ML17277A957

Offsite Dose Calculation Manual.

ML17277A957
Person / Time
Site:	Columbia
Issue date:	10/17/1983
From:	WASHINGTON PUBLIC POWER SUPPLY SYSTEM
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PROC-831017, NUDOCS 8310260122
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8310260122 831017 PDR ADOCK 05000397 A PDR WASHINGTON PUBLIC POWER SUPPLY SYSTEM WNP-2 OFFSITE DOSE CALCULATION MANUAL

t a l .I l

e 1 OFFSITE DOSE CALCULATION MANUAL 1

Section TABLE OF CONTENTS Title

~Pe e

1.0 INTRODUCTION

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 1 2.0 LIQUID EFFLUENT DOSE CALCULATION . ~ ~ ~ ~ 2 2.1 Introduction.. . ; ~ ~ ~ ~ 2 2.2 Radwaste Liquid Effluent Radiation Monitoring System . . ~ ~ ~ ~ 2 2.3 10 CFR 20 Rele'ase Rate Limits 3 2.3.1 2.3.2 Prerelease Post Release Calculation.....;........

Calculation............

~ ~ ~ ~ ~ ~ e ~

3 4

2.3.3 Continuous Release............... ~

~

~

~

~

~

~ 5 2.4 10 CFR 50, Appendix I, Release Rate Limits....... ~ ~ ~ ~ 6 2.4.1 Projection of Doses ~ ~

e' 9

2.5 Radwaste, Liquid Effluent Alarm Setpoints Calculations. ~ 9 2.5.1 Introduction e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 9 2.5.2 Methodology for Determining the Setpoints . 10 2.6 Verification of and 10 CFR 20, Appendix B................I, Compliance with 10 CFR 50, Appendix

~ ~ ~ ~ 12 Methods for Calculating Dose to Man from Liquid Effluent Pathways e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 13

.2.7.1 Radiation Doses ~ ~ ~ ~ 13 2.7.2 Plant Parameters'. . . . . ; . . . . . . . . . . . . . . . 17 2.8 Compliance with Technical Specification 3.11.1.4....

2.8.1

'.8.2 Introduction......................

Calculation of the Maximum Allowable Concentration of

~

~

~

~

~

~

~

~

18 18 Radionuclides in the Liquid Radwaste Temporary Tank ~ ~ ~ ~ 19 3.0 GASEous EFFLuENTS DOSE CALCULATION . . . . . . . . . . . . . . - 30 3.1 Introduction ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 30 3.2 Gaseous Effluent Radiation Monitoring System . . . ~ ~ ~ ~ ~ ~ ~ 30 3.2.1 Main Plant Release Point . . ~ ~ ~ ~ ~ ~ ~ 30 3.2.2 Radwaste Building Ventilation Exhaust Monitor . 31 3.2.3 Turbine Building Ventilation Exhaust Monitor . ... . 32

1 l' 1

Section Title ~Pe e 3 .3 10 CFR 20 Release Rate Limits ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ o ~ 32 3.3.1 Noble Gases . 33 3.3.2 Radioiodines and Particulates . 33 3.3.2.1 Dose Parameter for Radionuclide i (P-) . 37 3.4 10 CFR 50 Release Rate Limits ~ o ~ 40 3.4.1 Noble Gases (Technical Specification 3.11.2.2).... ~ ~ ~ ~ ~ 40 3.4.2 Radioiodines and Particulates 3.4.2.1 (Technical Specification Dose Parameter 3.11.2.3)..........

for Radioiodine i (Rl)

~ . ~

o

~

~

~

~

43 45 3.5 Compliance with Standard Technical Specifications 3.11.2.4 and 3.11.2.5 . . . . . . . . . . . . . . . . . . . . . . . . . . 52 3.6 Calculation of Effluent Monitor Alarm Setpoint 3.6.1 3.6.2 Introduction..................,...

Gaseous Setpoints Determination for Elevated Release and

~ ~

. 53

~ 53 3.6.2.1 Containment Building Elevated Release Setpoints Calculations Based Vent......

on Whole Body Dose Limits

~ ~

o

~ 53

. 53 3.6.2.2 Setpoints Calculations Based on Skin Dose Limits... ~ ~ ~ 56 4.0 COMPLIANCE WITH 40 CFR 190 .. ~ ~ ~ ~ 88 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING ~ ~ ~ ~ ~ ~ ~ ~ ~ 89 Radiological Environmental Monitoring Program ~ ~ ~ ~ ~ ~ ~ ~ 89 Land Use Census ~ ~ ~ ~ ~ ~ ~ ~ ~ 90 5.3 Laboratory Intercompar ison Program........... . 91 5.4 Reporting Requirements . . . . . . . . . . . . ~ ~ o ~ ~ ~ ~ ~ ~ 92

OFFSITE DOSE CALCULATION MANUAL LIST OF TABLES Table Title ~Pa e Section 2.0 2-1 Fish Bioaccumulation Factors (BFi) and Adult Ingestion Dos'e Conversion Factors (DF;). . . . . . . . . . . . . . . . . 23 2-2 Ingestion Critical Organ........................

Dose Factors (Ai>) for Total Body and 26 2-3 From Liquid Effluents ....................

Input Parameters Used to Calculate Maximum Individual Dose 29 Section 3.0 Dose Factor s for Noble Gases and Daughters...... ~ ~ ~ e 57 3-2 Distance (miles) to Controlling Locations as Measured from Center of WNP-2 Containment Building......... ~ ~ ~ ~ 58 3-3 WNP-2 Annual Average Dispersion (X/Q) and Deposition ( D/Q)

Values for Special Locations . . . . . . . . . ~ - ~ ~ 59

. Dose Rate 3 Parameters. Implementation of 10 CFR 20, Airborne Releases ~ ~ ~ ~ 60 3-5 Dose Rate Parameters.

Airborne Releases .................;....

Implementation of 10 CFR 50, 61 3-6 Input Parameters for Calculating R i

~ ............. 65 3-7 Input parameters for Calculating R,. . . . . . . . . . . . . . 66 3-8 Input Parameters for Calculating R,.............,

V

. 67 3-9 Input Parameters Needed for Calculating Dose to the Maximum Individual from WNP-2 Gaseous Effluent . . . . . . 68

l l Tab 1'e. Title ~Pa e 3-10 3-11 Reactor Building Stack X/g and D/g Values ......... - 70 Turbine Building X/g and D/g Values 74 3-12 Radwaste Building X/q and D/q Values............ - 78

'3-13 Characteristics of WNP-2 Gaseous Effluen't Release Points... 82 3-14 References for Values Listed in Table 3-10.......... 83 3-15 Design Base Percent Noble Gas (30-Minute Decay) . . . . . . . 84 3-16 Annual Doses at Special Locations Within WNP-2 Site Boundary.

Source: WNP-2 Gaseous Effluent 85 3-17 Annual Occupied Air Dose at Special Locations Within WNP-2 Site Boundary . . . . . . . . . . . . . . . . . . . . . . 86 Section 5.0 5-1 Radiological Environmental Monitoring Program ~ ~ ~ ~ ~ 94 WNP-2 REMP Locations . . . . . . . . . . . . ' . .

J

~ ~ ~ ~ ~ 97 5-3 Environmental Radiological Monitoring Annual Summary 103

~ ~ ~ ~ ~

~4 Reporting Levels for Nonroutine Operating Reports 104 LIST OF FIGURES

~iciure Title ~Pa e 3-1 Site Boundary for Radioact ive Gaseous and Liquid Effluents ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 87 5-1 'adiological Environmental Monitoring Sample Locations Outside of 10-Mile Radius ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 101 r

5-2 Radi ologi cal Environmental Monitoring Sample Locations

'Inside of 10-Mile Radius . ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 102 5-3 Area TLD Stations 103

I r' I

0

1 0 >yNTRODUCTION The purpose of this manual is to provide the information and methodologies to be used by the Washington Public Power Supply System to ensure compliance with the dose requirements stated in the WNP-2 Effluents Technical Specifications.

l 0

2.0 LI ID EFFLUENI DOSE CALCULATION

'.1 Intro duct i on Liquid radwaste released from MNP-2 will meet 10 CFR 20 limits at the point of discharge to the Colunbia River. This design objective will be kept at all times. Based on the radionucl ides mixture obtained from the HNP-2 GALE liquid computer run and Columbia River dilution flow, a theoretical, continuous con-centration of radionuclides at 10 CFR 20 limits at the point of dischar ge to the Colunbia River will result in compliance with 10 CFR 50 Appendix I limits in the unrestricted areas. Actual discharges of liquid radwaste effluents will only occur on a Batch Bases, and the average concentration at the point of discharge will be only a small percentage of the allowed limits.

The cumulative quarterly dose contributions due to radioactive liquid efflu-ents released to the unrestricted areas-will be determined once every 31 days using the NRC LADTAP computer code. The maximum exposed individual is assuned.

to be an adult whose exposure pathways include potable water and fish 'consump-tion. The choice of an adult as the maximum exposed individual is based on the highest fish and water consumption rates shown by that age group and the fact that most of the dose from the liquid effluent comes from these two pat hways .

The dose contributions will be calculated for all radionuclides identified in the released effluent. The calculations are based on guidelines provided by the NRC Nureg-0133 and the LADTAP computer code.

The methods for calculating the doses are discussed in Section 2.4 of this manual.

2.2 Radwaste Li uid Effluent Radiation Monitorin S stem This monitoring subsystem measures the radioactivity in the liquid effluent prior to its entering the cooling tower blowdown line.

1 1

All radwaste effluent passes\

through a four-inch line which has an off-line sodium iodide radiation monitor. The radwaste effluent flow, variable fry

~ ~

~ 0 to 190 gpm, combines with the 36-inch cooling water blowdown line, variable

~ ~

from 0 to 7500 gpn, (average of 2690 gpm) and is discharged to the Columbia River with a total flow based on NPCi total, and 'cooling water flushing needs.

The radiation monitor has a minimun sensitivity of 10 vCi/cc of C -137),

s and the radiation indicator has a range of seven decades. The radiation monitor is located on the 437'evel of the Radwaste Building.

2.3 10 CFR 20 Release Rate Limits The requirements pe'rtaining to discharge of radwaste liquid effluents to the unrestricted area are specified in Technical Specification 3.11.1.1:

"The concentration of radioactive material released from the site to unrestricted areas shall be limited to the concentrations specified in 10 CFR 20, Appendix B, Table II, Coluon 2 for radionuclides other than noble gases, and 2 x 10< pCi/ml.total activity concentratra-tion for all dissolved or entrained noble gases."

In order to comply with the requirements stated above, limits will be set to assure that blowdown line concentrations do not exceed 10 CFR 20, Appendix B, Table II, Column 2 at any time.

2.3.1 Pre-Rel ease Cal cul ation The activity of the radionuclide mixture will be determined in accordance with Supply System pmcedure PPM 12.5.3. Liquid effluent discharge is determined and calculated according to PPM New '12.11.1 Radiological Effluent tlonitoring Report. The effluent concentration is determined by the following equation:

Ci Ci ~wt D

~Fw '

I k

where:

ConC,. Concentration of radionuclide i in the effluent at point of discharge - pCi/ml.

Ci Concentration of radionuclide i in the batch to be released - pCi/ml.

Fw = Discharge flow rate from sample tank to the blowdown line - variable from 0 to 190 gpm.

Fd = Blowdown flow rate - variable from 0 to 7500 gpm.

The calculated concentration in the blowdown line must be less than the con-centrations listed .in 10 CFR 20, Appendix B. Before releasing the batch to the environment, the following equation must hold:

m gi=1 (ConC./MPC.)

Cl 1 < '1 (2) where:

ConC.

Ci The concentration of radionuclide i in the effluent at the point of discharge.

MPC.- Maximum permissible concentration of nuclide i as listed in 10 CFR 20, Appendix B, Table II.

m = Total number of radionuclides in the batch.

2.3.2 Post-Release Cal cul ation The concentration of each radionuclide in the restricted area, following the batch release, will be calculated as follows:

I 1 The average activity of radionuclide i during the time period of the release is divided by the Plant Discharge Flow/Tank Discharge Flow ratio yielding the concentration at the point of discharge:

C ik x Fw on (3)

C ik ~M+

where:

C'nC k The concentration of radionuclide i in the effluent at the point of dischai ge during the release period k

- (>Ci/ml).

Cik = The concentration of radionuclide i in the batch during the release period k - (vCi/ml).

Fw = Oischar ge flow rate from sample tank to the blowdown line - variable from 0 to 190 gpm.

FD = Blowdown flow rate - variable from 0 to 7500 gpm.

To assure compliance with 10 CFR 20, the following relationships must hold:

Q (ConC.k/NPC.) < 1 (4) i=1 where the terms are as defined in Equation (2).

2.3.3 Continuous Release Continuous release of liquid radwaste effluent is not planned for WNP-2.

However, should it occur, the concentrations of various radionuclides in the

I 1 t 0

unrestricted area would be calculated according to Equation (3) and Equa-tion (4). To show compliance with 10 CFR 20, the two equations must again

~

hold. ~

2.4, 10.CFR 50 A endix I Release Rate Limits Standard Technical "Specification 3-.11.1.2 requires that the cumulative dose contributions be determined in accordance with the ODCN at least once per 31 days. It specifies that the dose to the individual from radioactive material in liquid effluents released to the unrestricted ar ea should be limited to:

<1.5 mrem/Calendar (}uarter - Total Body

< 5.0 mrem/Calendar quarter - Any Organ.

The cumulative dose for the calendar year shall be limited to:

< 3 mrem - Total Body i and

<10 mrem - Any Organ.

The dose contribution will be calculated for all radionuclides identified in the liquid effluent released to the unrestricted area, using the following eq ua ti.on:

m 0 =Q Ai.1J Q TlC 1 1F~ (5) 1 1 g

where:

0. The cumulative calendar quarter or yearly dose to any organ j from liquid effluent for the total release period - (in mrem).

1 The length of the 1th release period over which C; and "1 are averaged for liquid releases - (in hours).

The number of releases for the time period under consideration.

Average concentration of nuclide i in the liquid effluent at point of discharge during the release Period Tl from any liquid release - (pCi/ml).

The site-related ingestion dose factor to the total body or critical organ j for each identified nuclide listed in Table 2-2 (in mrem/hr per pCi/ml).

The near field average dilution factor for C.lil during any liquid waste release. Defined as the ratio of the average radwaste discharge flow during the release to the product of the average flow from the site structure to unrestricted receiving waters times 100. This is a conservative value since the average river flow is 120,000 cfs and blowdown rate is only 6 cfs.

Li uid Radwaste Flow isc arge tructure xst x (6)

1 I I "i>, the ingestion dose factors for the total body and critical organs, are tabulated in Table 2-2. It embodies the dose factor, fish bioac-

. cumulation factor, pathway usage factor, and the dilution factor for- the plant diffuser pipe to the nearest potable water intake. The following equation was used to calculate the ingestion dose factors:

Uw

= K + UF BF.)OF.

A.) (P where:

A.) The composite dose parameter for total body or criti-cal organ of an adult for nuclide i (in mrem/hr per -.

~Ci/ml).

A conversion factor:

1.145+05 =[(105 PCi/eCi) x (105 m1/1iter)]-: 5750 hr/yr U

730 liter/yr - which is the annual water consumption by the maximum adult (Table E-4 of Regulatory Guide 1.109).

Fi Bioaccumulation factor for radionuclide i in fish

- (pCi/Kg per pci/liter) (Table A-1 of Regulatory Guide 1.109) .

Fi Adult ingestion dose conversion factor for nuclide i

- Total body or critical organ - (mrem/pCi).

'w Dilution factor from near field area to the nearest potable water intake - 200.

Adult fish consumption, 21 kg/yr (Table E-4 of Regulatory Guide 1.109).

'I

), i The values of BFi and DF. are listed in Table 2-1.

The quarter ly limits mentioned before represent one-half of the annual design objective of Section II.A of 10 CFR 50, Appendix I. If any of the limits (either that of the calendar quarter or calendar year) are exceeded, a special report pursuant to Section IY.A of 10 CFR 50, Appendix I, shall be filed with the NRC.

2.4.1 Projection of Doses The projected doses due to releases of WNP-2 radwaste liquid effluents will be calculated for each batch, using equation 5. If the sum of the accumulated dose to date for the month and the projected dose for the remainder of th8 month exceeds the technical specification 3.11.1.3 limits, then the liquid radwaste treatment system shall be used. This is to ensure compliance with Standard'echnical Specification 3.11.1.3. This technical specification states that the liquid radwaste treatment system shall be maintained and the-appropriate subsystem shall be used if the radioactive materials in liquid waste, prior to their discharge, when the dose, due to liquid effluent release to unrestricted areas when averaged over the month-would exceed 0.06 mrem to total'body or 0.2 mrem to any organ.

2.5 Radwaste Li uid Effluent Dilution Ratio and Alarm Set pints Calculations 2.5.1 Introduction The dilution alarm ratio and setpoints of the sample liquid effluent monitor are established to ensure that the limits of 10 CFR 20, Appendix B, Table II, Column 2, are not exceeded in the effluent at the discharge point (i.e.,

compliance with Standard Technical Specification 3.11.1.1, as discussed in section 2.3.1 of this manual).

The trip/alarm setpoint for the, liquid radwaste effluent monitor is calculated from the results of the radiochemical analysis of the waste solution. The setpoint will be set into the radwaste monitor just prior to the release of each batch of radioactive liquid.'.5.2 Methodolo for Oeterminin the Oilution Ratio Prior to discharge, the tank is isolated and recirculated for at least two liquid volumes, and a representative sample is taken from the tank. An isotopic. analysis of the batch will be made to determine the dilution ratio required to comply with 10 CFR 20 limits. Radwaste liquid effluents can only be discharged to the environment through the four-inch radwaste line. The maximum radwaste discharge flow rate is 190 gpm. Typical circulating water blowdown flow is approximately 2700 gpm, which would resulting in a dilution factor of 14 at the maximum radwaste flow.

From the sample analysis and the MPC.. values, a dilution ratio (O.R.) is calculated using the following equation:

(8) where:

O.R. The dilution ratio required for compliance with 10 CFR 20, Appendix 8, Table II, Column 2.

10

f Ci The undiluted concentration of radionuclide i in the batch to be released - pCi/m>

MP C- 10 CFR 20, Appendix 8, Table II, Colum', maximum permissible concentration for nuclide i - vCi/mi The total number of radionuclides in th'e batch to be released .

If the dilution ratio is equal to or less than one:

D.R. < 1 (9)

Than the tank may be discharged. at any circulating water or radwaste blow downr.ate .

If the dilution ratio (D.R.) exceeds unity (D.R. 1); discharge rates are set such that:

Fd Fm ~~~pR (10) where:

The maximum, allowed discharge flow rate from the liquid waste storage tank - the maximum pmp rate is 190 gpm.

Fd = The actual plant dilution flow rate - (circulating water blowdown flow rate).

11.

1 E 7 i

f

5.2.3 Set Point Determinations The calculation for the radiation monitor's alarm/trip point is as follows:

For O.R. yl:

Setpoint =

(Z, c,. x Ef i + Background x Fd/Fm ( 12a)

(max.)

For D.R.cl:

Setpoint =

(pc,. x Ef + Background x Fd/Fw ( 12b) i where:

i = undiluted concentration of'adionuclide i in the batch to be released in yCi/ml.

Efi is the radiation monitors response to nuclide i.

To assure of never exceeding the MPC,. limit, the setpoint will be set at 50 percent of the setpoint (max.).

2.6 Verification of '

Com liance with 10 CFR 50 endix I and 10 CFR 20 A endix B Verification of compliance with 10 CFR 50, Appendix I, and 10 CFR 20, Appen-dix 8, dose limits will be achieved by following WNP-2 Plant Operating Procedures for liguid discharge and a monthly run of LADTAP computer code.

2D Methods for Calculatin Doses to Man From Li uid Effluent Pathways Dose models presented in NRC Regulatory Guide 1.109, as incorporated in the LADTAP computer code, will be used for offsite dose calculation. The details of LAOTAP, including the program listing and user instruction, are included in the Offsite Dose Calculation Reference Manual (ODCRM).

2.7.1 Radiation Doses Radiation doses from potable water, aquatic food, shoreline deposit, and irrigated food pathways will be calculated by using the following eguations:

0

a. Potable Water U Mp R

apj

. = 1100 ~QQ.D F .

..exp(-a.ti )

i aipj p

b. Aquatic Foods U Mp

{ l4)

c. Shoreline Deposits R . = 110,000 ~P U M W Q,.T,.D, [exp(-x,.t ) (I - exp(-x,.t>)j (15)

d. Irrigated foods For all radionucl ides .except tritium:

'. re exp(-X .t Ei e )]

f I B.iv~

I'I exp(-kt )1 i b~

ap,.Q d.exp{-X.t R =

apj U

i i h )D aipj Y P,E.

v El PA.

1 animal 1

'"" v Ei fiB,(l - exp(->,.t>)] {16)

PA. iAw~Aw 1

13

I, For tritium:

I veg + animal apj ap v apj ap apj A v F Aw~Aw where:

ip The equilibrium bioaccumulation factor for nuclide i in pathway p, expressed as the ratio of the concen-tration in biota (in pCi/kg) to the radionuclide concentration in water (in pCi/liter), in liters/kg.

iv 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.

iAw The concentration of radionuclide i in water consumed by animals, in pCi/liter.

iv The concentration of radionuclide i in vegetation, in pCi/kg.

alp j The dose factor specific to a given age group a, radionuclide i, pathway p, and organ j, which can be used to calculate the radiation dose from an intake of a radionuclide, in mrem/pCi, or from exposure to a given concentration of a radionuclide in sediment, expressed as a ratio of the dose rate (in mrem/hr) and the areal radionuclide concentration (in pCi/m~).

d- The deposition rate of nuclide i, in pCi/m~ per hour.

