage by enleels gross) 2160 hr (go days for storedfeed) l 24 he (1 day. for

! 11) For investion of crops by son leeYy vegetables 8 i siealaumIadIeideal)

' 1440 hr (60 days, for

' produce & mealsum ladividual) 4

! D W

i l

0.7 kg/m2 gg,,,,,,,,

Agrtcultural predvettvity by unit eres (messered cow <ntiasenpathuey)

Y' in wet weight) i ,

2.0 hetat gg,, ,,,g,,,

er 6 fy vegetebies ingested by con) l l

(

APPENDIX B Definition of Lower Limit of Detection I

a. The LLD is defined for purposes of these specifications as the smallest con-centration of radioactive material in a sample that will yield a net count (above system background) that will be detected wie.h 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. l l

For a gross activity measurement system (which may include radiochemical I separation):

l 4.66 eb LLD=--------------------------------------

E

V ' 2.22 x 106 . y , exp (- At)

Where:

< LLD is the "a priori" lower limit of detection as defined above (as microcuries per unit mass or volume), i ob is the standard deviation of the background counting rate or of the I I

counting rate of a blank sample as appropriate (as counts per minute) defined as B, T

B is the average background count rate (as counts per minute),

T is the total time of the background count (in minutes),

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

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

2.22 x 106 is the number of disintegrations per minute per microcurie, i

Y is the fractional radiochemical yield (when applicable), ,

i A is the radioactive decay constant for the particular radionuclide, and l l

t for plant effluents is the elapsed time between the midpoint of j sample collection and time of counting. l

. 1 Typical values of E, V, Y, and t should be used in the calculation.

l l

B-1

4 4

i For a Multichannel analyser activity measurement system (which may include radiochemical separation):

i 4.66 yfGross Area LLD = n-----

T*E*I

V

3.7 x 104*Y* 1-(e-AEI )/Atg. * (e-AE2)

Where:

~

; *f : in seconds E = efficiency for energy of interest (cps /Y/sec) l i I = fractional photon abundance (Y/d)

V = volume (in units of mass or volume) 3.7 x 104 = dps/uci Y = fractional radiochemical yield (when applicable)

A = radiosctive decay constant for the radionuclide of interest t1 = sample collection period t2 = elapsed time from end of collection period to start of count.

b. For certain radionuclides with low gamma yield or low energies, or for certain radionuclide mixtures, it may not be possible to measure radionuclides in concentrations near the LLD. Under these circumstances, the LLD may be increased inversely proportionally to the magnitude of the gamma yield (i.e., l 5 x 10-7/I, where I is the photon abundance expressed as a deciaal fraction),

but in no ease shall the LLD, as calculated in this manner for a specific radionuclide, be greater than 10% of the NPC value specified in 10 CFR 20, Appendix B Table II, Column 2.

c. For Liquid Effluents the principal gaana esitters for which the LLD specifi-cation will apply are exclusively the following radionuclides: Mn-54, Fe-59, Co-58, co-60, En-65, Mo-99, Cs-134, Co-137, Ce-141, and Ce-144.

, This list does not mean that only these nuclides are to be detected and l reported. Other peaks which are measurable and identifiable, together with l the above nuclides, shall also be identified and reported. Nuclides which '

are below the LLD for the analyses should not be reported as being present

, at the LLD level. When unusual circumstances result in the LLD's higher

, than required, the reasons shall be documented in the Semi Annual Effluent i

Report.

d.- For Caseous Effluents the principal gamma emitters for which the LLD specifi-l cation will apply are emelusively the following radionuclides: Kr-87, Kr-88, Ee-133, Ee-133u, Ee-135, and Xe-138 for gaseous emissions, and Mn-54, Fe-59 Co-58, Co-60, 2n-65, Co-134, Cs-137, Ce-141 and Ce-144 for particulate B-2

t.

\

emissions. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported.

Nuclides which are below the LLD should not be reported as being present at the LLD level for that nuclide. When unusual circumstances result in LLD's higher than required, the reasons shall be documented in the Seat-Annual Effluent Report.

e B-3

. _ _ _ _

ML20024A650

Text

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