The flow rate of the liquid effluent, in ft3/sec.

The fraction of the year crops are irrigated, dimensionless.

iA The stable element transfer coefficient that relates the daily intake rate by an animal to the concen-tration in an edible portion of animal product, in pCi/liter (milk) per pCi/day or pCi/kg (animal pro-duct) per pCi/day.

The mixing ratio (reciprocal of the dilution factor) at the point of exposure (or the point of withdrawal of drinking water or point of harvest of aquatic food), dimensionless.

The effective "surface density" for soil in kg (dry soil)/m~ (Table E-1, Regulatory Guide 1.109).

QAw The consumption rate of contaminated water by an animal, in liters/day.

QF The consumption rate of contaminated feed or forage by an animal, in kg/day (wet weight).

The release rate of nuclide i, in Ci/yr.

The fraction of deposited activity retained on crops, dimensionless (Table E-15, Regulatory Guide 1.1.09).

15

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

The period of time for which sediment or soil is exposed to the contaminated water, in hours (Table E-15, Regulatory Guide 1.109).

The time period that crops are exposed to contamina-tion during the growing season, in hours (Table E-15, Regulatory Guide 1.109).

A holdup time that represents the time interval between harvest and consumption of the food, in hours (Table E-15, Regulatory Guide 1.109).

The radioactive half life of nuclide i, in days.

--The average transit time required for nuclides to reach the point of exposure. For internal dose, t P

is the total time elapsed between release of the nuclides and ingestion of food or water, in hours (Table E-15, Regulatory Guide 1.109).

A usage factor that specifies the exposure time or intake rate for an individual of age group a associ-ated with pathway p, in hr/yr, E/yr, or kg/yr (Table E-5, Regulatory Guide 1.109).

16

The shoreline width factor, dimensionless (Table A-2, Regulatory Guide 1.109).

Y The agr icultural productivity (yield), in kg (wet "2

weight) /m (Table E-15, Regulatory Guide 1.109).

The effective removal rate constant for radionuclide i from crops, in hr, where >E. = X. + A Ei i w's 1

the radioactive decay constant, and X is w

the removal rate constant for physical loss by weathering (Regulatory Guide 1.109, Table B-15).

The radioactive decay constant of nuclide i, in hr-'100 The factor to convert from (Ci/yr)/(ft /sec) to pCi/1 i ter .

110,000 The factor to convert from (Ci/yr)/(ft /sec) to pCi/liter and to account for the proportionality constant used in the sediment radioactivity model.

These equations yield the dose rates to various organs of individuals from the exposure pathways mentioned above.

2:7.2 Plant- Parameters WNP-2 is a river shoreline site with a variable effluent discharge flow rate 0 to 7500 gpm (2690 gpm average). The population center nearest WNP-2 is the city of Richland, where drinking water withdrawal takes place. The applicable dilution factor is 20,000, using full river flow. The time required. for re-leased liquids to reach Richland, approximately 12 miles downstream, is esti-mated at 4.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. Richland is the "realistic case" location, and doses cal-culated for the Richland location are typically applicable to the population as a whole. Individual and population doses based on Richland parameters are calculated for all exposure pathways.

17

Only the 75,000 population downstream of the WNP-2 site is affected by the liquid effluents released. There is no significant commercial fish harvest in

~ ~ ~ ~ ~ ~

the 50-mile radius region around WNP-2.~ Sportfish harvest is estimated at

~ ~ ~

14,000 kg/year .~

For irrigated foods exposure pathways, it can be assumed that production with-in the 50-mile radius region around WNP-2 is sufficient to satisfy consumption requirements.

I Other relevant parameters relating to the irrigated foods pathways are defined as follows:

~l "4 4 I ~Pi I ~Bi I I

~FOOd T O ( liter /m2/mo) (kg/m2) (Days)

Vegetation 150 5.0 70 Leafy Vegetation 200 1.5 70 Feed for Milk Cows 200 1.3 30 Feed for Beef Cattle 160 2.0 130 Source terms are measured based on sampled effluent.

Table 2-3 summarizes the LADTAP input parPameters. Documentation and/or calcu-lations of these parameters are discussed in detail in the WNP-2 ODCRM, and Rad. Prog. calculation Log 83-1.

2.8 Com liance with Technical S ecification 3.11.1.4 2.8.1 Maximum Allowable Li uid Radwaste Activit in Tem orar Radwaste Hold-U Tanks The use of temporary liquid radwaste hold-up tanks is planned for WNP-2.

Technical Specification 3.11.1.4 limits the amount of liquid radwaste stored in the tanks to 10 curies, except for tritium and dissolved noble gases. The 18.

surveillance requirements state that the quantity of radioactive material in

~ ~ ~

the hold-up tank shall be determined at least once per seven days when

. radioactive material is added to the tank.

~ ~ ~

~

2.8.2 Maximum Allowable Li uid Radwaste in Tanks That Are Not Surrounded b Liners Dikes or Wall s Although permanent outside liquid radwaste tanks which are not surrounded by liners, dikes, or walls are not planned for WNP-2, Equation 18 will be used should such tanks become necessary in the future.

AT=- Kd bP C ~ e,"A it where:

AT Total allowed* activity in tank gcuries).

N'. Maximum permissible concentration of radionuclide i (10 l7R 20, Appendix B, Table II, Column 2) .

Decay constant (years ) radioisotope i.

Transit time of ground water from WNP-2 to WNP-I well (WtP-2 FSAR Section 2.4) = 67 years.

Fraction of radioisotope i = .

A QAi

~

1 All radioisotopes in tank except tritium and noble gases.

Kd Dispersion constant based on hydrological parameters.

2.4E+5 Ci per pCi/cc.

19

t e

r j The total allowed activity (AT) is based on limiting WNP-1 we)) water to of the entire liquid content of the tank spilled to ground

~

then migrated via ground water to the WNP-1 well. The WNP-1 well is the

~

and ~

loca- tion of maximum concentration since it is the nearest source of ground

~ ~ ~ ~ ~

water and conditions are such that no spill of liquid would reach surface water . The 70-85 foot depth of the water table and the low ambient moisture of the soil requires a rather ]ar ge volume of spillage for the liquid to even reach the water table in less than several hundred year's. However, allowed tank activity (AT) is conservative]y based on all liquid radwaste in the tank instantaneously reaching the water table.

The hydrological analysis performed for the WNP-2 FSAR (Section 2.4) deter-mined that the transit time through the ground water from WNP-2 to the WNP-1 we]1 is 67 years for Strontium and 660 years for Cesium. These two radio-nuclides are representative of the radionuclides found in liquid radwaste.

Strontium is a moderate sorber and Cesium strongly sorbs to soil particles.

This calculation conservatively treats all radionuclides as moderate sorbers with a transit time of 67 years.

The concentration of each radionuclide in the well (CWi) is simply the con-centration in the tank (CT ad>usted for radioactive decay during transit

)

(e-><<) and divided by the concentration reduction factor (CFR min). Limit-ing well concentration to 1 NPC~yie]ds:

CW NPC 1

= 1 ~

Z CT. e CFR

~

1

.~ f1PC.~

From page 2.4 of WNP-2 FSAR.)

i

~

min 1/2 CFR . (20) min 2V 20

'where:

L = Migration distance = 1 mile.

V = Volume of tank.

a i a = Dispersion constants.

+~ ~

Z Combining Equations 2 and 3 yields:

CT. 2V e 1

~ i 1 = (21)

(4mL) (a x a / MPC.~

Y z) 1 Substituting Ai for CTi V and reorganizing terms yields.

(4 L) 3/2( E 1/2 y z )

1 (22)

~wc 1

Making the following substitutions A. fi AT (4 L) 3/2(

1/2

)

= ". x 10 Ci/Ci = 2.4 x 10 Ci per v Ci Kd (23)

CC 21

yie1ds:

K = A d T ~MPC-;e P't or A = K f

MPC.e (Equation 18) 22

~ II I," v ~ ~ A f

Table 2-1 FISH BIOACCUHULATION FACTORS (BF.) (

AND ADULT INGESTION DOSE CONVERSION FACTORS (DF )

Dose Conversion Factor (DF.)

Fish Bioaccumulation Total GI Nuclide Factor (BF;) Body . Bane Thyroid Liver Tract (PCi/kg per PCi/liter)

H-3 9.0E-01 1.1E-07 (3) 1.1E-O? 1.1E-07 1.1E-07 Na-24 1. OE+02 1.7E-06 1.7E-06 1.7E-06 1.7E-06 1.7E-06 P-32 1.0E+05 7.5E-06 1.9E-04 (3) 1.2E-04 2.2E-05 Cr-51 2.0E+02 2.7E-09 . (3) 1.6E-09 (3) 6.7E-07'.4E-05 Mn-54 '.0E+02 8.7E-07 (3? (3) 4.6E-06 Nn-56 4.0E+02 2.0E-OS (3) (3) 1.2E-07 3.7E-06 Fe-55 1.0E+02 4.4E-07 2.8E-06 (3) 1.9E-06 1.1E-06 Fe-59 1.0E+02 3.9E-06 4.3E-06 (3) 1.0E-05 3.4E-05 Co-58 5.0E+01 1.7E-06 (3) (3) 7.5E-07 1.5E-05 Co-60 5.0E+01 4.7E-06 (3) (3) 2.1E-06 4.0E-05 Ni-65 1.0E+02 3.1E-OS 5.3E-07 (3) 6.9E-08 1.7E-06 CU-64 5.0E+01 3.9E-OS (3) (3) 8.3E-OS 7.1E-06 Zn-65 2.0E+03 7.0E-06 4.8E-06 (3) 1.5E-05 9.7E-06 Zn-69 2.0E+03 1.4E-09 1.0E-OS (3) 2.0E-OS 3.0E-09 Br-83 4.2E+02 4.0E-08 (3) (3) (3) 5.8E-OS Br-84 4.2E+02 5.2E-OS (3) (3) (3) 4.1E-13 Rb-89 2.0E+03 2.8E-08 (3) (3) 4.0E-OS 2.3E-21 Sr-89 3.0E+-1 S.SE-06 3.1E-04 (3) (3) 4.9E-05 Sr-90 3. OE+01 1.9E-03 7.6E-03 (3) (3) 2.2E-04 (1)NRC Regu'iatory Guide 1.109, Table A-1.

(2)NRC Regulatory Guide 1.109, Table E-11.

(3)No data listed in Regulatory Guide 1.109, Table E-11. (Use whole body dose conversion factor as an approximation.)

23

i Table 2-1 (contd.)

Dose Conversion Factor (DF.)

Fish 1 Bioaccumulation Total GI Nuclide Factor (BF;) Body Bone Thyroid Liver Tract PCi g per PCi/liter)

Sr-91 3.0E+Ol 2.3E-07 5.7E-06 (3) (3) 2.7E-05 Sr-92 3.0E+01 9.3E-OS 2.2E-06 (3) (3) 4.3E-05 Y-90 2.5E+01 - 2.6E-10 9.7E-09 (3) (3) 1.0E-04 Y-91m 2.5E+01 3.5E-12 9.1E-11 (3) (3) 2.7E-10 Y-91 2. 5E+01 3.8E-09 1.4E-07 (3) (3) 7.8E-05 Y-92 2.5E+01 2.5E-11 8.5E-10 (3) (3) 1.5E-05 Y-93 2.5E+01 7.4E-11 2.7E-09 (3) (3) S.SE-05'.0E-05 Mo-99 1.0E+01 8.2E-07 (3) (3) 4.3E-06 Tc-99m 1.5E+01 8.9E-09 2.5E-10 (3) 7.0E-10 '.1E-07 Tc-101 1. 5E+01 3.6E-09 2.5E-1.0 (3) 3.7E-10 1.1E-21 Ru-103 1.0E+01 S.OE-OS 1.9E-07 (3) (3) 2.2E-OS RU-105 1.0E+Ol 6.1E-09 ~ 1.5E-OS (3) (3) 9.4E-06 Rh-105 (3) (3) (3) (3) (3) (3)

Te-129m 4.0E+02 1.8E-06 1.2E-OS 4.0E-06 4.3E-06 5.8E-05 Te-129 4.0E+02 7.7E-09 3.1E-OS 2.4E-08 1.2E-OS 2.4E-OS Te-131m 4.0E+02 7.1E-07 1.7E-06 1.3E-06 8.5E-07 8.4E-OS Te-131 4.0E+02 6.2E-09 2.0E-OS 1.6E-OS 8.2E-09 2.8E-09 Te-132 4.0E+02 1.5E-06 2.5E-06 1.8E-06 1.6E-06 7.7E-05 I-131 1.5E+01 3.4E-06 ~

4.2E-06 2.0E-03 6.0E-06 1.6E-06

'-132 1. 5E+01 1.9E-05 2.0E-07 2.0E-OS 5:4E-07 1.0E-07 I-133 1. Sf~01 7.5E-07 1.4E-06 3.6E-04 2.5E-06 2.2E-06 I-134 1.5E+01 1.0E-07 1.0E-07 S.OE-06 2.9E-07 2.5E-10 I-135 1.5E+01 4.3E-07 4.4E-07 7.7E-OS 1.2E-06 1.3E-06 Cs-134 2.0E+03 1.2E-04 6.2E-05 (3) 1.5E-04 2.6E-06 Cs-136 2.0E+03 1.9E-05 6.5E-06 (3) 2.6E-05 2.9E-06 Cs-137 2. OE+03 7. 1E-05 8. OE-05 (3) 1.1E-04 2.1E-06 Cs-138 2. OE+03, 5.4E-OS 5.5E-OS (3) 1.1E-07 4. 7E-13 Ba-139 4.0E+0 2.8E-09 9.7E-OS (3) 6.9E-11 1.7E-07 24

Tab1e 2-1 (contd.)

Dose Conversion Factor (DF )

Fish 1 Bioaccumulation Total GI Nuclide Factor (BF ) Body Bone Thyroid Liver Tract g per PCi/1i ter)

Ba-140 4.0E+0 1.3E-06 2.0E-05 (3) 2.6E-08 4.2E-05 La-140 2.5E+Ol 3.3E-10 2.5E-09 (3) 1.3E-09 9.3E-05 La-141 2.5E+01 (3) (3) (3) (3) (3)

La-142 2.5E+Ol 1.5E-ll 1.3E-10 (3) 5.8E-11 4.3E-.07 Ce-141 1.0E+0 7.2E-10 '.4E-09 (3) 6.3E-09 2.4E-05 Ce-143 1.0E+0 1.4E-10 1'.7E-09 (3) , 1.2E-06 4.6E-05 Pr-143 2. 5E+01 4. 6E-10 9.2E-09 (3) 3.7E-09 .4.0E-OS W-187 1.2E+03 3.0E-08 1.0E-07 (3) 8.6E-08 2.8E-05 Np-239 1.0E+01 6.5E-ll 1.2E-09 (3) 1. 2E-10 2.4E-05

I Table 2-2 INGESTION 00SE FACTORS (A..)

lj FOR TOTAL BOOY ANO CRITICAL ORGAN

>n mrem r per p i m Liquid Effluent*

Total Gi Nucl i de ~Bod Bone .

~Th oid Liver Tract H-3 2.8E-01 2.8E-01 2.8E-01 2.8E-01 Na-24 4.1E+02. 4.1E+02 .'4.1E+02 4.1E+02 4.1E+02 P-32 1.8E+06 4.6E+07 2.9E+07 5.3E+06 Cr-51 1.3E+00 7. 7E-Ol 3.'2E+02 Hn-54 8.3E+02 4. 4E+03 1.3E+04 Mn-56 1.9E+01 l. 2E+02 3.6E+03 Fe-55 1.1E+02 6.7E+02 4. 6E+02 2.6E+02 Fe-59 9.4E+02 1.0E+03 2. 4E+03 8.2E+03 Co-58 2.0E+02 9.0E+01 1.8E+03 Co-60 5. 7E+02 2.5E+02 4.8E+03 Ni -65 7.4E+00 1. 3E+02 1.7E+01 4.1E+02 Cu-64 4.7E+00 1. OE+01 8. 5E+02 Zn-65 3.4E+04 2. 3E+05 7.2E+04 4.7E+04 Zn-69 6.7E+00 4.BE+01 9.65+01 1 . 4E+O1 Br-83 4.0E+01 5.BE+01 Br-84 5.2E+01 4.1E-04 Rb-89 1.3E+02 ** 1.9E+02 1.1E-10 Sr-89 6.4E+02 2. 3E+04 3.5E+03 Sr-90 1.4E+05 5.5E+05 1.6E+04 Sr-91 1.7E+01 4.1E+02 2. OE+03 Sr-92 6.7E+00 1.6E+02 3.1E+03 "Based on conservative radionuclide mix obtained from GALE Liquid Code.

Equation (7) was used to calculate the ingestion dose factors. (A;>).

~No Ingestion Oose Factor (DF;) is listed in Table E-ll of Regulatory Guide 1.109. (Whole body dose factor value will be used as an approximation.)

26

Tab1e 2-2 (contd.)

Tota1 Gi Nuc1ide ~Bod Bone ~Th roid Liver Tract Y-90 1.7E-02 5. 9E-01 6.0E+03 Y-91m 2.1E-04 5.5E-03 ** 1.6E-02 Y-91 2.3E-01 8.4E+00 4.7E+03 Y-92 1.5E-03 5.1E-02 9.0E+02 Y-93 4.5E-03 1. 6E-01 5.1E+03 Mo-99 2.0E+01 1.0E+02 2.4E+02 Tc-99m 3.2E-01 9.1E-03 2.5E-02 1.5E+Ol Tc-101 1. 3E-01 9.1E-03 1.3E-02 4.0E-14 Ru-103 1.9E+00- 4.6E+00 5.4E+02 Ru-105 1.5E-01 3.7E-01 2.3E+02 Rh-105 Te-129m 1.7E+03 1.1E+04 3.BE+03 4.1E+03 5.6E+04 Te-129 7.4E+00 3.0E+01 2.3E+01 1.1E+01 2.3E+01 Te-131m 6.8E+02. 1.6E+03 1.3E+03 8. 1E+02 8.1E+04 Te-131 5.9E+00 1.9E+01 1. 5E+01 7.9E+00 2.7E+00 Te-132 1.4E+03 2.4E+03 1.7E+03 1.5E+03 7.4E-04 I-131 1.2E+02 1.5E+02 7.3E+04 2.2E+02 5.BE+01 I-132 6.9E+02 7.3E+00 7.3E+02 2.0E+01 3.6E-OO I-133 2. 7E+01 5.1E+01 1.3E+04 9.1E+Ol 8.0E+02 I-134 3.6E+00 3.6E+00 1.8E+02 '.1E+01 9.1E-03 I-135 1.6E+01 1.6E+01 2.BE+03 4.4E+Ol 4.7E+01 Cs-134 5.BE+05 3.0E+05 7.2E+05 1.2E+04 Cs-136 9.9E+04 3.1E+04 1.2E+05 1.4E+04 Cs-137 3.4E+05 3.8E+05 5.3E+05 1.0E+04 Cs-138 2.6E+02 2.6E+02 5.3E+02 2.3E-03 Ba-139 2.8E-02 9.7E-01 6.9E-04 1.7E+00 Ba-140 1.3E+Ol 2.0E+02 2.6E-01 4.2E+02 La-140 2.0E-02 1.5E-01 7.8E-02 5.6E+03 La-141 La-142 9.0E-04 7.8E-03 3.5E-03 2.6E+01 Ce-141 2.0E-03 '.6E-02 1.8E-02 6.7E+Ol 27

Table 2-2 (contd.)

Total Gi Nuclide ~Bod Bone ~Th roid Liver Tract Ce-143 3.9E-04 4.8E-03 3.4E+00 1.3E+02 Pr-143 2.8E-02 5.5E-01 2.2E-01 2.4E+03 M-187 8. 6E+01 2.9E+02 2.5E+02 S.OE+04 Np-239 1.6E-03 2.9E-02 2.9E-03 5.BE+02 28

ll TABLE 2-3 INPUT PARAMETERS USED TO CALCULATE MAXIMUM INDIVIDUAL DOSE FROM LI UID EFFLUENTS

~i "k i

~ ~

Ih River Dilution: 20,000 River Transit Time: 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Water Treatment and Delivery-Time: 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Usage Factors:- Adult = 814 1/yr Teenager = 567 1/yr Child = 567 1/yr Infant = 344 1/yr

'ish River Dilution: 20,000 for Richland 2,000 for WNP-2 Slough Time To Consumption: 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Usage Factors: Adult = 48 kg/yr Teenager =.

36 kg/yr Child = 15 kg/yr Infant = 0 Recreation River Dilution: '0,000 Shoreline Width Factor: 0.2 Usage Factors: Shoreline Activities: Adult 298 hr/yr Teenager 1665 hr/yr Child 349 hr/yr Infant 0 Sw immi'ng: Adult 59 hr/yr'36 Teenager hr/yr Child 68 hr/yr Boating: Adult 145 hr/yr Teenager 31 hr/yr Child 0 hr/yr Infant 0 Irri ated Foodstuffs River Dilution: 20,000 River Transit Time: 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Leafy

~ie etab les Hilt Meat ~Ue etablas Food Delivery Time: 60 days 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 20 days 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Usage Factors':

Adult 529 kg/yr 224 1/yr 119 kg/yr '29 kg/yr Teenager 670 kg/yr 408 1/yr 74 kg/yr 36 kg/yr Child 559 kg/yr 346 1/yr 46 kg/yr 29 kg/yr Infant 0 346 0 0 Monthly Irrigation Rate: 150'/m2 200 1/m2 160 1/m2 200 1/m2 Annual Yield: 5 1/m2 1.3 1/m2 2.0 kg/m2 1.5 kg/m2 Annual Growing Period: 70 days 30 days 130 days 70 days, Annual 50-Mile Production: 1.5E+07 7.3E+06 2.6E+06 8.0E+05 29

k 8 ~

t I I 3.0 GASEOUS EFFLUENTS DOSE CALCULATIONS 3.1 Introduction WNP-2 gaseous effluents are released on a continuous basis; in addition, batch releases also occur when containment and mechanical vacuum pump purges are performed and when the OFF-GAS treatment system. operates in the charcoal bypass mode. The gaseous effluents released from WNP-2 will meet instanta-neous technical specification requirement at the site boundary.

Figure 3-1 delineates the WNP-2 Site boundary. There are several low occupancy unrestricted locations within the site boundary. These locations, with the exception of the WNP-2 visitor center, are not continuously controlled by the Supply System. The special locations are:

1. Wye bur ial site - normally controlled by DOE.

2. DOE train - two railroad lines pass through the site (approximately 3 miles of line). According to DOE, the train makes one round trip a r> day, through the site at an average speed of 20 mph, 5 days a week, weeks/year.

52

3. BPA Ashe Substation - occupied 2080 hour0.0241 days <br />0.578 hours <br />0.00344 weeks <br />7.9144e-4 months <br />s/year . These people are not normally controlled by the Supply System but are involved in activ-

. ities directly in support of WNP-2.

4. WNP Supply System Visitor Center - assumed occupied 8 hrs/yr by non-Supply System individuals.

5. WNP occupied 2080 hrs/yr . This location is controlled by the Supply System. However, activities are not in direct support of WNP-2.

6. WNP occupied 2080 hrs/yr. This location is controlled by the Supply System. However, activities are not in direct support of WNP-2.

30

All other locations listed in Figure 3-1 support WNP-2 activities and are controlled by the Supply System.

Air doses and doses to individuals at these locations were calculated based on the NRC GALE code design base mixture, location specific estimated occupancy, and X/Qs from XOQDOQ. (Note: Desert Sigmas were used in calculating X/Q and D/Q values, and are listed in Table 3-10 to 3-12). These, doses are listed in

=-

Tables 3-16 and 3-17 along with the doses to the maximum exposed individual.

The maximum ex osed individual is currently an infant residing in Taylor Flats (4.2 miles SE of WNP-2). This is the closest residential area with the highest X/Q and D/Q values. Maximum occupied air doses inside the site are only a fraction of the site boundary air dose for continuous occupancy.

3.2 Gaseous Effluent Radiation Monitorin S stem 3.2.1 Main Plant Release Point The Main Plant Release is instrument monitored for gaseous radioactivity prior to discharge to the environment via the main plant vent release point.

Particulates and iodine activity are accumulated in filters which will be r )

changed and analyzed at least weekly per Technical Specification 3.3.7.12.

The effluent is supplied from: the gland seal exhauster, mechanical vacuum pumps, treated off gas, standby gas treatment, and exhaust air from the entire reactor building's ventilation.

'wo 100-percent capacity vanaxial fans supply 98,000 CFM ventilation air. One is.'normally operating, the other is in standby. The radiation monitors are located on the ventilation exhaust plenum.

Effluent monitoring consists of beta scintillators and two ion chamber LOCA monitors. The beta scintillator has a four inch. thick lead shielded chamber and has an estimated response of 50 cpm/pCi/ml to Kr-85.

The read out meter and recorder is located in the main control room panel BD-RAD-24. The analogue count rate meter has a range of 10-10 cpm. Power 31

is provided from 125 VDC divisional buses. This monitor has no control function but annunciates in the main control room. The alarm will initiate

~

~ ~

proper action as defined in the WNP-2 Plant Procedures.

3.2.2 Radwaste Buildin Ventilation Exhaust Monitor The radwaste building venti'lation exhaust monitor ing system monitors the radio-activity in the exhaust air prior to discharge. Radioactivity can originate from: radwaste tank vents, laboratory hoods, and various cubicles housing liquid process treatment equipment and systems.

The radwaste building exhaust system has three 50 percent capacity exhaust filter units of 42,000 cfm capacity. Each exhaust unit has a medium-efficiency prefilter, a high efficiency particulate air filter (HEPA and two centrifugal.

fans. Total exhaust flow will vary as the combined exhaust unit maintains a radwaste building ~P of-0.25 inches H20 to the environment.

Particulate and iodine air sample filters are changed weekly for laboratory analysis. After the particulate and iodine filters, the air sample streams are combined in a manifold prior to being monitored by a beta scintillator.

The beta scintillator, on radwaste 487'evel 'southwest corner is mounted in a three inch lead shielded chamber and has an estimated response of 50 cpm/pCi/ml to Kr-85. The readout meter and recorder is located in the main control room panel BO-RAO-24. The analog count rate meter has a range of 10 to 106 cpm. Power is provided from 125 VDC divisional buses. This monitor has no control functions but annunciates in the main control room. The alarm will initiate prope. action as defined in the WNP-2 plant procedures.

3.2.3 Turbine Buildin Ventilation Exhaust Monitor This monitoring system detects fission and the activation products from the turbine building air which may be present due to leaks from the turbine and other primary components 'in the building.

32

The turbine building main exhaust system consists of four roof-mounted centri-fugal fans which draw air from a central-exhaust plenum. Three fans operate continuously, with one in standby to provide a flow of 260,000 cfm.

A representative sample is extracted from the exhaust vent and passed through a particulate and charcoal filter. The air'ample then passes to a beta s cin ti 1 1 ato r.

The beta scintillator is mounted in a three inch lead shielded chamber and has an estimated response of 50 cpm/pCi/ml to Kr-85. The monitor is on the of the radwaste building and the readout meters and the records are in 525'evel the main control room BD-RAD-24. The analog count rate meter has a range of 6

10 to 10 cpm, power is provided from the 125 VDC divisional buses. This monitor has no control functions but annunciates in the main control room.

The alarm will initiate proper action as defined in the WNP-2 plant procedures.

3.3 10 CFR 20 Release Rate Limits Limits for release of airborne effluents to the unrestricted area are stated in Technical Specification 3.11.2.1. The dose rate in unrestricted areas due to radioactive materials released in gaseous effluents from the site shall be limited to the following values:

(a) "The dose rate limit for noble gases shall 'be<<500 mr em/yr to the total body and~3000 mrem/yr to the skin.

(b) "The dose rate limit for all radioiodines and for all radio-active mater ials in particulate form and radionuclides other than noble gases with half-lives greater than eight days shall be <1500 mr em/yr to any organ."

33 I

3.3.1

~ ~ Noble Gases In order to comply with Technical Specification 3.11.2.1, the following equa-tions must hold:

Whole body:

m KiL(X/0)m 0.1 I

+ (~X0) g 0

g

) j( 500 mrem/yr () )

Sk in (Li + 1.1Mi Tom ~m

+ ~ 9 ) ~ 3000mrem/yr (2) 3.3.2 Radioiodines and Par ticul ates Part "b" of Technical Specification 3.11.2.1 requires that the release rate limit for a'.1 radioiodines and radioactive materials in particulate form and radionuclides other than noble gases must meet the following relationship:

Any organ:

Q p, N ~iN g ~ig <1500 mrem/yr (3) 1 The terms used in equations 1 through 3 are defined as follows:

K.

1

= The total body factor due to gamma emissions for each iden-tified noble gas radionuclide i (mrem/yr per )

3 Ci/m ).

L 1

= The skin dose factor due to beta emissions for each iden-tified noble gas radionuclide i (mrem/yr per ) Ci/m 3 ).

34

The air dose factor due to gamma emissions for each identi.-

fied noble gas radionuclide in mrad/yr per yCi/m (unit conversion constant of 1.1 mrem/mrad converts air dose to skin dose).

P. = The dose parameter for all radionuclides other than noble 3

gases for inhalation pathway, (mrem/yr per pCi/m ) and for 2 .

food and ground contamination pathways, (m 'rem/yr per pCi/sec). The dose factors are based on the critical in-dividual organ and the most restrictive age group, which is infant (see Section 3.3.2.1).

The release rate of radionuclide i in gaseous effluent from mixed mode release. The main plant release point is a partially elevated mixed mode release.

q = The release rate of radionuclide i in gaseous effluent from all grou'nd-level releases (vCi/sec).

(~) (sec/m )". For partially elevated mixed mode releases from the main plant vent release point. The highest calculated partially elevated annual average relative concentration for any area at or beyond the site boundary.

(~) g (sec/m 3 ). For all Turbine Building and Radwaste releases .

The highest calculated ground level annual average relative concentration for any area at or beyond the site boundary.

35

"g = The highest calculated annual average dispersion parameter for estimating the dose to an individual at the controlling location due to all ground level releases.

(sec/m ). For the inhalation pathway. The loca-tion is the site boundary in the sector of maximum concentration.

W = m-2. For ground plane pathways. The location is the site boundary in the sector of maximum concentration.

The highest calculated annual average dispersion parameter for estimating the dose to an individual at the controlling ~

location due to partially elevated releases:

sec/m . For inhalation pathway. The location is the site boundary in the sector of maximum concentration.

I m . For ground plane pathways. The location is the site boundary in the sector of maximum concentration.

Th<<<<t<<s. "i and M, relate the radionuclide airborne concentrations to various dose rates assuming a semi-infinite cloud. These factors are listed in. Table B-1 of Regulatory Guide 1.109 and in Table 3-1 of this manual.

The X/Q values used in the equations for the implementation of Technical Specification 3.11.2.1 are based upon the maximum long-term annual average at the site boundary. The distances between the nearest unrestricted area and the WNP-2 site are listed in Table 3-2. The distances between WNP-2 and the nearest vegetable garden, milk cow, and beef animal are tabulated in Table 3-3, along with representative X/Q and D/Q values.

36

0

The X/g and D/g values listed in Tables 3-10 through 3-12 reflect correct ac-quired meteorological data up to 1983 and were utilized in the initial GASPAR Computer runs. Subsequent reports will use updated X/g and 0/g averages Char-acteristics of WNP-2 gaseous effluent release points are listed in Table 3-13.

3.3.2.1 Dose Parameter for Radionuclide i (Pi)

Analysis of GALE Code release mixtures show that thyroid doses from radio-iodine inhalation are much larger than all other doses. Therefore, routine assessment of compliance with Equation 3 will be performed only for child thyroid dose from radioiodine:inhalation.

The dose parameters used in Equation 3 are based on:

1. Inhalation and ground plane. (Note: Food pathway is not applicable to MNP-2 since no food is grown at or near the restricted area boundary.)

2. The annual average continuous release meteorology at the site boundary.

3. The critical organ for each radionuclide (thyroid for radioiodine).

4. The most restrictive age group.

Calculation of P-I (Inhalation): The following equation will be used to calcu-late I (Inhalation).

P,.

P - ( Inh al ati on) = KA (BR DFA; (mrem/yr per><C 3

i/m )

)

37

where:

KA = A constant of conversion, 106 pCi/pCi.

BR = The breathing rate of the child age group, (m3/yr) = m3/yr.

DFA. The critical organ inhalation dose factor for the child age group for the ith radionuclide in mrem/pCi. The total body is considered as an organ in the selection of DFA; The inhalation dose factor for DFAi for the child age group is listed ln Table E-9 of Regulatory Guide 1.109 and Tables 3-4 of this manual. Resolving the units yields:

I (Inhalation) 9 3 P; = = (1.4 x 10 )(DFAi) (mrem/yr per pCi/m ) (e)

The P.

I (Inhalation) values for the child age group are tabulated in Table 3-4 C of this manual.

3.4 10 CFR 50 Release Rate Limits The requirements pertaining to 10 CFR 50 release rate limits are specified in Technical Specifications 3.11.2.2 and 3.11.2.3.

Technical Specification 3.11.2.2 deals with the air dose from noble gases and requires that the air dose at or beyond the site boundary due to noble gases released in gaseous effluents shall be-limited to the following:

(a) "During any calendar quarter, to~5 mrad for gamma radiation and towl0 mrad for beta radiation."

1 (b) "During any calendar year, to~10 mrad for gamma-radiation and(20 mrad for beta radiation."

38

Technical Specification 3.11.2.3 deals with radioiodines and radioactive matc-rials in particulate form, and requires that the dose to an individual from

~ ~ ~

h ~

radioiodines, radioactive materials in particulate form, and radionuclides

~ ~ ~ ~ ~

other than noble gases with half-lives greater than eight days in gaseous

~ ~ ~

, effluents released to unrestricted areas shalI be limited to the following:

(a) "During any calendar quarter, to +7.5 mrem."

(b) "During any calendar year, to <15 mrem."

3.4.1 Noble Gases Technical S ecification 3.11.2.2 The air dose at or beyond the site boundary due to noble gases released in the gaseous effluent will be determined by using the following equations.

I

a. During any calendar quarter, for gamma radiation:

( ) 3.17 x 10 0 p iLL(X/Q)g Qiig Mi + (X/q) gigqi .+ (X/Q)MQ M lm

+ (X/q)qmgt +5 mrad (8)

During any calendar quarter, for beta radiation:

3.17 x 10 Z N; [(X/g) 0; + (X/q) q; + (X/Q) Q; + (X/q)gq,~]<10 farad (0) 1

b. During any calendar year, for gamma radiation:

3.17 x 10 Z M. (77/) Q. + (X/q) q. + (77))MP.m +(X/q) q i~10 mrad (10) 1 39

'1

'l

~ 'wN ~1 '+i 0'ak I h a ~ . 'p+Jv m,, vv, ~ a J 4ht~aA 6 ~ loat4ll 4,'al %4.".'c a > '

Ouring any calendar year, for beta radiation:

3.17 x 10 Z N< l(X)Q) Q. + (X/q) q + (X/Q) 0( + (X/q) q,. ]C20 mrad (11) where:

The air dose factor due to gamma eranissions for each identified noble gas radionuclide, in mrad/yr per (Mi values are listed in Table 3-1).

The air dose factor due to beta emissions for each iden-tified noble gas radionuclide, in mrad/yr per pCi/m3

("i values are listed in Table 3-1).

(>Kg = For ground level release points. The highest calculated annual average relative concentration for area at or beyond the site area boundary for long-term releases (greater than 500 hr/yr). (Sec/m3)

For ground level release points. The relative concentration for areas at or beyond the site area boundary for short-term releases (equal to or less than 500 hr/yr). (Sec/m3)

For partially elevated release points. The highest calculated annual average relative concentration for areas at or beyond the site boundary for long-term releases (greater than 500 hr/yr). (Sec/m3)

For partially elevated release points. The relative concentration for areas at or beyond the site boundary for short-term releases (equal to or less than 500 hr/yr). (Sec/m3) 40

The average release of noble gas radionuclides in gaseous effluents, i, for short-term releases (equal to or less than 500 hr/yr) from the main plant release point, in pCi. Releases shall be cumulative over the calendar quarter or year, as appropriate.

The average release of noble gas radionuclides in gaseous effluents, i, for short-term releases (equal to or less than, 500 hr/yr) from Radwaste and Turbine Building, in pCi. Releases shall be cumulative over the calendar quarter or year, as appropriate.

'I OiM = The average release of noble gas radionucl ides in gaseous releases, i, for long-term releases (greater than 500 hr/yr) from the main plant release point, in pCi. Release shall be cumulative over the calendar quarter or year, as appropriate.

The average release of noble gas radionuclides in gaseous effluents, i, for long-term releases (greater than 500 hr/yr) from Radwaste and Turbine Building, in >Ci. Releases shall be cumulative over the calendar quarter or year, as appropriate.

3.17 x 10"B = The inverse of the number of seconds in a year.

3.4.2 Radioiodines and Particulates Technical S ecification 3.11.2.3 The following equation calculates the dose to an individual from radioiodines, radioactive material in particulate form, and radionuclides other than noble gases with half-lives greater than eight days in .gaseous effluents released to the unrestricted areas:

41

e I

a. During any calendar quarter:

3.17 x 10 P R. [Wq< + w q,. + W 0,. + w q ]<7.5 mrem (>2)

b. During any calendar .year:

3 17 x 10 Q g. + ws q.im + g" + w q. 3 ~c iL mim Ri I M M g ig g igg 15 mrem (13) where:

The, releases of radionuclides, radioactive mater ials in particulate form, and radionuclides other 'than noble gases in gaseous effluents, i, for long-term releases greater than 500 hr/yr, in uCi. Releases shall be cumu-lative over the calendar quarter or year, as appropriate.

The releases of radionuclides, radioactive materials in particulate form, and radionuclides other than noble gases in gaseous effluents, i, for short-term releases equal to or less than 500 hr/yr, in pCi. Releases shall be cumulative over the calendar quarter or year as appropriate.

42

M m,wg The dispersion parameter for estimating the dose to an individual at the controlling location for long-term (o 500 hr.) releases (m is for mixed mode releases, g is for ground level releases).

M = .(Ã/9) for the inhalation pathway, in sec/m .

M = (0/g) for the food and ground plane pathways in meters-2.

wm,wg The dispersion parameter for estimating the dose to an individual at the controlling location for short-term (c500 hr.) releases (m is for mixed mode releases, g is for ground level releases) w = (X/q) for the inhalation pathway, in sec/m3.

w =-(OD~) for the food and ground plane pathways in meters-~.

3.17 x 10"8 = The inverse of the number of seconds in a year.

The dose factor for each identified radionuclide, i, in m~(mrem/yr) per vCi/sec or mrem/yr per pCi/m .

n = Total number of radionuclides (noble gases) in the effluent.

43

I 3.4.2.1 Dose Parameter for Radionuclide i (R 1))

The Ri values used in equations 12 and 13 of this section are calculated separately for each of the following potential exposure pathways:

I Inhalation Ground plane contamination Grass-cow/goat-milk pathway Grass-cow-meat pathway Vegetation pathway 8ased on GALE Code release projections, the infant age group is expected to be the most restrictive. However, monthly dose assessments for WNP-2 gaseous effluent will be done for all age groups.

Calculation of R.I (Inhalation Pathway Factor)

I (Inhalation)

/') R; = K1 {BR)a

{DFAi)a (mrem/yr per gCi/m )

3 (I4) where:

I R =- The inhalation pathway factor (mrem/yr per qCi/m3 ).

K> .

= A constant of unit conversion, 106 pCi/qCi.

The breathing rate of the receptor of age group (a) in meter3/yr. (Infant = 1400, child = 3,700, teen = 8,000, adult = 8,000. From P.32 NUREG-0133).

44

I I

(DFA ) The maximum organ inhalation dose factor for receptor of age group (a) for the ith radionuclide (mrem/pCi). The total body is considered as an organ in the selection of (DFAi) a. The (DFAi) a values for the infant age group were used. They are listed in Table E-10 'of Regula-tory Guide 1.109 manual. Values of RI are listed in Table 3-5.

G Calculation of R (Ground Plane Pathway Factor)

G R.(Ground Plane) = A B K K (SF)(DFG,.) (1-e i 2 x mrem/yr per pCi/sec)

)/A,. (m (15) 1 where:

G 2 R- = Ground plane pathway factor (m x mrem/yr per qCi/sec).

KA = A conversion constant of 106 pCi/pCi.

f' KB = A conversion constant - 8760 hr/yr.

The decay constant for the ith radionuclide (sec"1) ~

t = Exposure time, 4.73 x 10B sec (= 15 years).

DFG. The ground plane dose conversion factor for the ith radio-nuclide, as listed in Table E-6 of Regulatory Guide 1.109 (mrem/hr per pCi/m2).

SF = Shielding Factor (dimensionless) 0.7, as suggested in Table E-15 of Regulatory Guide 1.109.

45

, e I The values of R-G are listed in Table 3-5 of this manual.

C Calculation of R (Grass-Cow/Goat-Milk Pathway Factor)

C R,. (Grass-Cow/Goat-Milk Factor ) =

K OF(Ue )

+ F (r)(DFL.)

ff +

(1ff)e

-X-th i f s

(m~ x mrem/yr per qCi/sec) where:

K A constant of unit conversion, 10S pCi/pCi.

0F = The cow/goat consumption rate, in kg/day (wet weight).

r=)

Uap = The receptor's milk consumption rate for age (a) ~ in liters/yr.

"p = The agricultural productivity by unit area of pasture feed grass, in kg/m~.

The agricultural productivity by unit area of stored feed, in kg/m2.

The stable element transfer coefficients, in days/liter .

r = Fr action of deposited activity retained on feed grass.

46

(DFL') The maximum organ ingestion dose factor for the ith radio-nuclide for the receptor in age group (a), in mrem/pCi (Tables E-Il to f-14 of Regulatory Guide 1.109).

The decay constant for the ith radionuclide, in sec The decay constant for removal of activity on leaf and plant surfaces by weathering, 5.73 x 10-7 sec I (cor-responding to a 14-day half-life).

The transport time from pasture to animal, to milk, to receptor, in sec.

The transport time from pasture, to harvest, to animal, to milk, to receptor, in sec.

Fraction of the year that the cow/goat is on pasture (dimensionless) = 0.5 s = Fraction- of the cow/goat feed that is pasture grass while the cow is on pasture (dimensionless) = 1.0 The input parameters used for calculating R; are listed in Table 3-7 and the C

Ri values are tabulated in Table 3-6.

For Tritium:

In calculating RT, pertaining to tritium in milk, the airborne concentration rather than the deposition will be used:

C RT (Grass-Cow/Goat-Milk Factor) =

A C 3 K K F gFU (DFL.) 0.75(0.5/H) (mrem/yr per uCi/m ) (17)

\

0

where:

KA = A constant unit conversion, 106 pCi/pCi.

KC = A constant of unit conver-sion, 103 gm/kg.

= Absolute humidity of the atmosphere, H in gm/m3.

0.75 = The fraction of total feed that is water.

0.5 = The ratio of the specific activity of the feed grass water to the atmospheric water.

Calculation of R.M (Grass-Cow-Meat Pathway Factor)

M R. (Grass-Cow-Meat Factor) =

1 qF(ua ) Xitf e

K ~~'~ W FF(r)(OFL )

Yp "s (is)

(m~ x mrem/yr per pCi/sec) where:

K' A constant unit conversion, 106pCi/pCi.

f = The stable element transfer coefficients, in days/kg.

ap

= The receptor's meat consumption rate for age (a), in kg/yr.

The transport time from pasture to receptor, in sec.

The transport time from crop field to receptor, in sec.

The input parameters needed for solving equation 18 are listed in Table 3-7.

For Tritium:

In calculating the RT for tritium in meat, the airborne concentration is used rather than the deposition rate. The following equation is used to calculate the RT values for tritium:

M R (Grass-Cow-Meat Pathway) =

K K

[ F<0FU (OFL,.)

] [ 0.75(0.5/H)] (mrem/yr per e Ci/m ) (19)

Where the terms are as defined in equations 17-19,'R~ values for tritium r pertaining to the infant age group is zero since there is no meat consumption by this age group.

Calculation of R.V (Vegetation Pathway Factor)

R.V (Vegetation Pathway Factor) =

(jLfLe

-X it L + USfge

>>X ith (20)

(OFL,),

K v il 'Xw (m2 x mrem/yr per pCi/sec)

I where:

K' A constant of unit conversion, 106pCi/pCi.

L =

U The consumption rate of fresh leafy vegetation by the receptor in age group (a), in -kg/yr.

S =

U The consumption rate of stored vegetation by the receptor in age group (a), in kg/yr.

The fr action of the annual intake of fresh leafy vegetation grown locally.

The fraction of the annual intake of stored vegetation grown locally.

The average time between harvest of leafy vegetation and its consumption, in seconds.

~ ~

The average time between harvest of stored vegetation and its consumption, in seconds.

"v = The vegetation area density, in kg/m .

All other items are as defined in equations 16-18.

For Tritium:

In calculating the RTV for tritium, the concentration of tritium in vegetation is based on airborne concentration rather than the deposition rate. The fol-lowing equation is used to calculate RT for tritium:

50

)*A C IC.' 0~ ~ >>II hh 4 WH I 4 al~tyl A* lAA 'I S~ H s ff W 8 . ~ ~ W ~ ~, p '4 ~

V ~

RT (Vegetation Pathway Factor) =

AC K K L,S UafL + Uaf (DFLi) a 0.75(0.5/H)

~ ~ (mrem/yr Per vCi/m 3

) (21)

Where all terms have been defined above and in equations 16-18, the R. value1 for tritium is zero for the infant age group due to zero vegetation consump-tion rate by that age group. The input parameters needed for solving equations 20 and 21 are listed in Table 3-8.

3.5 Com liance with Standard Technical S ecification 3.11.2.4 Standard Technical Specifi cati on 3.11.2.4 states:

The GASEOUS RADWASTE TREATMENT SYSTEM shall be in opera-tion in either the normal or charcoal bypass mode. The charcoal bypass mode shall not be used unless the offgas post-treatment radiation monitor is OPERABLE as specified in Table 3.3.7.11-1."

"APPLICABILITY: Whenever the main condenser steam jet air ejector evacuation) system is in operation."

Prior to placing the Gaseous Radwaste Treatment System in the charcoal bypass mode, the alarm setpoints on the main plant vent release monitor shall be set to account for the increased percentages of short-lived noble gases. Noble gas percentages shall be based either on actual measured values or on primary coolant design base noble gas concentration percentages adjusted for 30-minute decay. Table 3-15 lists the percentage values, for 30-minute decay.

3.6 Calculation of Gaseous Effluent Monitor Alarm Set pints

3. 6.1 Intro ducti on The following procedure used to ensure that the dose rate in the unrestricted areas due to noble gases in the WNP-2 gaseous effluent do not exceed 500 51

(

mrem/yr to the whole body or 3000 mrem/yr to the skin. The initial setpoints

~ ~ ~

determination is calculated using a conservative radionuclide mix obtained

~

from the WNP-2 GALE code. Once the plant is operating, the actual radio-

~

nuclide mix is used to calculate the alarm setpoint.

~

~ ~

3.6.2 Set oint Determination for all Gaseous Release Paths The setpoints for gaseous effluent are based on an instantaneous noble gas dose rates. A monthly analysis of radioiodines and radionuclides in particu-late form will be performed to ensure compliance with 10 FR 20 and 10 CFR 50 Appendix I limits. The three release points will be partitioned such that their sm does not exceed 100 percent of the limit. Originally, the setpoints will be set at 40 percent for the reactor building, 40 percent for the turbine building and 20 per cent for the radwaste building. These per centages could vary at the plant discretion, should the operational conditions warrant such change. However, the combined releases due to variations in the setpoints will not result in doses which exceed the limit stated in technical specifica- .

tion. Both skin dose and whole body setpoints will be calculated and the lower 1 imi t will be used.

3.6.2.1 Set pints Calculations Based on Whole Bod Dose Limits The fraction ( <<i) of the total gaseous" radioactivity in each gaseous effluent release path (j) for each noble gas radionuclide i will be determined by using the foTlowing equation:

C ~ ~

lj (dimensi onl ess ) (22) where:

r C.. = The measured individual concentration of radionuclide i in the lj gaseous effluent release path j (pCi/cc).

The measured total concentration of all noble gases identified in the gaseous effluent release path j (pCi/cc).

I Based on Technical Specification 3.11.1.2, the maximum acceptable release rate of all noble gases in the gaseous effluent release path j is calculated by using the following equation:

F 500 (23) x/Qj g (Ki)( ij) where:

The maximum acceptable release rate (~Ci/sec) of all noble gases in the gaseous effluent release path j (uCi/cc).

Fj = Fraction of total dose allocated to release path j.

,rI 500 = Whole body dose rate limit of 500 mrem/yr as specified in Tech-nical Specification 3.11.2.1a.

X/Qj Maximum normalized diffusion coefficient of effluent release path j at the site boundary (sec/m3). Turbine Building and Radwaste Building values are based on average annual ground level values. Main plant vent release values are for mixed mode and may be either short term or average annual value dependent upon type of release.

The total whole body dose factor due to gamma emission from noble gas nuclide i (mrem/yr per pCi/m3) (as listed in Table B-1 of Regulatory Guide 1.109).

53

As defined in equation 22.

m = Total number of radionuclides in the gaseous effluent.

j = Different release pathways.

The total maximum acceptable concentration (CTj) of noble gas radionuclides in the gaseous effluent release path j (pCi/cc) will be calculated by using the following equation:

C Tj

= ~

gT ~

Rj (pCi/cc) ~

(24) where:

Tj = The total al 1 owed concentration of al 1 noble gas r adionucl ides in the gaseous effluent release path i (pCi/cc).

The maximum acceptable release rate (pCi/sec) of all noble gases in the gaseous effluent release path i.

The effluent release rate at the point of release.

To determine the maximum acceptable concentration (CiA) of noble gas radio-nuclide i in the gaseous effluent for each individual noble gas in the gaseous effluent (pCi/cc), the following equation will be used:

ij i jCTj (pCi/cc) (2S)

where:

~ij and CTg are as defined in equations 22 and 24 respectively, the gaseous effluent monitor alarm setpoint will then be calculated as follows:

C.R.j =

g ij lj C.jE..(cpm) (26) where:

C.R.j = Count rate above background (cpm) for gaseous release path j.

The maximum acceptable concentration of noble gas nuclide i in, the gaseous effluent release path j. gCi/cc.

Detection efficiency of the gaseous effluent monitor j for noble gas i (cpm/vCi/cc).

3.6.2.2 Set pints Calculations Based on Skin Dose Limits The method for calculating the setpoints to ensure compliance with the skin

~

dose limits specified in Technical Specification'.11.2.la is similar to the

~ one described for whole body dose limits (Section 3.6.2.1 of this manual),

except Eq. 27 will be used instead of Eq. 23 for determining maximum accept-able release rate (gTj)

Fj 3000 (X/q )

m (L.1 + i.l.V.)(

i ..)(" i/'")

lj (27) i = 1 55

(

where:

The maximum acceptable release rate of all noble gases in the gaseous effluent release path j in. Ci/sec.

X/gj = The maximum annual normalized diffusion coefficient for release path j at the site boundary (sec/m3).

Fraction of total allowed dose.

The skin dose factor due to beta emission for each identified noble gas radionuclide i in mrem/yr per pCi/m3 (from Table B-l of Regulatory Guide 1.109).

The air dose factor due to gamma emmissions for each identified noble gas radionuclide, in mrad/yr 'per pCi/m3 (M; values are listed in Table 3-1).

1.1 = A conversion factor to convert dose in mrad to dose equivalent in mrem".

3000 = Skin dose rate limit of 3000 mrem/yr as specified in Technical Speci fication 3.11.2.1.

56

Table 3-1 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS*

Total Body Gamma Air Beta Air Dose Factor Skin Dose Factor Dose Factor Dose Factor Radi onuc 1 i de Ki L. H. N ~

(mrem/yr per pCi/m3) (mrem/yr per pCi/m3) (mrad/yr per pCi/m3) (mrad/yr per pCi/m3)

Kr-85m ]7Ey03** 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72E+Ol 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37&03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 . 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+Ol 4.76E+02 1.56E+02 1.11E<03 Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E403 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1. 51E+03 1.27E+04 Xe-138 8.836 03 4.13E+03 1

9.21E~03 4.75E+03 Ar-41 8.84E+03 2. 69E+03 9.30E+03 3.28E+03 "The listed dose factors are for radionuclides that may be detected in gaseous effluents.

• • 7.56E-02 = 7.56 x 10-2.

I The values listed above were taken from Table B-l of NRC Regulatory Guide 1.109. The values were multiplied by 10 to convert picocuries to microcuries

r>> ~ > >. >,v l', ',>> ", A>>> ' '>> e. >> '~ '>' ~>>>' R,>so> q> '> >a>>r A>gw >>4twpe>>t >>>A'> ~ a~' >h J "8 '>> l '4u ~,l >, A ' > e>> . ~ >

Table 3-2 DISTANCES (MILES) TO CONTROLLING LOCATIONS AS MEASURED FROM CENTER OF WNP-2 CONTAINMENT BUILDING*

Location Comments Site Boundary 1.2 SE Air dose measurement.

Taylor Flats 4.2 SE The nearest significant residence in the southern direction with vegetable gardens, milk, and meat production.

Ringold 4.0 ENE The nearest significant residence in the northern direction with vegetable gardens, milk, and meat production.

• Selection of location sector is based on the highest annual average

-X/Q values.

58

Tab.le 3-3 WNP'-2 ANNUAL AVERAGE DISPERSION (X/Q)

AND DEPOSITION D/ VALUES FOR SPECIAL LOCATIONS X/Q X/Q X/Q 2.3 Days 8.0 Days No Decay Decay Decay Location Sector Distance .Point of Release No De letion No De letion ~oe 1eted (miles) (sec/m3) (sec/m3) (sec/m3) (m-2)

Site Boundary SE - 1.2 Containment Bldg. 1.8E-06 1.8E-06 1.6E-06 1.0E-08 Turbine Bldg. 1.1E-05 1.1E-05 1.0E-05 8.3E-08 Radwaste Bldg. 1.1E-05 1.1E-05 1.0E-05 8.3E-OB Taylor Flats SE 4.2 Containment Bldg. 4.1E-07 4.1E-07 3. 8E-07 8. 2E-10 Turbine Bldg. 8.9E-07 8.7E-07 6.8E-07 7.2E-10 Radwaste Bldg. 8.9E-07 8.7E-07 6.8E-07 7.2E-10 Ringold ENE 4.0 Containment Bldg. 2.5E-07 2.5E-07 1.9E-07 3.3E-10 Turbine Bldg. i 3.9E-07 3.8E-07 3.0E-07 3.3E-10 Radwaste Bldg. 3.9E-07 3.8E-07 3.0E-07 3.3E-10 BPA Ashe 0.5 Containment Bldg. 6.4E-06 6.4E-06 5.8E-06 3.7E-08 Substation Turbine Bldg. 3.0E-05 2.9E-05 2.7E-05 7.8E-08 Radwaste Bldg. 3.0E-05 2.9E-05 2.7E-05 7.8E-08

Table 3-4 DOSE RATE PARAMETERS IMPLEMENTATION OF 10 CFR 20 AIRBORNE RELEASES Child Dose Factor* PI 1 Inhalation mrem/hr mrem/ r

-1 Nuclide sec ~mrem/ Ci ~Ci /m v Ci/m H-3 1.8E-09 3.0E-07 0.0 1.1E+03 I-131 1.0E-06 4.4E-03 3.4E-09 1.6E+07 I-133 9.2E-06 1.0E-03 4.5E-09 3.7E+06 Cr-51 2.9E-07 4.6E-06 2.6E-10 1.7E+04 Mn-54 2.6E-08 4. 3E-04 6.8E-09 1.6E+06 Fe-55 8.5E-09 3.0E-05 0.0 1.1E+05 Fe-59 1.8E-07 3.4E-04 9.4E-09 1.3E+06 Co-58 1.1E-07 3.0E-04 8.2E-09 1.3E+06 Co-60 4.2E-09 1.9E-03 2.0E-OB 7.0E+06 Zn-65 3.3E-08 2.7E-04 4.6E-09 1.0E+06 Sr-89 1.5E-07 5.8E-04 6..5E-13 2.2E+06 Sr-90 7.9E-10 2.7E-02 ~ 1.0E+08 Zr-95 1.2E-07 6.3E-04 5.8E-09 2.3E+06 Cs-134 1.1E-08 2.7E-04 1.4E-08 1.0E+06 Cs-137 7.3E-010 2.5E-04 4.9E-09 9.3E+05 Ba-140 6.3E-07 4.7E-04 2.4E-09 1.7E+06

+Maximum Organ 60

Table 3-5a DOSE RATE PARAMETERS IMPLEMENTATION OF 10 CFR 50 AIRBORNE RELEASES Age Group: Infant Dose Parameters Maximum Or an

. Inhalation Ground Milk Cow Milk Goat RI RG RC R 1 i Nuclide sec mrem/ r m x mrem/ r m x mrem/ r m x mrem/ r (per (pCi/m ) (per (pCi/sec) (per (qCi/sec) (per (qCi/sec)

H-3 1. 8E-9 6.5E+2 0.0 3.4E+3 7.0E+3 I-131 1.0E-6 1.5E+7 1.0E+7 2.4E+11 4.3E+11 I-133 9.2E-6 3.6E+6 1. 5E+6 2.2E+9 4.0E+9 Cr-51 2.9E-7 1.3E+4 5.5E+6 2.0E+6 3.5E+5 Fe-55 8.5E-9 8.7E+4 0.0 7.0E+7 7.1E+6 Fe-59 1.8E-7 1.0E+6 3.2E+8 1.7E+8 3.2E+7 Mn-54 2.6E-8 9.9E+5 1.6E+9 2.0E+7 2.9E+6 Co-58 1.1E-7 7.BE+5 4.4E+8 2.8E+7 4.5E+6 Co-60 4.2E-9 4.5E+6 2. 5E+10 1.1E+8 1.4E+7 Sr-89 1.5E-7 . 2.0E+6 . 2.5E+4 5.6E+9 1.6E+10 Sr-90 7.9E-10 4.1E+7 0.0 7.1E+10 1.7E+11 Cs-134 1.1E-8 7.0E+5 8.0E+9 3.6E+10 1.3E+11 Cs-136 5.9E-7 5.6E+4 1.7E+8 2.6E+9 1.2E+10 Cs-137 7. 3E-10 6.1E+5 1.2E+10 3.4E+10 1.2E+11 Ba-140 6.3E-7 1.6E+6 2.3E+7 1.1E+8 1.9E+7

(-%

I

Table 3-5b DOSE RATE PARAMETERS--IMPLEMENTATION OF 10 CFR 50 AIRBORNE RELEASES Age Group: Child Nuclide I-131 sec

1. BE-9 1.0E-6

~/

Inhalation RI i

(per (pCi/m 1.1E+3 1.6E+7

)

~ ~/

m Ground R

x mrem/ r (per (pCi/sec) 0.0 1.0E+7 Dose Parameters Milk 2

RC 1

Cow (per (pCi/sec) 2.3E+3 9.9E+10 Maximum Or an m

Milk Goat RC x mrem/

(per (pCi/sec) 4.6E+3 1.8E+ll r m Vegetables 2

R'.

1 x mrem/

(per (pCi/sec) 5.6E+3 1.1E+10 r m Neat RN 1

x mrem/ r (per (pCi/sec) 3.4E+2 1.3E+9 I-133 9.2E-6 3.8E+6 1. 5E+6 9.2E+8 1. 7E+9 1. 7E+8 3.DE+1 Cr-51 2.9E-7 1. 7E+4 5.5E+6 2.3E+6 4.1E+5 5.3E+6 2.0E+5 Fe-55 8.5E-9 1.1E+5 0.0 5.BE+7 9.1E+6 3.9E+8 2.4E+8 Fe-59 1.8E-7 1.3E+6 3.2E+8 9.0E+7 1.6E+7 6.DE+8 2.BE+8 Mn-54 2.6E-8 1. 6E+6 1. 6E+9 1.1E+7 1. 6E+6 6.3E+8 4.1E+6 Co-58 1.1E-7 1.1E+6 4.4E+8 3.2E+7 5.2E+6 3.4E+8 4.4E+7 Co-60 4.2E-9 7.1E+6 2.5E+10 1.3E+8 1.BE+7 2.0E+9 2.1E+8 Sr-89 1. 5E-7 2.2E+6 2.5E+4 3.0E+9 8.6E+9 3. 3E+10 2.2E+8 Sr-90 7.9E-10 1.0E+8 0.0 6.5E+10 1.6E+11 1.3E+12 6.1E+9 Cs-134 1.1E-B 1.0E+6 8.DE+9 2.0E+10 7.0E+10 2.5E+10 7.9E+8 Cs-136 5.9E-7 1. 7E+5 1. 7E+8 1.2E+9 5.6E+9 1.5E+8 2.0E+7 Cs-137 7.3E-10 9.1E+5 1.2E+10 1.BE+10 6.4E+10 2.4E+10 7.5E+8 Ba-140 6.3E-7 1. 7E+6 2.3E+7 5.2E+7 9.4E+6 1.BE+8 2.0E+7

(

Table 3-5c DOSE RATE PARAMETERS IMPLEMENTATION OF 10 CFR 50, AIRBORNE RELEASES Age Group: Teen Dose Parameters Maximum Or an Inhalation Ground Milk Cow Milk Goat Vegetables Meat RI R RC RC R". R'.

1 1 1 1 1 Nuclide sec mrem/ r m x mrem/ r m x mrem/ r m x mrem/ r m x mrem/ r m 2

x mrem/ r (per (pCi/m ) (per (vCi/sec) (per, (pCi/sec) (per (pCi/sec) (per (pCi/sec) (per (pCi/sec)

H-3 1.8E-9 1.3E+3 1.4E+3 2.9E+3 3.5E+3 2.BE+2 I-131 1.0E-6 1. 5E+7 1.DE+7 5.1E+10 9.1E+10 7.DE+9 8.4E+8 I-133 9.2E-6 2.9E+6 1.5E+4 3.9E+8 7.DE+8 9.4E+7 1.7E+1 Cr-51 2.9E-7 2.1E+4 5.5E+4 3.6E+6 6.4E+5 8.5E+6 4.1E+5 Fe-55 8.5E-9 1.2E+5 1.6E+7 3.6E+6 3.0E+8 8.BE+7 Fe-59 1.8E-7 1.5E+6 3.2E+8 1.3E+8 2.3E+7 8.7E+8 5.2E+8 Mn-54 2. 6E-8 2. OE+6 1. 6E+9 1.5E+7 2.2E+6 8.7E+8 7.4E+6 Co-58 1.1E-7 1.3E+6 4.4E+8 5.DE+7 8.1E+6 5.4<+8 8.9E+7 Co-60 4.2E-9 8.7E+6 2. 5E+10 2.0E+8 2. BE+7 3. 1E+9 4.1E+8 Sr-89 1.5E-7 2.4E+6 2.5E+4 1.2E+9 3.5E+9 1.3E+10 1.1E+8 Sr-90 7.9E-10 1.1E+8 3.BE+10 9.4E+10 7.9E+11 4.7E+9 Cs-134 1.1E-B 5.5E+5 8.DE+9 1.2E+10 4.4E+10 1.5E+10 6.5E+8 Cs-136 5.9E-7 1.9E+5 1.7E+8 7.9E+8 3.5E+9 1.0E+10 1. 6E+7 Cs-137 7.3E-10 8.5E+5 1.2E+10 1.0E+10 3.5E+10 1.3E+10 5.4E+8 Ba-140 . 6.3E-7 2.0E+6 2.3E+7 3.3E+7 6.0E+6 1.2E+8 1. 6E+7

Table 3-5d r

DOSE RATE PARAMETERS IMPLEMENTATION OF 10 CFR 50 AIRBORNE RELEASES Age Group: Adult Dose Parameters Maximum Or an Inhalation Ground Milk Cow Milk Goat egetables Meat R RC RC R'. R".

1 1 1 1 1 R'rem/ 2 2 Nuclide sec r m x mrem/ r m x mrem/ r m x mrem/ m 2

x mrem/ r m x mrem/ r (per (pCi/m ) (per (pCi/sec) (per (pCi/sec) (per (pCi/sec) (per (pCi/sec) (per (pCi/sec)

H-3 1. BE-9 1.3E+3 1.1[+3 2.2E+3 3.0E+3 4.7E+2 I-131 1.0E-6 1.2E+7 1.0E+7 5.7E+10 8.2E+9 1.2f+9 3.2E+10'.3E+8 I-133 9.2E-6 2.2E+6 1. 5E+6 4.1E+8 1.1E+8 2.2E+1 Cr-51 2.9E-7 1.4E+4 5.5E+6 3.1E+6 5.5E+5 8.7E+6 7.7E+5 Fe-55 8.5E-9 7.2E+4 l. 3E+7, 2.0E+6 1.BE+8 1.5E+8 Fe-59 1.8E-7 1.0E+6 3.2E+8 1.0E+8 1. 9E+7 8.0E+8 9.2E+8 Mn-54 2.6E-B 1.4E+6 1.6E+9 l.'3E+7 1.9E+6 8.5E+8 1.4E+7 Co-58 1.1E-7 9.3E+5 4.4E+8 4.4E+7 7.1E+6 5.3E+8 1.7E+8 Co-60 4.2E-9 6.0E+6 2. 5E+10 1.7E+8 2.4E+7 2.9E+9 7.6E+8 Sr-89 1.5E-7 1.4E+6 2.5E+4 6.5E+8 1.9E+9 8.2E+9 1.3E+8 Sr-90 7.9E-10 9.9E+7 2.7E+10 6. 7E+10 6.2E+11 7.2E+9 Cs-134 1.1E-8 8.5E+5 8.0E+9 7.0E+9 2.5E+10 9.9E+9 8.2E+8 Cs-136 5.9E-7 1.5E+5 1. 7E+8 4.6E+8 2.1E+9 9.0E+7 2.1E+7 Cs-137 7. 3E-10 6.2E+5 1. 2E+10 5.6E+9 1.5E+10 8.3E+9 6.7E+8 Ba-140 6.3E-7 1.3B6 2.3E+7 2.5E+7 4.4E+6 1.4E+8 2.6E+7

Table 3-6 INPUT PARAMETERS FOR CALCULATING R.

P arameter Value Table*

r (dimensionless) 1.0 for radioiodine E-15 0.2 for particulates E-15 Fm (days/liter) Each stable element E-1 Uap ( liters/yr) Infant 330 E-5 Child 330 E-5 Teen 400 E-5

--Adult 310 (DFLi)a (mrem/pCi) Each radionuclide E-11 to E-14 "p (kg/m ) 0.7 s (kg/m 2.0 E-15 tf (seconds) 1.73 x 10 (2 days) E-15 th (seconds) 7.78 x 10 (90 days) E-15

~F (kg/day) 50 E-3 fs (dimensionless) 1.0 NUREG-0133 fp (dimensionless) 0.5 for cow Site specific 0.75 for goat Site specific

• Of Regulatory Guide 1.109 unless stated otherwise.

65

Table 3-7 INPUT PARAMETERS FOR CALCULATING R.

Parameter Value Table*

r (dimensionless) 1.0 for radioiodine E-15 0.2 for particulates E-15 Ff (days/kg) Each stable element E-1 Uap (kg/yr) Infant 0 E-5 Child 41 E-5 Teen 65 E-5 Adult 110 E-5 (DFL.) (mrem/pCi) Each radionuclide E-ll to E-14 "p (kg/m ) 0.7 E-15 "s (kg/ ) 2.0 E-15 tf (seconds) 1.73 x 10 (20 days) E-15 th (seconds) 7.78 x 106 (90 days) E-15

~F (kg/day) 50 E-3

• Of Regulatory Guide 1.109.

66

0 Table 3-8 INPUT PARAMETERS FOR CALCULATING R.

Par ameter Value Table*

r (dimensionl ess) 1.0 for radioiodine E-1 0.2 for particulates E-1 (DFLi) a (mrem/pC1) Each radionuclide E-11 to E-14 U

L (kg/yr) Infant 0 Child 26 E-5 Teen 42. E-5 Adult 64 E-5 U

S (kg/yr) Infant 0 E-5 Child 520 E-5 Teen 630 E-5 Adul t 520 E-5 fL (dimensionless) Site specific (default = 1.0) E-5 fg (dimensionless) Site specific (default = 0.76) RG 1.109, p 28 t'L (seconds) 8.6 x 104 (1 day) E-15 th (seconds) 5.18 x 106 (60 days) E-15 y (kg/m 2.0 E-15

• Of Regulatory Guide 1.109.

67

Table 3-9 INPUT PARAMETERS NEEDED FOR CALCULATING DOSE TO THE MAXIMUM INDIVIDUAL FROM WNP-2 GASEOUS EFFLUENT In ut Parameter Value Reference Distance to Maine (miles) 3000 Ref 1 Fraction of year leafy vegetables are grown 0.42 May 15-Oct 15 Fraction of year cows are on pasture 0.5 Ref 2 Fraction of crop from garden 0.76 Ref 3 Fraction of daily intake of cows derived from pasture while on pasture 1.0 Ref 3 Annual average relative humidity (X) 53.8 Ref 4 Annual average temperature (Fo) 53.0 Ref 5 Fraction of year goats are on pasture 0.75 Site Specific Fraction of daily intake of goats derived from pasture while on pasture 1.0 Ref 2 Fraction of year beef cattle are on pasture 0.5 Ref 2 Fraction of daily intake of beef cattle derived from pasture while on pasture 1.0 Ref 2 Populytion within 50 miles of plant and the year that the population is used 336,115 (year 2000) Ref 6 Annual 50-mile milk production

( 1 i ters/yr) 9.91E+06 Refs 7 & 9 Annual 50-mile meat production (kg/yr) 3.54E+06 Refs6, 7,59 Annual 50-mile vegetable production (kg/yr) 2.0E+07 Refs6, 7,59 Source terms GALE-Gaseous 8 Ref 8 68

Table 3-9 (contd.)

In ut Parameter Value Reference X/q values by sector for each dis-tance (recirculation, no decay) See Tables 3-11 (sec/m3) through 3'-12 Ref 10 X/g values by sector for each dis-

'tance (recirculation, 2.26 days See Tables 3-11 decay, undepleted) (sec/m3) through 3-12 Ref 10 X/g values by sector for each dis-tance (recirculation, 8,0 days See Table 3-11 decay, depleted) (sec/m3) through 3-12 Ref 10 D/9 values by sector for each dis- See Table 3-11 tance (1/m2) through 3-12 Ref 10 Number of special locations* Ref ll

• Refer to Tables 3-3 and 3-4 for location name, distance from

'/g and D/Q values.

WNP-2, and 69

Table 3-10 nEACTOR GUILDltlG STAN X AtlD 0 VALUES>>

e) ~lie Oeee ~dede leted Cttl/Q (sec/meter cubed) for each segment Direction Frtee Site Se ment Boundaries in Ht les from the Site S 1.103E-06 3.229E-07 1.153E-07 6.291E-OS 4.151E-OS 2.056E-OG 6.109E-OG 4.956E-OS 3.370E-O& 2.530E-OB SSM 8.&24E-07 2.569E-07 9.106E-OS 4.941E-OG 3.243E-OB 1.607E-OG. 5.267E-OG 4.304E-OB 2.930E-OG- 2. 201E-08 SM 7.484E-07 2.220E-07 8.257E-OB 4.646E-OS 3.09&E-OG 4.101E-OG 6.486E-OS 4.274E-OG 2.917E-OS 2.195E;0&;

MSM 5.687E-07 1. 717E-07 6.362E-OS 3.543E-OB 2.341E-OS 2,682E-OG 4.367E-OB 2.851E-OB 1.940E-OS 1.457E'-08 M 2.201E-07 7.362E-OS 2.829E-M 1.604E-OG 1.065E-OG 5;201E-09 2.9&6E-OB 2.489E-OB 1.695E-OG 1.274E-'08 WtlM 3.037E-07 1.024E-07 3.926E-OB 2.208E-OG 1.459E-OG 7.601E-09 2.6&DE-OB 2.168E-OS 1.471E-OG E-OB '.104 ttM 9.434E-07 2.769E-07 9 '67E-08 5.427E-OG 3.563E-OG 1.789E-OS 3.036E-OB 2.344E-OQ 1.582E-OS 1.)83E-OG llllM 3. 010E-06 8.542E-07 3.077E-07 1.684E-07 1.121E-07 5.49&E-OS 5.529E-OG 4.004E-OG 2.706E-OB 2.023E-OG tl 3.675E-06 1.034E-06 3.712E-07 2.037E-07 1.343E-07 1.060E-07 8.208E-OG 4.4&4E-OS 3.033E-OS 2.269E-OB li&E'lE 2.430E-06 6.639E-07 2.313E-07 1.237E-07 8.113E-OG 9.852E-OG 5.491E-OS 2.952E-OG 1 '&OE-08 1.473E-OQ 1.30&E-06 3.571E-07 1.242E-07 6.79&E-OQ 7.999E-OG 9. 512E-08 4.486E-OB 2.428E-OB 1.634E-OB 1.219E-OS EtlE 1.086E-06 3.381E-07 2.229E-07 2.754E-07 2.056E-07 9.895E-OG 4.020E-OB 2. 168E-OS 1.455E-OB '1.082E-OB E 1.21& E-06 3.665E-07 2.195E-07 2.582E-07 1.926E-07 9.269E-OG 3.768E-OG 2.036E-OS 1.369E-OB 1.020E-OS ESE 2.409E-06 7.211E-07 4. 124 E-07 4.440E-07 3.242E-07 1.423E-07 5.594E-OG 3.335E-OS 2.231E-OB 1.656E-O&

SE 3.043E-06 8.555E-07 3.10&E-07 2.844E-07 3.417E-07 1.677E 8.760E-OS 5.311E-OQ 3.586E-OS 2.6&OE-OQ SSE 1.842E-06 5.373E-07 1.943E-07 1.064E-07 7.011E-OB 3.471E-OB 7.245E-OQ 5.737E-OG 3,891E-OS 2. 917E-08

• Desert Sigmas, Suilding wake effect. All stability classes A through G.

Tahle 3-10 (contd.)

h) 2.26-oa IIeca Urule leled CIII/I) (sec/meter cubed) for each segment Direct Ion From Site Se ment Boundaries ln Illles from the Site S 1. 101E-06 3.218E-07 1.146E-07 6.23&E-OS 4.106E-OO 2.202E-OS 5.876E-OG 4.683E-OO 3.113E-OB 2.285E-OQ SSW 8. 810E-07 2.561E-07 9.054E-OG n.'goof-o& 3.20GE-OG 1.580E-OB 5.064E-OG 4.064E-OG 2.704E-OQ 1.985E-OG SM 7.471E-07 2. 212E-07 8.20GE-OG 4.608E-OQ 3.065E-OQ 4.023E-OG. 6.259E-OS 4.036E-OG 2.692E-OG 1.980E-OG MSM 5.67&E-07 1.711E-07 6.326E-OG 3. 515E-08 2.317E-OG 2.827E-OQ 4.213E-OS 2.691E-OG 1.789E-OS 1.313E-OB W 2.197E-07 7.334E-OG 2.810E-OQ 1.589E-O& 1.053E-OG 5.107f-09 2.859E-OQ 2.338E-OB 1.553E-OG 1.138E-OO MIIM 3.031E-07 1.020E-07 3.899f-oG 2.187E-OG 1.442E-OO 7.652E-09 2.570E-OG 2.039E-OG 1.350E-OG 9.877E-09 IIM 9.419E-07 2.760E-07 9.911E-OG 5.383E-OQ 3.527E-OQ 1.760E-OS 2.929E-OB 2.223E-OS = 1.469E-OG 1.074E-OB IIIIW 3.006E-06 8.520E-07 3.063E-07 1.673E-07 1.111E-07 5.422E-OG 5.369E-OG 3.830E-OG 2.542E-OB 1.867E-OB II 3.671E-06 1.031E-06 3.696E-07 2.024E-07 1.332E-07 1.044f-07 7 '96E-OG -4.291E-OQ 2.852E-OG 2.096E-OG tltlf 2.427E-06 6.624E-07 2.303E-07 1.230E-07 8.050E-OG 9.700E-OG 5.336E-OG 1.850E-OG 1.350E-OG tif 1.307E-06 3.562E-07 1.236E-07 6.753E-OO 7.927E-OQ 9.359E-OG 4.343E-OG 2.812E<<OG'.300E-OB 1.514E-OG 1.104E-OG EllE 1.0&5E-06 3.371E-07 2.217E-07 2.733E-07 2.036E-07 9.737E-OG 3.890E-OG 2.051E-OB 1.346E-OG 9.792E-09 E 1.216E-06 3.655E-07 2.185E-07 2.563E-07 1.907E-07 9.125E-O& 3.649E-OB 1.92&E-OG 1.268E-OG 9.243E-09 ESE 2.no6E-06 7.193E-07 4.104 E-07 n.'no&E-o7 3. 212E-07 1.403E-07 5.420E-OG 3. 164 E-08 2.072E-OQ 1.506E-OQ SE 3.039E-06 8.532E-07 3.093E-07 2.825E-07 3.389E-07 1.655E-07 8.49&E-OG 5.050E-OG 3.341E-OG 2.446E-OG SSE 1.839E-06 5.356E-07 1.932E-07 1.055E-07 6.939E-OG 3.414 E-OG- 6.983E-OQ 5.436E-OG 3.60&E-OG 2 '46E-08

Table 3-10 (contd.)

c) B.O-Da Deca De leted C&l/O (sec/meter cubed) for each segment Direction From Site Se ment Boundaries in Hiles from the Site'

.5- -2 -4 -20 3 -4 4-S l. 006E-06 2.858E-07 9.773E-O& 5.164E-OB 3.323E-OB 1.572E-OB 5.545E-OB 4.289E-OB 2.735E-OB 1.946E-OB

. SSW 8.039E-07 2.269E-07 7.694E-OB 4.035E-OB 2.578E-OB 1.221E-OB 4.794E-OB 3.733E-OB 2.383E-OB 1.697E-OB SW 6.775E-07 1.942E-07 6.924E-O& 3,784E-OB 2.462E-OB 3.644E-OB 5.757E-OB '.520E-OB 2.246E-OB 1.597E-OB WSW 5.169E-07 1.515E-07 5.39&E-O& 2.923E-OB 1.886E-OB 2.562E-O& 3.875E-OB 2.347E-OB 1.493E-OB 1.06OE-OB W 2.038E-07 6.726E-OB 2. 521E-OB 1.407E-OB 9.223E-09 '.395E-09 2.772E-OB 2.189E-OB 1.399E-OB 9.964E-09 WNW 2. 813E-07 9.369E-OB 3.505E-O& 1.93&E-OB 1.263E-OB 6.663E-09 2.393E-OB 1.82&E-O& . 1.161E-OB 8.239E-09 tlW 8.584E-07 2.450E-07 8.465E-OB 4.468E-OB 2.865E-OB 1. 391E-08 2.6&BE-OB 1.9&7E-OB 1.257E-OB 8.893E-09 NNW 2. 714 E-06 7.416E-07 2.547E-07 1.345E 8.724E-OB 4.071E-OB 4.583E-OB 3.202E-OB 2. 021E-08 1.427E-OB N 3.312E-06 8.954E-07 3.060E-07 1.619E-07 1.037E-07 8.674E-OB 6.796E-OB 3.375E-OB 2.123E-OB 1.495E-OB NNE 2.196E-06 5.789E-07 1.924E-07 9.939E-OB 6.36OE-OB 8.587E-OB 4.544E-OB 2.222E-OB 1.387E-OB 9. 713E-09 NE 1;186E-06 3.134E-07 1.045E-07 5.570E-OB 7.0&OE-O& 8.611E-OB 3:736E-08 1.841E-OB 1. 153E-08 8.096E-09 ENE 9.883E-07 3.011E-07 1.866E-07 2.147E-07 1.554E-07 7.012E-OB 2.504E-OB 1.187E-OB 7.20BE-09 4.925E-09 E 1.107 E-06 3.252E-07 1.832E-07 2.013E-07 1.456E-07 6.569E-O& 2.347E-O& 1. 115E-08 6.784E-09 4.643E-09 ESE 2.182E-06 6.364E-07 3.437E-07 3.464E-07 2.451E-07 1.014 E-07 3.460E-OB 1.827E-O& 1.107E-OB 7 '48E-09 SE 2.747E-06 7.450E-07 2.593E-07 2.509E-07 3.134 E-07 1.463E-07 6.976E-OB 3.884E-OB 2.434E-OB 1.709E-OB SSE 1.671E-06 4.722E-07 1.634E-07 8.657E-OB 5.559E-OB 2.633E-OB 5.975E-OB 4.484E-OB 2.835E-OB 2.003E-OB

." Table 3-10 (contd.)

d) Reactor Bniidin Stac'k Relative Dc osition Rate D Per Unit Area meter Direction From Site Se ment Boundaries in tliies from the Site S 7.256E-09 1.756E-09 5.194E-10 2.494E-10 1.466E-10 5.865E-11 3.375E-11 1.798f-ll 9.603E-12 5.944 E-12 SSW 5.752E-09 1.380E-09 4.082E-10 1. 959E-10 1.150f-10 4.626E-ll 2.608E-11. 1.395f-ll 7.448E-12 4.610E-12 SW 3.176E-O9 7.513E-10 2.191E-10 1.035E-10 6.028E-11 3.817E-11 2.414f-ll 9.646E-12 5.151E-12 3.188E-12 WSW 2.757E-09 6.889E-10 2.061E-10 9.796f-ll 5.718E-11 3.358E-11 1.980E-ll 7.927E-12 4.233E-12 2.620E-12 it 1.601E-09 4.334E-10 1.358E-10 6.565E-11 3.861f-ll 1.524f-ll 1.094E-ll 6.220f-lz 3.321E-12 2.056E-12 WllW 2.215E-09 5.797E-10 1.816E-10 8.829E-11 5.204f-ll 2.856E-11 1.697E-ll 7.175E-12 3.031E-12 2.372E-12 tiW 4.901E-09 1. 218E-09 3.728E-10 1.813E-10 1.068E-10 4.328E-ll 2.419E-11 1.286E-ll 6.869E-12 4.252E-12 ttNW 1.235E-OB 2.845E-09 8.19QE-10 3.873E-10 2.303E-10 9.105E-11 4.558E-ll 2.363E-ll 1.262f-ll. 7.811E-12 tt 1. 914 E-08 4.304E-09 1.213E-09 5.660E-10 3.273E-10 1.707f-lO 7.090f-ll 2.810E-11 1.501f-ll 9.288E-12 NIE 2.034E-08 4.577E-09 1.284E-09 5.961E-10 3.471E-10 1.810E-10 6.3I4E-11 2.526E-'ll 1.349E-ll 8.350E-12

'tE 1.338E-08 2.986E-09 8. 341E-10 3.918E-10 2.819E-10 1.483E-10 4.323E-11 1.713E-11 9. 150E-.12 5.663E-12 EtlE 9.298E-09 2.169E-09 7,730E-10 4.579E-10 2.604 E-10 1.001E-10 2.897E-11 1.148E-ll 6.132E-12 3.795E-12 E 1.017E-OB 2.355E-09 8.239E-10 4.749E-10 2.699E-10 1.038E-10 3.003 f-l 1 1.190E-ll 6.355E-12 3.934E-12 ESE 1.832E-OB 4. 190E-09 1.440E-09 8.177E-10 4.647E-10 1.780E-10 5.'136E-11 2.049E-ll 1.094E-11 6.773E-12 SE 2.006E-08 4.525E-09 1.262E-09 7.531E-10 6.421E-10 2.467E-10 7.197E-11 2.872E-11 1.534E-11 9.492E-12 SSE 9. 321E-09 2.265E-09 6.764E-09 3.250E-10 1.905E-10 7.633E-ll 4.186E-ll 2.224E-ll 1.187f-ll 7.350E-12

(

Table 3-11 TUltOt tie QUILDlttO X AtlO D VALUES+

a) ~lee Ileca aeeepleeed Cltt/ti (sec/meter cubed) for each segment Direction From Site Se ment Boundaries in Wiles from the Site

-2 -4 4- -0 5 1.791E-05 5.032E-06 1.836E-06 1.019E-06 6.765E-07 3.337E-07 1.405E-07 7.800E-OS 5.333E-OB 4.018E-OQ SSW 1.513E-05 4.282E-06 1.56GE-06 8.729E-07 5.803E-07 2.781E-07 1. 214 E-07 6.75GE-OB 4.627E-OG 3.489E-OS Sit 1. 419E-05 4.080E-06 1.513E-06 8.46GE-07 5.651E-07 2.811E-07 1.19SE-07 6.690E-OB 4.584E-OS 3 '57E-08 WSW 1.004 E-05 2.847E-OG 1.044E-06 5.811E-07 3.862E-07 1.909E-07 8.059E-OB 4.481E-OB 3.066E-OB 2.311E-OB W S. 834 E-06 2. 512E-06 9.240E-07 5. 149E-07 3.426E-07 1.695E-07 7. 171E-08 3.9BGE-OS 2.728E-OB 2.056E-OS WlN 8.324E-06 2.320E-O6 8.416E-07 4.654E-07 3.080E-07 1.511E-07 6. 317E-08 3.489E-OQ 2.380E-OS 1.791E-OS lPit 9.578E-06 2.620E-06 9.367E-07 5. 135E-07 3.377E-07 1.639E-07 6.739E-OG 3.6Q7E-OB 2.506E-OG 1.881E-OS tltN 1.520E-OS 4. 196E-06 1.494E-06 8. 198E-07 5.393f-07 2.620E-07 1.07GE-07 5.905E-OR 4.107E-OS 3.015E-OG B 1.661E-OS 4.558E-06 1.636E-06 8.9Q7E-07 6 '18E-07 2.QQ1E-07 1.189E-07 6 ~ 518 E-OB 4.435E-O& 3.329E-OG tlHE 1.259E-OS 3.378E-06 1.189E-06 6.456E-07 4.217E-07 2.025E-07 8.191E-DQ 4.445E-OB 3.015E-OB 2.260E-OO BE 1.019E-05 2.764E-06 9.837E-07 5.377E-07 3.528E-07 1.707E-07 6.978E-OB 3.804E-OS 2.581E-OS 1.935E-OB EtlE 9.32QE-06 2.52GE-06 8.9Q9E-07 4.907E-07 3. 215E-07 1.550E-07 6.302E-OS 3.426E-OS 2.322E-OQ 1.739f-08 E 8.659E-OG 2.344E-06 8.336E-07 4.553E-07 2.9B5E-07 1.441E-07 5.868E-OB 3.191E-OG .2.162E-OG 1.619E-OB ESE 1.452E-05 3. 919E-06 1.391E-OG 7.573E-07 4.950E-07 2.375E-07 9.577E-OO 5.173E-OB 3.494E-OG 2.611E-OG SE 2.052E-05 5.657E-OG 2.038E-06 1.121E-06 7 '07E-07 3.595E-07 1.482E-07 8. 123E-OG 5. 519E-08 4.141E-OB SSE 2.128E-05 5.940E-06 2.156f-06 1.193E-06 7.895E-07 3.875E-07 1.619E-07 8.949E-OS 6.10BE-OS 4.596E-OB "Ground level release, Desert Sigmas. All stability classes A through G

.Tab)c 3-11 (Contd)

C b) 2.2C-I!ay~occa ~tlndc leted Ctll/t) (sec/aIcter cnbecl) for each segment Dlrcc'tlon FroIa S

Site

.r~~3 3-I'~~0:2~~

1.783E-05 1.506E-05 4.991E-06 1.809E-06 Scoecnt Gonndarles 9.984E-07 6.586E-07 ln Hlles from thc Site 3.195E-07 1.287E-07 6.725E-OS 4.334E-OG 3.079E-OS SSW 4.246E-06 1.snsE-o6 8.547E-07 5.647E-07 2.746E-07 1.110E-07 5.810E-OB 3.745E-OS 2.660E-OG SW 1.413E-05 4.046E-06 1.490E-06 8.292E-07 5.500E-07 2.689E-07 '1.095E-07 5.754E-OS 3.712E-OG 2.637E-OB WSIl 9.992E-06 2.823E-06 1.029E-06 5.689E-07 3.75GE-07 1.825E-07 7.359E-OG 3.846E-OB 2.475E-OG 1.756E-OG W 8.792E-06 2.489E-OG 9.089E-07 5.03OE-07 3.324E-07 1.614E-07 6,487E-OS 3.368E-OG 2.152E-OG 1. 515E-08 WtlW 8.286E-06 2.300E-OG 8.282E-07 4.549E-07 2.990E-07 1.441E-07 5.731E-OB 2. 961E-08 1.891E-OB 1.332E-OG tlW 9 '50E-06 2.600E-06 9.244E-07 5.040E-07 3.295E-07 1;576E-07 6.218E-OB 3.220E-OG 2.073E-OB 1'.475E-08 llHW 1. 515E-05 4.145E-06 1.479E-06 B,OBOE-07 5.293E-07 2.541E-07 1.013E-07 5. 321E-08 3.473E-OG 2.SO3E-OG tl 1.656E-05 4.532E-06 1.619E-06 8.858E-07 5.GOBE-07 2.794E-07 1.117E-07 5.878E-OS 3.839E-OS 2.769E-OB lttlE 1.255E-05 3.356E-06 1.175E-06 6.350E-07. 4.12GE-07 1.956E-07 7.628E-OB 3.941E-OG 2.548E-OS 1.821E-OG tlE 1.015E-OS 2.743E-06 9.705E-07 5.274E-07 3.nnlE-o7 1.638E-07 6.419E-OB 3.303E-OS 2.117E-OB 1.500E-OS EWE 9.291E-06 2.508E-06 8.865E-07 4.810E-07 3. 133E-07 1.487E-07 5.788E-OG 2.966E-OS 1.897E-OS ).342E-08 E 8.626E-06 2.326E-06 8.225E-07 4.467E-07 2.912E-07 1.384E-07 5.403E-OB 2.774E-OB 1.777E-OG 1.259E-OG

, ESE 1.446E-05 3.891E-06 1.373E-06 7.435E-07 4.834E-07 2.285E-07 8.846E-OG 4.521E-OG 2.893E-OB 2.049E-OG SE 2 '45E-05 5.618E-06 2.013E-06 1.102E-06 7.222E-07 3.446E-07 . 1.376E-07 7. 159E-08 4.625E-OS 3.301E-OB SSE 2. 120E-05 5.895E-06 2.127E-06 1.170E-06 7.700E-07 3.721E-07 1.491E-07 7.790E-OS 5.030E-OB 3.583E-OG

- Table 3-11 (Contd) ri c) O.O-Da Deca De leted CIII/I) (sec/<<<eter cubed) for each se<Jaent Direction Fro<<< Site Se <<<ent Boundaries in Hiles fro<a the Site 0-S 1.602E-05 4.299E-06 1.468E-O& 7.920E-07 5.0&1E-07 2.342E-07 8.603E-OB 4. 155E-08 2.544E-OG 1.742E-OO SSM 1.353E-05 3.657E-06 1.269E-06 6.782E-07 4.358E-07. 2. 014 E-07 7.428E-OG 3.596E-OO 2.205E-OB 1.510E-OO SM 1.269E-05 3.4&5E-06 1.224E-06 6.579E-07 "4.244E-07 1.972E-07 7.328E-OO 3.561E-OB 2.184E-OO 1.497E-OO WSM 8.97&E-06 2.432E-06 8.448E-07 4.515E-07 2.901E-07 1.339E-07 4.930E-OB 2.3&4E-OS 1.460E-OG 9.995E-09 M 7.901E-06 2. 145E-06 7.473E-07 3.99&E-07 2. 571E-07 1.188E-07 4.375E-O& 2.112E-OB 1.291E-OB 8. 819E-09 MttM 7.446E-06 1.982E-06 6.BOSE-07 3. 614 E-07 2. 312E-07 1.060E-07 3.858E-OS 1.850E-OS 1.129E-OB 7. 701E-09 IIW 8.579E-06 2.239E-06 7.584E-07 3.993E-07 2.538E-07 1.152E-07 4. 137E-08 1.971E-OO 1.201E-OO 8,205E-09 tlMM 1.3&DE-05 3.564E-06 1.211E-06 6.382E-07 4.061E-07 1.&47E-07 6.652E-OB 3.185E-OG 1 ~ 950E-OG 1.337E-OG II 1.487E-05 3.&97E-06 1.32&E-06 6.99&E-07 4.45&E-07 2.030E-07 7.334E-OB 3.516E-DO 2.153E-OG 1.477E-OG ttttf 1.127E-05 2.OBOE-06 9.630E-07 5.023E-07 3.173E-07 1.426E>>07 5.042E-OB 2. 386E-08 1.454E-OG 9.933E-09 tIE . 9. 117E-06 2.362E-06 7.964E-07 4.180f-07 2.651E-07 1.199E-07 4.2&DE-OB 2.030E-OB 1.235E-OO 8.415E-09 EtlE 8.34&E-06 '.160E-06 7.277E-07 3.814E-07 2. 416E-07 1.089E-07 3.864E-OB 1.827E-OO 1.109E-OS 7.752E-09 E 7.750E-06 2.003E-06 6.749E-07 3.539E-07 2.243E-07 1.013E-07 3.601E-OB 1.704E-OS 1.035E-OO 7.046E-09 ESE 1.299E-OS 3.349E-06 1.12GE-06 5.889E-07 3.722E-07 1. 671E-07 S.M3E-OS 2.766E-OB I ~ 67&E-08 1.139E-OB SE 1.&36E-05 4.834E-06 1.650E-06 8.720E-07 5.555E-07 2.529E-07 . 9.11&E-OO 4.353E-OB 2.656E-OG 1.815E-OB SSE 1.904E-05 5.075E-06 1.745E-OG 9.273E-07 5.933E-07 2.723E 9.932E-OO 4.779E-OG 2.925E-OB 2.002E-OS

~

Table 3-11 (contd.)

S d) Turbine Buiidin Aelative De osition IIate D -Per Unit Area meter Direction Frtee Site Se ment Boundaries in Wiles frosn the Site

-4 4- 4 S 2.244E-OG 4.597E-09 1. 200E-09 5.390E-10 3.049E-10 1.173E-10 3.392E-ll 1.344E-11 7. 180E-12 4.444E-12 SSW 1.749E-OG 3.583E-09 9.353E-10 4.201E-10 2.376E-10 9.13GE-)l. 3.644E-ll 1.04GE-ll 5.595E-12 3.463E-12 SW 1.21GE-OQ 2.496E-09 6.515E-10 2.926E-10 1.655E-10 6.366E-ll . 1 ~ 842E-11 7.299E-12 3.89GE-12 2.413E-12 WSW 1.010 E-OQ 2.069E-09 5. 402 f-10 2.426E-10 1.372E-10 5.178E-11 6.051E-12 3.23lf-l2 2.00OE-12 W 7.468E-09 1.530E-09 3.993f-10 1.794E-10 1.015E-10 3.902E-ll 1.527E-11'.129E-11 4.474E-12 2.389E-12 1.479E-)2 WIIW 8.961E-09 1.836E-09 4.792E-10 2.152E-10 1.21GE-10 4.682E-11 1.355f-ll 5.368E-12 2.867E-12 1.774E-12 II'I 1.615E-OG 3.309E-09 8.638E-10 3.880E-10 2.195E-10 8.440E-ll 2.442E-ll 9.677E-12 5.16BE-12 3.199f-12 IIIIW 3.066E-OQ 6.280E-09 ,

1.639E-09 7.363E-10 4.165E-10 1.602E-10 4.634E-ll 1.I137f-ll 9.80GE-12 6.070E-12 II 3.891E-OG 7.97OE-09 2.081E-09 9.345E-10 5. 287E-10 2.033E-10 5.881E-ll 2.331E-ll 1.245E-11 7.705E-ll IIIIE 3.647E-OG 7.471E-09 1.950E-09 8.760E-10 4.956E-10 1.906E-10 5.513E-11 2.185E-ll 1.167E-11 7.222E-12 UE 2.492E-OG 5.104E-09 1.333E-09 5.985E-10 3.386E-10 1.302E-10 3.766E-11 1.493f-ll 7.972E-12 4.934f-l2 EIIE 1.906E-OG 3.905E-09 4.050E-09 1.019E-09 4.578E-10 2.590E-10 9.960E-11 2.Mlf-ll 1. 142E-11 6.09GE-12 E 1.977E-OG ).057E-09 4.748E-10 2.686E-10 1.033E-10 2.988E-10 1.184E-11 6.325E-12 3.775E-12'.915E-12 ESE 3.404E-OB 6.972E-09 1.820E-09 G. 175E-10 4.624E-10 1.778E-IO 5. 145E-1 1 2.039E-11 1.089E-11 6.740E-12 SE 4. 158E-08 8.518E-09 2.224E-09 9.987E-10 5.650E-10 2.173E-10 6.285E-11 2.491E-ll 1.330E-11 8.234E-12 SSE 2.983E-OG 6.lllf-09 1.595E-09 7 '65E-10 4.053E-10 1 ~ 559 E-10 4.509E-11 1.787E-11 9.543E-12 5.907E-12

Table 3-12 BADWASTG'GUILDIIIG X AIID D/ VALUES>>

a) tto Deca Utnte leted CIII/Q (sec/meter cubed) for each segment Directton From Stte

- 0 S 1. 791E-05 5.032E-06 1.836E-06 1.019E-06 6.765E-07 3.337E-07 1.405E-07 7,800E-OO 5.333E-OS 4,018E-OB SSW 2. 513 E-05 4.282E-OG 1.56QE-06 8.729E-07 5.765E-07 2.871E-07 ~ 1. 214 E-07 6.75GE-OQ 4.627E-OG 3.489E-OQ Sk 1.419E-05 4.080E-OG 1 ~ 513E-06 8.46GE-07 5.651E-07 2.811E-07 1.19GE-07 6.690E-OB 4.584E-OB 3.457E-OG WSW 1.004E-05 2.847E-06 1.044E-06 5.811E-07 3.862E-07 1.909E-07 8.059E-OG ~ 4.481E-OG 3.066E-OQ 2.311E-OG W 8.834E-06 2.512E-06 9.240E-07 5.149E-07 3.426E-07 1.695E-07 7.171E-OB 3.9QQE-OB 2.72GE-OG 2.056E-OG WIN 8.324E-06 2.320E-06 8.'416E-07 4.654E-07 3.OBOE-07 1.511E-07 6.317E-OG 3.489E-OG 2.380E-OB 1.791E-OG IIW 9.587E-06 2.620E-06 9.367E-07 5.135E-07 3.377E-07 1.639E-07 6.739E-OG 3.687E-OQ 2.506E-OS 1. 881E-08 UIIW 1.520E-OS 4.169E-06 1.494E-06 8.198E-07 5.393E-07 2.620E-07 1.07BE-07 5.905E-OB 4.017E-OG 3.015E-OG tt 1.661E-OS 4.558E-OG 1.G36E-06 8.987E-07 5.91QE-07 2.881E-07 1.198E-07 6.518E-OG 4.435E-OG 3.329E-OQ IIIIE 1.259E-05 3.378E-06 1.189E-06 6.45GE-07 I 4.2$ 7E-07 2.025E-07 8.191E-OG 4.445E-OS 3.015E-OG 2.260E-OB tlE 1.019E-OS 2.764E-OG 9.837E-07 5.377E'-07 3.52GE-D7 1 ~ 707E-07 6.97GE-OG 3.804E-OQ 2.581E-OG 1.935E-OG EIIE 9.328E-06 2.52QE-06 8.9GgE-07 4.907E-07 3.215E-07 1.550E-07 6.302E-OB 3.426E-OG 2.322E-OB 1.739E-OG E 8.659E-06 2.344E-06 8.336E-07 4.553E-07 2.985E-07 1.441E-07 5.868E-OQ 3.191E-OB 2.162E-OS 1;619E-0&

ESE 1.452E-OS 3.919E-O6 1.39IE-06 7.573E-07 4.950E-07 2.375E-07 9.577E-OB 5. 173E-08 3.494E-OQ 2.611E-OG SE 2.052E-05 5.657E-06 2.03GE-06 1.121E-06 7 '87E-07 3.595E-07 1.483E-07 8. 123E-OQ 5.519E-OO 4.141E-OG SSE 2. 128E-05 5.940E-06 2 156E-06 1.193E-06 7.895E-07 3.875E-07 1. 619E-07 8.949E-OG 6.10GE-OG 4.59GE-OG

'Ground Level release. Desert stgmas. All stabIIIty classes% through G.

'I Table 3-12 (Cont'd) b) 2.26-Da Deca Un<le leted CIII/I) (sec/meter cubed) for each segamnt Direction From Site Se nt Boundaries in Mlles from the Site 5 1 '83E-05 4.991E-06 1.809E-06 9.984E-07 6.586E-07 3.195E-07 1.287E-07 6.725E-OQ 4.334E-OG 3.079E-OG SSW 1.506E-05 4.246E-06 1.545E-06 8.547E-07 5.647E-07 2.746E-07 1. 110E-07 5.810E-O& 3.745E-OB 2.660E-OS SW 1.413E-05 4.056E-06 1.490E-06 8.292E-07 5.500E-07 2.689E-07 1.095E-07 5.754E-OQ 3.712E-OG 2.637E-OB WSW 9.992E-06 2.823E-06 1.029E-06 5.689E-07 3.75QE-07 . 1.825E-07 7.359E-OS 3.846E-OS 2.475E-OS 1.756E-OB W 8.792E<<O6 2.489E-06 9.089E-07 5.030E-07 3.324E-07 1.614E-07 6.487E-OB 3.368E-OQ 2.152E-OB 1.515E-OQ WIIW 8.286E-06 2.300E-06 8.282E-07 4.549E-07 2.990E-07 1.441E-07 5.731E-07 2.961E-OB 1.891E-OB 1.332E-OS IIW 9.550E-06 2.600E-06 9.244E-07 5.040E-07 3.295E-07 1.576E-07 6.218E-M 3.220E-OQ 2.073E-OS 1;475E-08 IIIIW 1.515E-05 4.145E-06 1.479E-06 S.OBOE-07 5.293E-07 2 ~ 541E-07 1.013E-07 5.321E-OG 3.473E-OS 2.503E-OS II 1.656E-OS 4.532E-06 1.619E-C6 8.85QE-07 5.80BE-07 2 '94E-07 1.117E-07 5.87QE-OB 3.839E-OG 2.769E-OS IIIIE 1.255E-OS 3.356E-06 1.175E-06 6.350E-07 4.128E-07  !.956E-07 7.628E-OB 3.941E-OQ 2.548E-OQ 1.821E-OB tlf 1.015E-05 2.743E-06 9.705E-07 5.274E-07 i 3.44!E-07 1.63QE-07 6.419E-OQ '.303E-OB 2.117E-OS 1. 500E-08 EIIE 9. 291E-06 2.SOQE-O6 8.865E-07 4.8!OE.-07 I 3.133E-07 1.487E-07 5.788E-OS 2.966E-OQ 1.897E-OQ 1.342E-OS E 8.626E-06 2 '26E-06 8.22SE-07 4.467E-07 2 '12E-07 1.384E-07 5.403E-OQ 2.774E-OG 1.777E-OQ 1.259E-OQ fsf 1.446F.-05 3.89!E-OG 1.383E-06 7.435E-07 4.834E-07 2.285E-07 8.846E-OQ 4.521E-OQ 2.893E-OQ 2.049E-OG SE 2'.OnSE-OS 5.61GE-06 2.013E-06 1.103E-06 7.222E-07 3.466E-07 1.376E-07 7.159E-OG 4.625E-OG 3. 301E-08 SSE 2.120E-05 5.895E-06 2.127E-06 1.170E-06 7.700E-07 3.721E-07 1.491E-07 7.790E-OB 5.030E-BO 3.583E-OQ

Table 3-12 (Cont'd) c) 8.0 Da Oeca Oe leted (Corrected for Open .Terrain Recirculation)

CIII/It (sec/meter cubed) for each segment Direction From Site Se ent Boundaries in IIiles from the Site

.5- -0 0- 0 S 1.602E-05 4.299E-06 1.486E-06 7.920E-07 5.081E-07 2.342E-07 8.603E-OS . 4;155E-08 2.544E-OB 1. 742E-08 SSM 1.353E-05 3.657E-06 1.269E-06 6.782E-07 4.358E-07 2.014E-07. 7.428E-OB 3.596E-OB 2.205E-OB 1.510E-OB SM 1.269E-05 3.485E-06 1.224E-06 6.579E-07 4.244E-07 1.972E-OI 7.3)BE-08 3. 561E-08 1.460E-OB 1.497E-OB WSW 8.976E-06 '2.432E-06 8.448E-07 4.515E-07 2.901E-07 1.339E-07 4.930E-OB 2.384E-OB 1.460E-OB 9.995E-09 W 7.901E-06 2. 145E-06 7.473E-07 ~ 3.998E-G7 2. 571E-07 1.188E-07 4.375E-OS 2.112E-OB 1.291E-OS 8. 819E-09 MIIM 7.446E-06 1.982E-06 6.BOSE-07 3,614E-07 2.312E-07 1.060E-07 3.858E-OB 1.850E-OB 1. 129E-08 7.701E-09 NM 8.579E-06 2.239E-06 7.584E-07 3.993E-07 2(538E-07 1.152E-07 4.137E-OS 1.971E-OB 1.201E-OB 8.205E-09 NtIM 1;360E-05 3.564E-06 1.211E-06 6.382E-07  !061E-07 1.847E-07 6.652E-OS 3.185E-OB 1.950E-OB 1 ~ 337E-08 N .1.487E-05. 3.897E-06 1.326E-06 6.996E-07 4'.456E-07 2.030E-07 '.334E-OS 3.516E-OS 2.153E-OB 1.477E-OS IIIIE 1. 127E-05 2.888E-06 9.630E-07 5.023E-07 3.173E-07 1.426E-07 5.042E-OS 2.386E-OS 1.454E-OB 9.933E-09 tlE 9.117E-06 2.362E-06 7.964E-07 4.180E-07 2.651E-07 1.199E-07 4.280E-OB 2.030E-OB 1.235E-OB 8.415E-09 EtiE 8.348E-06 2.160E-06 7.277E-07 3.814E-07 2.416E-07 1.089E-07 3.864E-OB 1.827E-OB 1. 109E-08 7.552E-09 E .. 7.750E-06 2.003E-06 6 '49E-07 3.539E-07 2.243E-07 1.013E-07 3.601E-OS 1.704E-OS 1.035E-OB 7.046E-09 ESE 1.299E-05 3.349E-06 1.126E-06 5.889E-07 3.722E-07 1.671E-07 5.883E-OB 2.766E-OB 1.676E-OB 1.139E-OS SE 1.836E-05 4.834E-06 1.650E-06 8.720E-07 5.555E-07 2.529E-07 9.116E-OB 4.353E-OB 2.656E-OB 1.8)5E-OB SSE 1.904E-05 5.075E-06 1.745E-06 9.273E-07 5.933E-07 2.723E-07 9.932E-OB 4.779E-OB 2.925E-OB 2,002E-OB

Table 3-12 (Cont'd) d) Raduaste Building Relative De osition Rate D <<Per Unit Area tieter 2)

D iree t ion From Site Senment Boundaries in Miles from the Site JQ 40-50 5 2. 2 l4E-OQ 4.597E-09 1.200f-09 5.390E-10 3.049E-IO 1.173E-10 3.392E-11 1.344E-11 7. 180E-12 4.444E-12 SSM 1.749E-OG 3.583E-09 9 353f-10 4.201E-10 2.376E-10 9.138E-ll 2.644f-ll 1.048E-11 5 '95E-12 3.463E-12 SM 1.2lGE-OG 2.496E-09 6.515E-10 2.926E-10 1.655E-10 6.366E-11 1.842E-ll 7.299E-12 3.89BE-12 2.413E-12 WSM 1.010E-OO 2.069E-09 5.402E-10 2.426E-10 1.372E-10 5.278E-11 1.527E-11 6.051E-12 3. 231E-12 2.000E-12 W 7.46GE-09 1.530E-09 3.993E-10 1.794E-10 1.015E-10 3.902E-11 1.129E-11 4.474E-12 2.389E-12 1.479E-12 kttlt 8.961f-09 1.836E-09 4.792E-10 2.152E-10 1.218E-10 4.682E-ll 1.355E-11 5.368E-12 2.867E-12 1.774E-12 Nt 1.615E-OO 3,309E-09 8.638E-10 3.OBOE-10 2.195E-10 8.440f-ll 2.442E-11 . 9.677E-12 5.16GE-12 3.199E-12 RflM 3.066E-OG 6.280E-09 1.639E-09 7.363E-10 4.165E-10 1.602E-IO 4.634E-11 1.837E-11 9.80OE-12 6.070E-12 tt 3.891E-OG 7.970f-09 2.081E-09 9.345E-10 5.287E-10 2.033E-10 5.881E-ll 2.331E-ll 1.245E-11 7.705E-12 ttttE 3.647E-OG 7.471E-09 1.950E-09 8.760E-10 4.956E-10 1.906E-10 5.513f-ll 2.185E-11 1.167E-ll 7.222E-12 ttf 2.492E-OG 5. 104 E-09 1.333E-09 5.985E-'10 3.386E-10 1.302E-10 3.766E-11 1. 493E-11 7.972E-12 4.934E-12 fttf 1.906E-OB 3.905E-09 1.019E-09 4.578E-.10 2.590E-10 9.960E-11 2.881E-11 1.142E-l 1 6.09OE-12 3.775E-12 E 1.977E-OG 4.050E-09 1.057E-09 4.74BE-10 ,

i 2.686E-10 1.033E-10 2.988E-ll 1.184E-ll 6.325E-12 3.915E-12 ESE 3.404E-OG 6.972E-09 1.820E-09 8. 175E-'10 I 4.624E-10 1.778E-10 5 ~ 145E-11 2.039E-11 1.089E-ll 6.740E-12 SE 4.158E-OO 8.518E-09 2.224E-09 9.987E-10 5.650E-10 2.173E-10, 6.285E-11 2.491E-11 1 ~ 330E-11 8.234E-12 SSE 2.983E-OG 6.111E-09 1.595E-09 7.165E-10 4.053E-10 1.559E-10 4.509E-ll 1.787E-11 9.543E-12 5.907E-12

Table 3-13 CHARACTERISTICS OF WNP-2 GASEOUS EFFLUENT RELEASE POINTS Reactor Radwaste Turbine Bui 1 din Bui ldin Bui 1 din Height of release point above ground level (m) 70.6m .31 1 27.7 Annual average rate of air flow from release point (m3/sec) 44.8 38.7 125.6 Annual average heat flow from release point (cal/sec) 1.06 x 106 2.9 x 106 9.1 x 105 Type and size of release Duct 3 Louver houses 4 Exhaust fans point (m) 1.14 x 3.05 1.4 x 2.4 x 0.8 1.45 x 2.01, Each Each Effective vent area (m2) 3.48 2 x 2+7 3 x 2.91 Vent velocity (m/sec)* 12.9 2 x 525 cfm** 14.4 Effective diameter (m) 1.0

( <r2 = area)

Building height (m) 70.1 70.1 70.1

• Reactor Building exhaust in vertical direction. Radwaste and Turbine Building exhaust in horizontal plane.

~FSAR Drawing 6-41, 525 cfm x 2 out of 3, will run at any one time.

82

Table 3-14 REFERENCES FOR VALUES LISTED IN TABLE 3-9 Reference 1 U.S. Map Reference 2 GASPAREDIT Input Instruction, page 10 Reference 3 Regulatory Guide 1.109, Table E-15

=Reference 4 Section 2.3, MNP-2 FSAR, Table 2.3-20 Reference 5 Section 2.3, MNP-2 FSAR, page 2.3-3 Reference 6 Keith E; Yandon, October 1980, "Projections and Distributions of Population Within a 50-Mile Radius of Washington Public Power Supply System Nuclear Projects Nos. 1, 2, and 4 by (i

Compass Direction and Radii Intervals," 1970-2030

)

Reference 7 WNP-2 ER, Table 5.2-12 Reference 8 WNP-2 FSAR, Table 11.3-7 Reference 9 Radiological Programs Calculation Log No. 83-1 Reference 10 MNP-2 XOqDOg Computer Run Reference 11 Regulatory Guide 1.145, Section C.l.2 83

Table 3-15 OESIGN BASE PERCENT NOBLE GAS (30-MINUTE DECAY)*

Isoto e Percent of Total Activit Kr-83M . 2.9 Kr-85M 5.6 Kr-85 0.

Kr-87 15 Kr-88 18 Kr-89 0.2 Xe-131M 0.02 Xe-133M 0.3 Xe-133 8.2 Xe-135M 6.9 Xe-135 22 Xe-137 0.7 Xe-138 21

<<From Table 11.3-1 WNP-2 FSAR 84

TABLE 3-16 ANNUAL DOSES AT SPECIAL LOCATIONS WITHIN WNP-2 SITE BOUNDARY Source: WNP-2 Gaseous Effluent Whole Thyroid Distance Occupancy Body Dose Dose Location (Miles) (hrs/yr) (mrem/ r) mrem/ r BPA Ashe Substation 0.5 N 2080 2.3E-O 3.4E-O DOE Train 0.5 SE* 78 9.2E-02 1.5E-01 Wye Burial Site 0.5 WNW 4.0E-03 6.1E-03 WNP-1 1.2 ESE 2080 6.1E-01 9.6E-01 WNP-4 1.0 ENE 2080 3.8E-01 6.0E-Ol WNP-2 Visitor Center 0.5 ENE 9.1E-03 1.6E-02 Taylor Flats~ 4.2 SE 8760 1.2E-O 7.9E-O Site Boundary~ 1.2 SE 8760 4.3E+01 2.4E+0 "The sector with the highest X/g values (within 0-0.5 mile radius) was used.

~Not within site boundary. Closest residental area representative of maximum individual dose from plume, ground, goat milk, and inhalation exposure pathways. Included for comparison.

~Assumed continuously occupied. Actual occupancy is very low. Doses from Inhalation and Ground Exposure pathways. No food crops.

85

TABLE 3-17 ANNUAL OCCUPIED AIR DOSE AT SPECIAL LOCATIONS WITHIN WNP-2 SITE BOUNDARY Annual Annual Beta Air dose Gamma Air Dose Location mrad mrad BPA Ashe Substation 2.1E-O 3.2E-O DOE Train 9.2E-02 1. 5E-01 Wye Burial Site 3.6E-03 6.0E-03 WNP-1 5.5E-01 8.6E-01 WNP-4 3. 6E-01 2.2E-O WNP-2 Visitor Center 9.4E-03 1.5E-02 Taylor Flats* 1.5E-O 1.8E-O Site Boundary 2.9E-01 5.4E+0

• Not within site boundary. Closest residential area. Included for comparison.

86

tn K

CJ O

X X

C O

I m

27 I r C

'X U) ill I'H. J. Ashe N r Substation 0

2:'D I WNP.O O~ IICCOCAAI ul r+ ACCII~ PNNAAI ACCIIO wNp twot Novoo Flow V5 CD 00 WYE auiNAC NII, IONIA

~ WNP S ca WNP

'll + Novoo S'vot GJ

~

t-0 n C>

lll 0

<,0 gi WNP I 2:~" oo "1;9 v)~ m AO

~ ~) I+o C) V Cc CO Plant Supporl m Facility 0 8 all EIIOCNCY Vl opsaA1 IONa PAcLn c Santon Swttchlny Slation NORTH tta6 oouII Sita

4.0 COMPLIANCE WITH 40 CFR 190 Standard Technical Specification 3.11.4 specifies that when the calculated doses associated with the effluent releases exceed twice the limits of any one of the Specifications 3.11.1.2, 3.11.2.2, or 3.11.2.3, a Special Report to the Commission shall be prepared and submitted, and subsequent releases will be limited such that the dose or dose commitment to a real individual from all uranium fuel cycle sources is limited to 25 mrem to the total body or any organ (except the thyroid, which is limited to 75 mrem) over 12 consecutive months. The Report shall include an analysis which demonstrates that r adi-ation exposures to all real individuals from all uranium fuel cycle sources (including all liquid and gaseous effluent pathways and direct radiation) are less than the standards in 40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operations. If analysis indicates that releases resulting in doses that exceed the 40 CFR 190 standard could occur, a variance from the Commission to permit such releases will be requested. The Special Report shall include the following:

1. Determination of which uranium fuel cycle facilites or operations, in

) addition to WNP-2, contribute to the annual dose to the maximum exposed member of the public.

2. Identification and explanation of the location of the maximum individual.

I 3..Determination of the total annual dose to the maximum individual from all pathways and sources of radioactivity and radiation, including direct radiation from N-16, the plant, and storage facilities. The direct radiation dose may be either calculated or measured. Pathway doses shall be calculated using the methodologies described in NUREG-0597 (GASPAR), NUREG GR-1276 (LADTAP). The external measurements or calculations of direct radiation will be documented in the report.

88

5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING Radiological environmental monitoring is intended to supplement radiological

~

effluent monitoring by verifying that measurable concentrations of radioactive

~

materials and levels of radiation in the environment are not greater than expected based on effluent measurement and dose modeling of environmental exposure pathways. The Radiological Environment'al Monitoring Program (REMP) for WNP-2 provides for measurements of radiation and radioactive materials in those exposure pathways and for those radionuclides for which the highest potential dose commitment to a member of the public would result due to plant operati cns .

The WNP.-2 RE% is designed to conform to regulatory guidence provided by Regulatory Guide 4.1, 4.8 and the Radiological Assessment Branch Technical Position, taking into consideration certain site specific characteristics.

The unique nature of the WNP-2 site on Federally owned and administered land

'(Hanford Reservation) dedicated to energy facilities, research, waste management and as a natural reserve, forms the basis for many of the site specific parameters. Amongst the many site specific parameters considered is demographic data such as:

1) No significant clusters of population including schools, hospitals, business facilities or primary public transportation routes are located within 8 km (5 mile) radius of the plant.

2) No private residences are located on the Hanford Reservation.

3) The closest resident is east of the Columbia River at a distance of approximately 4 miles.

Additicnal site information is available in the WNP-2 Environmental Report, Operating License Stage.

The Radiological Environmental Monitoring Program is conducted as specified in the Plant Technical Specifications, 3/4e12 and detailed in the following secti ons.

89

5.1 Radiolo ical Environmental Monitor in Pro ram (REMP)

Environmental samples for the REMP are collected in accordance with

~

Table 5-1. This table provides a detailed outline of the sampling program by

~

sample type, sample location code, sampling and collection frequency, and type and frequency of analysis of samples collected within exposure pathway.

Deviations from the sampling frequency detailed. in Table 5-1 may occur due to circumstances such as hazardous conditions, malfunction of automatic sampling equipment, seasonal-unavailability, or other legitimate reasons. When sample media is unobtainable due to equipment malfunction, special actions per program instruction shall be taken to ensure that corrective action is implemented prior to the end of the next sampling period. In some cases, alternate sample collection may be substituted for the missing speciman. All deviations from the sampling program detailed in Table 5-1 shall be documented and reported in the Annual Radiological Environmental Operating Report in accordance with Plant Technical Specifications.

In the event that it becomes impossible or impractical to continue sampling a media of choice at currently established location(s) or time, an evaluation shall be made to determine-a-suitable alternative media and/or location to provide appropriate exposure pathway evaluations. The evaluation and any substitution made shall be implemented in the sampling program within 30 days of identification of the problem. All changes implemented in the sampling program due to unavailability of samples shall be fully documented in the next Semiannual Radioactive Effluent Release Report and ODCM, including revised table(s) and figure(s) reflecting the new locations and/or media.

WNP-2 sampling stations are described in Table 5-2. Each station is identified by an assigned number or alphanumeric designation, meteorological sector (16 different, 22-1/2o compass sections) in which the station is located, and radial distance from WNP-2 containment as estimated from map positions. Also included in Table 5-2 is information identifing the type(s) of samples collected at each station.

90

5.2 Land Use Census A land use census shall be conducted in accordance with Plant Technical Speci-fications at least once per calendar year during the growing season being completed no later than September 30 each year. The information obtained is to be used to identify demographic changes in the unrestricted areas to permit modifications in monitoring programs for evaluation of doses to individuals through critical pathway analysis and estimation of dose to the total population within a 50-mile (80 km) radius. Local demographic data shall include information on growing season, irrigation pr actices, cattle feed sources, land productivity, and fish and game consumption within a 50-mile radius. More specific data within each of the 16 meteorological sectors, such as distance to nearest resident, nearest milk animal, and nearest garden greater than 50m2 (500 ftZ) in size producing broad leaf vegetation shall be identified to support recalculation of maximum individual dose estimates.

Site-specific considerations such as the Department of Energy's Hanford Reservation Site Boundary, within which WNP-2 is located, may require that

'specific information be collected beyond a 5-mile (8 km) radius in certain meteorological sectors to adequately identify pertinent data.

The results of the land use census will be reported within 30 days of completion of all field work and no later than October 31 of each year to the person(s) responsible for calculation of individual and population doses. All changes, such as a location yielding a greater estimated dose or different location with a 20 percent greater estimated dose than a currently sampled location, shall be reported in the next Semiannual Radiological Effluent Report per Plant Technical Specifications and the monitoring program changed to reflect the new data as appropriate.

The best available information, whether obtained by aerial survey, door-to-door survey, or consultation with local authorities, shall be used to complete the Land Use Survey and the results reported in the Annual Radiological Environmental Operating Report per Plant Technical Specifications.

91

5.3 Labor ator Interco arison Pro ram Analysis of REMP samples is contracted to a provide~ of radiological analyti-c cal services. By contract, this analytical service vendor is required to

~

~

conduct all activities in accordance with Regulatory Guides 4.1, 4.8, and 4.15, and,to include in each monthly report actions pertinent to their participation in the Environmental Protection Agency's (EPA) Environmental Radioactivity Laboratory Intercomparison Studies (Crosscheck) Program. A precontract award survey and annual audit at the contractor's facility ensure that the con-tractor is participating in the Crosscheck Program.

The results of the contractor's analysis of Crosscheck samples shall be included in the Annual Radiological Environmental Operating Report in accordance with the Plant Technical Specifications.

Besides the vendor 's required participation in the EPA's Crosscheck Program,-

the Department of Social and Health Services (DSHS) of the State of Washington oversees an analytical program for the Energy Facility Site Evaluation Council (EFSEC) to provide an independent test of WNP-2 REMP sample analyses. The WNP-2/DSHS split samples are analyzed by Washington State's Office of Public Health Laborator ies and Epidemiology, Environmental Radiation Laboratory (ERL). The State's ERL participates in the EPA Crosscheck Program, as well as other federal participatory analytical 'quality assurance programs. The results of the ERL, EPA Crosscheck data are included in an annual report, "Environmental Radiation Program, Environmental Health Surveillance, State of Washington" which is available for comparison with the WNP-2 data.

5.4 Re ortin Re uirements WNP-2 radiological environmental surveillance program activities are presented annually in the Annual Radiological Environmental Operating Report (AREOR).

This report is submitted to the Director of the NRC Regional Office, with copies to the Director, Office of Nuclear Reactor Regulation, and the State of Washington Energy Facility Site Evaluation Council (EFSEC) by May I of each 92

year for all program activities conducted the previous calendar year. The period of the first operational report begins with the date of initial cri i-cality. A preoperational report is due to EFSEC within 90 days of initial criticality.

The annual report is to include the following types of information: a tabu-lated summary; interpretations and analyses of trends for results of radio-logical environmental surveillance activities for the report period, including comparisons with operational controls, preoperational studies, and previous environmental surveillance reports as appropriate; an assessment of the observed impacts of plant operation on the environment; a brief description of the radiological environmental monitoring program; maps representing sampling station locations, keyed to tables of distance and direction from reactor containment; results of the land use census; and the results of analytical laboratory participation in the EPA's Crosscheck Program. The tabulated sum- .

mary shall be presented in a format represented in Table 5-3. A supple-mentary report is required if all analytical results are not available for inclusion in the annual report within the specified time frame. The missing r data shall be submitted as soon as possible upon receipt of the results.

Along with the missing data-;the supplementary report shall include an explanation as to the cause for the delay in completion of the analysis within the report period.

A nonroutine radiological environmental operating report is required to be submitted within 30 days from the end of any quarter in which a confirmed measured radionuclide concentration in an environmental sample averaged over the quarter sampling period exceeds a reporting level. Table 5-4 specifies the reporting level (RL) for most radionuclides of environmental importance due to potential impact from plant operations. When more than one of the nuclides listed in Table 5-4 is detected in a sample, the reporting level is considered to be exceeded and a nonroutine report required if the following conditions are satisfied:

93

Concentration 1 Concentration 2

. Reporting Level 1 Reporting Level 2

+

For radionuclides other than those listed in Table 5-4, the reporting level is considered to have been exceeded if the potential annual dose to an indi-vidual is greater than or equal to the design objective doses of Appendix I, 10 CFR 50.'hen a nonroutine report on an unlisted (Table 5-4) radionuclide must be issued, it shall include an evaluation of any release conditions, environmental factors, or other aspects necessary to explain the anomalous sample results-.

When it can be demonstrated that the anomolous sample result(s) exceeding reporting levels is not the result of plant effluents, a nonroutine report does not have to be submitted. A full discussion of the sample result and subsequent evaluation or investigation of the anomolous result will be included in'the Annual Radiological Environmental Operational Report.

94

TABLE 5-.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Sampling and 1 Type and Frequency 1 Sam le T e Sam le Location Code Collect'ion Fre uenc of Anal sis

1. AIRBORNE

a. Particulates 1, 4-9, 21, 23, 40, Continuous sampling 'articulate:

radioiodine and and 48 Weekly collection ~k. isotopic3,Gross gamma 11 quarterly composite (by location)

Radioiodine: I-131 analysis, weekly

b. Soilll 9, 1, 7, 21, and 23 Annually Gamma isotopic3

2. DIRECT RADIATION

a. TLD4 1-9, 10-25, 40-47, Quarterly, annually Gamma, quarterly data 49-51, 53-56, 1S-16S review

b. P IC12 1, 21, and 23 Continuous recording, Gamma, monthly data monthly tape exchange review

3. WATERBORNE

a. f Sur ace13 26 and 28 Composite aliquots5, Gamma isotopic3, monthly tritium quarterly composite

b. Drinking water6 26, 28 and 29 Composite aliquots5, Gamma isotopic3, monthly Gross Beta, tritium quarterly iomposite

c. Ground water7 31, 32, and 52 Quar terly Gamma isotopic3 and tritium, quar ter ly

TABLE 5-1 (contd.)

• 1 Sampling and 1 Type and Frequency 1 Sam le T e Sam le Location Code Collection Fre uenc of Anal sis WATERBORNE (contd.)

d. Sediment from 33 and 34 Semiannually Gamma isotopic3 shoreline

4. INGESTION

a. Milk8 9, 35, 36, and 40 Semimonthly during Gamma isotopic3 grazing season, Iodine-131 monthly at other times

b. Fish9 30, 38, and 39 Seasonal or Gamma isotopic3 1 Semiannually

c. Garden produce10 37 and 9 Monthly during grow- Gamma isotopic3 ing season in the Riverview area of Pasco and a control

. near Grandview-

• Sample locations are graphically depicted in Figures 5-1 and 5-2.

IDeviations are permitted if samples are unobtainable due to hazardous conditions seasonal avail-Al) deviations will ability, malfunction of automatic sampling equipment, or other legitimate reasons. be documented in the Annual Radiological Environmental Monitoring Report.

2Particulate sample filters will be analyzed for gross beta after at least 24-hour decay. If gross beta activity is greater than 10 times the mean of the control sample, gamma isotopic analysis should be performed on the individual sample.

3Gamma isotopic means identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents of the facility.

TASLE 5-1 (gontd.)

Pressurized Ion Chambers (PICs) are instruments-for measuring and recording dose rate continu-ously. The three PICs are a part of a special two-phase, two-year monitoring program for the Energy Facility Site Evaluation Council.

13Station 28; 300 Area drinking water (untreated at sampling point) is a river (surface) water sample from beyond the mixing zone of the WNP-2 discharge, safisfying the BTP criteria -for a discharge sample. Station 27 is sampled from the WNP-2 discharge effluent to allow for quantification of discharges to the river from each operating plant.

14Drinking and groundwater samples will be analyzed and reported in accordance with'he requirements of 40 CFR Part 141 for tritium, because of the presence of a tritium plume in the unconfined aquifer in the vicinity of WNP-2. This groundwater containment is. the result of Hanford Site operations since 1944 (PNL-4659, Groundwater Surveillance at the Hanford Site for CY 1982).

I TABLE 5-1 (sontd.)

1 LD refers to thermoluminescent dosimeter. For .purposes of WNP-2 RENP, a TLD is a phosphor card

( 32mm x 45mm x 0.5mm) with eight individual read-out areas (four main dosimeter areas and four back-up dosimeter areas) in each badge case. TLDs used in REHP meet the requirements of Regulatory Guide 4.13 (ANSI N545-1975), except for specified energy-dependence response. Correction factors are available for energy ranges with response outside of the specified tolerances. TLD stations IS-16S are special interest stations and are not included amongst the 34 routine TLD stations required by Plant Technical Specifi-cation, Table 3.12-1.

5Composite samples will be collected with equipment which is capable of collecting an aliquot at time intervals which are short relative to the compositing period.

6Station 26, WNP-2 makeup water intake from the Columbia River, is considered the control for drink-ing water samples. Drinking water samples are not routinely analysed for I-131 from two week composit.

I-131 analysis calculated for the consumption of water is greater than 1 mrem per year.

7Additional groundwater sampling is conducted by plant chemistry personnel to demonstrate compliance with EPA drinking water standards. Results of WNP-2 well 83 pumphouse sample from plant sampling program will be included in RENP Annual Radiological Environmental Monitoring Report (Station 52).

BHilk samples will be obtained from farms or individual milk animals which are located in sectors with high calculated annual average ground-level D/gs and high dose potential. Milk sample locations are7greater than 5 km distance recommended in the Branch Technical Position due to the restricted area of the Hanford Reservation on which WNP-2 is located. Nearest resident is approximately 6 km and nearest milk animal is approximately 10 km distant from WNP-2. If Cesium-134 or Cesium-137 is measured in an individual milk sample in excess of 30 pCi/1, then Strontium-90 analysis should be performed.

9There ar'e no comnercially important species in the Hanford reach of the Columbia River. Host recreationally important species in the area are anadromous, primarily salminoids. Four specimen will normally be collected by electroshock technique in the vicinity of the plant discharge. If electroshocking produces insufficient samples, anadromous species may be obtained from a catch pond at the Ringold Fish Hatchery (Station 39).

10Garden produce will routinely be obtained from farms or gardens using Columbia River water for irrigation. One sample of a root crop, leafy vegetable, and a fruit should be collected each sample period if available. The variety of the produce sample will be dependent on seasonal availability.

11Soil samples are collected to satisfy the requirements of the Site Certification Agreement (SCA),

WNP-2.

TABLE

~

WNP-2 REMP LOCATIONS Station Sector Radial Miles 1S N 0.3 X 2S NNE 0.4 X 3S NE 0.5 X 4S ENE 0.4 X 5S E 0.4 X 6S ESE 0.4 X 7S SE 0.5 X 8S SSE 0.7 X 9S S 0.7 X 10S SSW 0.8 X 11S SW 0.7 X 12S WSW 0.5 X 13S W 0.5 X 14S WNW 0.5 X 15S NH 0.5 X 16S NNW 0.4 X

TAOLE 5-2 (coned.)

r Station Sector Radial Miles 1 S 1.3 X X X X 2 NNE 1.8 X 3 SE 2.0 X SSE 9.3 X X 5 ESE 7.7 X X 6 S 7.7 X X 7 WNW 2.7 X X 8 ESE 4.7 X X 9A>> WSW 30.0 X X 98>> WSW 35.0 9C* WSW 33.0 X 10 3.1 X ll ENE

'.1 X

12 NNW 6.1 X 13 SW 1.4 X 14 WSW 1.4 X 15 -

1.4 X 16 WNW 1.4 X 17 NNW 1.2 X

Oj

TABLE 5-2 Station Sector Radial Miles 18 N X 19 NE 1.8 X 20 ENE 1.9 X 21 ENE 1.5 X X X X 22 E 2.1 X 23 ESE 3.0 X X X X 24 SE 1.9 X 25 SSE 1.6 X 26* E 3.2 X X 27 E 3.2 X 28 SSE 7.4 29 SSE 11.0 30 E 3.5 31 E' 1.1 32 1.2 33* ENE 3.3 34 ESE 3.3 35 ENE 10.5 36 ESE 7.2 37A SSE 17.0 37B SSE 17.0 38* E 9.3

TABLE 5-2 (cont).)

Station Sector Radial Miles 39 NE 4.3 40 SE 6.4 X X 41 SE 5.8 X 42 ESE 5.6 X 43 E 5.7 X 44 ENE 5.7 X 45 ENE 4.2 X 46 NE 4.7 X 47 N 0.5 X 48 NE 4.3 49 NW 1.2 50 SSW 1.2 51 ESE 2.1 52 N 0.1 X X 53 N 7.5 X 54 NNE 6.5 X 55 SSE 7.0 X 57 SSW 7.0 X

• Control location.

aEstimated from center of WNP-2 Containment from map positions.

bIncluded in sampling program to satisfy requirements for Site Certification Agreement with the State of Washington.

cWHP-2 drinking water sampled and analyzed through plant chemistry program.

0

'POLE 5-3 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

a

-A Name of facility Docket No.

Location of Facility Reporting Period County, State Location with Highest Medium or Type and All Indicator Annual Mean Number of Pathway Sampled Total Number Lower Limit Locations Name Mean f Control Locations Nonroutine (Unit of of Analyses of Detection (f) Distance and Mean (f) Reported Measurement Performed LLD Mean Ran e Direction Ran e 0.10 (5/52)

~R0.08 (8/104)

Measurementc Air particulates Gross 416 0.01 0.08 (200/312) Middletown (pCi/m3) (0.05-2.0) 5 mi. 340o (0.08-2.0) (1.05-1.40)

-Spec 32 137Cs 0.01 0.05 (4/24) Smithville 0.08 (2/4) LLD (0.03-0.13) 2.5 mi. 160o (0.03-2.0) 131I 0.07 0.12 (2/24) Podunk 0.20 (2/4) 0.02 (2/4)

(0.09-0.18) 4.0 mi. 270P (0.10-0.31) fish (pCi/kg) -Spec. 8 (wet weight) 137Cs 130 LLD LLD 90 (1/4) 134Cs 130 LLD LLD LLD 60Co 130 180 (3/4) River Mile 35 See Column 4 LLD (150-225)

Summary Table is taken from the NRC s Branch Technical Position, Rev. 1, Nov. 1979, and provided for illustrative purpose:

only.

cMean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (f).

Othello NASHINGTON 38 Conn ell Lower Snake RNer Granite Dem Priest Rapids IDAHO Men!ord Dam Resenation 35 I A Lower LJ'ttle Goose I hfonumental Dam Pomeroy WNP-2 I Dam I

9C Clarkston A Dayton Sun yslde ~ 9A 9 Eureka Benton City West Ichtand 9B ~

Al e Grandvlew A Pasco

%+or e 3TA, ~ Ice Marbor Reer ~

Prosser Dam Kennewtck Walla Walla McNary Dam OREGON Coktmbia ~

1 Inch 16 mlles A Sample Locations 0 8 15 FlGURE 5 ]. Radlologlcal Environmental Monltorlng Sample Locations Outside of;10-Mlle Radius 822'll 1

C' TABLEg5-4 REPORTING LEVELS FOR NONROUTINE OPERATING REPORTS eporting Leve R Airborne Particulate Broad Leaf

~Anal sis Water or Gases Fish Milk ~n (pCi/1) (pCi/m3) (pCi/kg, wet) (pCi/1) (pCi/Kg, wet)

H-3 2 x 104*

Mn-54 1 x 103 3 x 104 Fe-59 4 x 102 1 x 104 Co-58 1 x 103 3 x 104 Co-60 3 x 102 1 x 104 Zn-65 3 x 102 2 x 104 Zr-Nb-95 . 4 x 102 I-131 0.9 1 x 102 Cs-134 30 10 1 x 103 60 1 x 103 Cs-137 50 20 2 x 103 70 2 x 103 Ba-La-140 2 x 102 3 x 102

• For drinking water samples. This is 40 CFR Part 141 value.

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IO to ~ rVIK ' II PLAN ZONE MAP f llrtTfil <<I I SU&PLY SYSTEM 21 '10 MILE RADIUS dot 0 11 1 l'I I ~ IC W&5HVOTOATTJILICFQI'ifA CP SUPPLY SYSTB I FIGURE 5-2.

RADIOLOGICALENVIRONMENTALMONITORING SAMPLE LOCATIONS INSIDE OF 10 h1ILE RADIUS

Attachment 1 ANSI 13.10 COMPARISON OFF GAS SYSTEM OG-RIS-609A and B N8407100290-5.4.1 Detection Ca abilities The monitors in this report are off-line units which can contin-uously sample from selected sample points on the off gas system e.g.

inlet to charcoal beds, outlet of the first charcoal bed, inlet to after filters; The monitors are sensitive to both gamma and beta radiation. There are three GM tubes in each of the two chambers.

The sampled gases are first drawn through a particulate filter then a charcoal cartridge and then into the counting chamber to insure noble gases are analyzed and the chambers remain clear of particu-lates and radioiodines. The sampled radioactive gas is then returned to the inlet side of the gas chillers.

5.4.1 .1 The monitors, mounted in 13.1 liter chambers are designed to be sen-sitive to radiation in a range that will relate to Technical Speci-fication limits directed to the off site dose. The following tables will summarize the parameters. See Tables 1 and 2.

5.4.1.2 Not Applicable 5.4.2 Range The requirement of 104 MDA's is exceeded.

5.4. 3 Sensitivity The detector unit is purposefully insensitive to assure the adequate range to cover the Technical Specification limits of activity at the off gas -pretreatment monitor, T.S. 3.11.2.7. See Table 1 Column 7 and Table 2.

g 4 Iq g 4

TABLE 1 Detector Isotope Background Calibration Detection Limits in Cr/cc Installed Factor 1 CF (cpm) (1) cpm/uCi/cc Tech Specs Normal ANSI 13.:10 ANSI 13:10 Sb (2) LLD 4.66 Sb MDA = 1.96 Sb MDA = 1.96 Hs Design MDA CF CF CF OG-601 A 133X 66.6 1.15E + 5 3. 31 E-4 1. 39E-4 8.41E-5 (2) 8.16 OG-601 B 133X 96. 2 1.04E + 5 4.39E-4 1.05E-4 6.62E-4 (2) 9.81 (1) The calibration factor is evaluated at 2 x 104- cpm, estimated set point for an alarm.

(2) Design MDA does not apply for this monitor as other plant factors must be necessary before a cpm/dose relationship is established.

4 I

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TABLE 1 Detector Isotope Background Calibration Detection Limits in Cr/cc Installed Factor 1 CF (cpm) (1) cpm/uCi/cc Tech Specs Normal ANSI 13.:10 ANSI 13:10 Sb (2) LLD 4.66 Sb MDA = 1.96 Sb MDA ~ 1.96 Ns Design NA CF

~ ~

OG-601 A 133X 66 ~ 6 1.15E + 5 3.31E-4 1.39E-4 8.41E-5 (2) 8.16 OG-601 B 133X 96.2 1.04E + 5 4.39E-4 1.05E-4 6.62E-4 (2) 9.81 (1) The calibration factor is evaluated at 2 x 104 cpm, estimated set point for an alarm.

(2) Design NA does not apply for this monitor as other plant factors must be necessary before a cpm/dose relationship is established.

Accuracy The system described in this report was calibrated with 133Xe gas, 100 cc grab samples were taken and analyzed on the ND6620 gamma analyzer system.

In the same calibration transfer and linearity sources were placed on the system. A modification by GE was made on the system after gas calibrations which allowed the voltage reduction to the GM tubes. This also causes a reduction in sensitivity, which is in-cluded in these calculations. As this recalibration, was performed to develop the ratios for the gas calibration to the current trans-fer source calibration, no applicable values for the error, (Rs-Rt)*100/Rt, is available. Over all primary calibration error calculations are included on the Table.

General Electric states the follow accuracies:

Recorder Output No accuracy in cpm stated but Vmax to be set at 1 + 0.002 vol t.

Rate Meter Reading No accuracy in cpm stated in the particular GE manual .

Information from Startup at the time of primary calibration was that the accuracy required is + 20% of scale.

TABLE 2 Monitor Range Sens itivi ty Accuracy (1) Precision 1.96 (Nb/2 RC)1/2 - Rt) lOOX Xn n = number of determinations (1) Heter Scale Ns = ~(R (2) 133Xe in uCi/cc MDL range 137Cs in uCi/cc + error at 1 6 MDL to HDL

• 104 Primary Cal (err of cal est.)

after bkg subtract (Incl. ratio after GE mod)

OG 601A (1) 10 106 Ns = 9.66 cpm 11.7% 1 a Y3 + 0.22%

(2) 8.37E-5 to 8.76 8.03E-5 to 8.08E-l within aeter range OG-601B (1 ) 10 - 106 Ns = 11 .62 cpm 9.2% 1 6 73 + 0.63%

(2) 6.49E-5 to 10.6 7.59E-5 to 7.59E-l within m ter range (1) This calibration will be confirmed periodically with gas grab samples.

8.4.5 Precision The precision for this monitor set is taken from multiple measure-ments on the NNP-2-83 linearity transfer source. The results demonstrate repositioning of the source and are listed on Table 2.

5.4.6 Res onse Time The off gas system upon a Hi Hi Hi radiation alarm closes OG-Y-60, the stroke time for this valve is 4.0 seconds as measured in the system line up test. This time is well within the response time of the rate meter module. The following Table 3 list the response time parameters for these modules.

Table 3 Response Time of GE Log Count Rate Meter*

Decade RC Time Constant Response Time Down Scale Seconds Seconds (2.2 RC) 10 82.17 180.8 100 82.17 180.8 1000 24.9 54.8 104 9.71 21.4 105 2. 49 5.5 106 0.2 0. 44

• This module is a GE Model 145C3284AA Gl-G3 5.4.7.1 Temperature The rate meter and power supplies are located in the main control room which is designed to be habitable under normal conditions; see Technical Specificaion 3/4.7.2, an 85 F (29.4'C) limit. The FSAR limit is 104 F (40 C). For this temperature range, calibration drift would be very small and is typically ignored.

1 Detectors -40'o 75 C Preamplifier similar to pulse preamplifier 0'o 60'C RIS Module 40 F to 120'F, 4.4'C to 48.8'C Rateoeter 4'o 49'C

0

'he 5.4.7. 2 Pressure counting chamber, 13.1 liters, pressure limits was not stated,

'however, the chamber while undergoing calibration was operated from

-15 inches mercury to + 6 psi with no apparent leaks.

5.4.7. 3 Humi di ty The RIS module had a humidity range from 0% to 90% relative. All other components had no statement specifying limits.

Recorder operating limit not specified.

5.4.7.4 Corrosive Atmos here No specification and no corrosive atmosphere expected. Chamber is stainless steel. GM tube holders are aluminum. GM tubes have stainless steel walls.

5.4.7.5 Power Re uirements The detector and preamplifier derive their power from the rate meter module.

The rate meter module requires 120Y of 50 or 60 Hz power. No state-ment about the range of power input was made.

The recorder is a Bailey instrument which requires 115 volts, -10%

to + 5X limitation before DC supplies are affected.

5.4.7.6

~ ~ ~ Electrical Effects This unit has no shielding around the component boards and is ex-ceedingly sensitive to RFI when opened for calibration work. Mhen the module was calibrated an administrative ban on radios was in effect in the control room.

The detectors and preamplifiers are RFI shielded.

Recorder when panel mounted was not affected.

5.4.7.7 Mechanical Effects (Seismic Testing)

Sesmic Class II, design verification only.

I

~ ~

~ g 5.4.8 Radiation Alarms There are two radiation alarms in the rate meter module and one taken from the recorder:

1. Hi Ratemeter Provides for closure of the charcoal bed bypass valve, OG-V-45.

2. Hi Hi Recorder Alerts operators of impending off gas system closure.

3. Hi Hi Hi Ratemeter Isolates the reactor off gas system, closes OG-V-60.

All alarms indicate on the annunciator panel P-604 and initiate a buzzer to sound. The alarm circutry will latch nessitating a manual reset to restore non-trip conditions. Indicator lights for the Hi and Hi Hi Hi are on the RIS module. There is no reset or light on the recorder for the Hi Hi alarm.

5.4.7.9 Failure Indicator A downscale or HV failure light ( INOP) is on the RIS module and will illuminate when tripped, buzzer to sound on P602-A5.

it will also illuminate a light and cause a The downscale/INOP will automatically reset when conditions return to normal.

5.4.7.10 Calibration A. A primary calibration using "33Xe was made by introducing three concentrations of 13~Xe gas into the chamber. The gas was circulated until no activity changes were noted, then two 100 cc gas vial grab samples were taken. The vials were sealed and counted on a HPGe detector and ND6620 analyzer system. The system has been calibrated using gas sources from an NBS Trace-able Laboratory, Analytics Inc., and cross calibrated with vials filled with liquids which were directly compar ed to NBS sources. The range of these calibrations was 5.2% at 133Xe peak of 81 Kev. All samples were multi-counted and each count was at least 50,000 counts to assure counting statistics was not an important factor. The error noted in this report was primarily due to solid source placement early on in the cali-bration. As the precision, indicates, this problem appears to be resolved. See Item C below.

Nhen sufficient activity is present grab samples will be taken periodically and analyzed on the HPGe system, these samples will further confirm the primary calibrations.

B. Transfer sources are high activity 137Cs sources having cali-brations traceable to NBS either by outside laboratory or MNP-2 laboratory analysis. These sources must be placed at some dis-tance from the detectors due to system physical limitations.

~ g ~

C. The detectors are rmunted inside a stainless steel cylinder and are riot removable for calibrations. The transfer sources are positioned over the check source opening and can be reposi-tioned to within a + 0.3% error.

D. The flow rate is measured by a ratemter capable of measuring from 0.3 cfm to 10 cfm. The system flow is 0.5 cfm. The rate meter is repeatable to within 20K of any reading.

E. Check sources, "37Cs, are mounted on top the detector shield these sources are activatyd by a switch on the RIS module. The detector units also have ~37Cs bug (keepalive) sources mounted between the preamplifier and the detectors. These keep alive sources provide the high background activity of the sys-tem and prevented the downscale trips'.

F. Electronic calibration signals are provided for in each rate meter module by:

1. Depressing the alarm button and reading its current setting.

2. Switch to the trip test and observe alarm trips as meter moves upscale.

3. Switch to cal test and observe meter positioning to the calibrate marker.

~ g

'0

Attachment 2 ANSI 13.10 COMPARISON TGB S T-l, FD-RIS-1

,T-2, FD-RIS-2 T-3, FD-RIS-3 5.4.1 Detection Ca ability Turbine Generator Building (TGB) Sump Monitoring Systems utilize NaI gamma scintillation detectors mounted in pipe wells immersed in the sump water to detect a liquid system failure resulting in excessive fission or activation products reaching any of the three non-radio-active TGB sumps. The sump discharges which are normally routed to an evaporative basin via a storm drain system are automatically diverted to the radwaste system for processing upon receipt of an upscale high-high trip. The high-high trip alarm point is set at 50% of the Cs-137 MPC to allow up to a 20% error in calibration and to be consistant with the alarm setpoint methodology for liquid ef-fluents. The response to the other principle nuclide of interest (Co-60) MPC value will present no problem because of the 2 gammas per di sintegration aspect of Co-60. Calculated efficiencies are based on Cs-137 since we are looking for fission or'activation pro-ducts which have leaked into the sumps. Strontium-90 is monitored in the reactor coolant. Off line samples from a composite sampler'o be installed at each sump will be used to verify the adequacy of the calibrations and the in place detector response.

5.4.1.1 Not applicable 5.4.1.2 Detection in Li uid Streams The TBG Sump Monitors are shielded to lower the background countrate from cement structures, etc. in order to achieve a low LLD. The LLD was calculated by using the Technical Specification definition, by using the method typically used in industry and by using the ANSI 13.10 method featuring the RC time constant. All represent the 95%

confidence level.

-1

~ ~

~l

ech 1 Installed Calibration 1.96 B 2R Detector Bk Factor LLD = Cal. Factor I MDA = Cal. Factor MDA = Cal. Factor c m T-1 650 cpm 3.084E8 uCz cc 3.85E-7 uCi/cc 1.65E-7 uCi/cc 4.74E-7 uCi/cc m

T-2 653 cpm 3.234E8 uCi cc 3. 68E-7 uCi/cc 1.58E-7 uCi/cc 4.53E-7 uCi/cc

~cm 689 cpm 3. 219E8 uCi/cc 3.80E-7 uCi/cc 1.63E-7 uCi/cc 4.68E-7 uCi/cc And the corresponding MDL or cpm for the above minimum detectable activity concentrations:

Tech. S ec. Normal ANSI Detector MDL = 4,66 L/Bk MDL = 2 VBk MDL = 1.96 VBk /2RC T-1 119 cpm 50.9 cpm 146 cpm T-2 119 cpm 51.1 cpm 147 cpm 122 cpm 52.5 cpm 151 cpm

5.4. 2 Range The range which should be 104 MDL's is calculated by multiplying each MDL in Section 5.4.1.2 by 104. The resulting values should i be within the detector range of 10 to 107 cpm.

Range Re uirement MDL Basis X 104 Detector Tech. Spec. MDL Normal MDL ANSI MDL 1.19E+6 5.09E+5 1.46E+6 T-2 1.19E+6 5.11E+5 1.47E+6 T-3 1.22E+6 5.25E+5 1.51E+6 All values are within the detector capabilities.

5.4.3 Sensitivity The sensitivities of the TGB sumps are calculated according to the ANSI definition featuring the RC time constant as shown in Section 5.4.1.2 in the tables. The time constant used was 3.5 sec. since this is the time constant for the decade of the background level.

5.4.4

~ ~ Accuracy The accuracy of the 3 TGB sumps was determined in primary liquid calibrations utilizing a sump mock-up barrel. The resulting total error at the 95 confidence level and the detector response to the transfer calibration source against which future calibrations will be compared are shown below.

Primary Gal ibr ation Error Transfer Cal. Res onse

+ 4.15% 1.499E5 cpm/uCi T-2 + 4.50% 1.5929E5 cpm/uCi

+ 5.30% 1.490E5 cpm/uCi The above values are based upon the output of a sealer which takes a signal equivalent (in count rate) to the signal which drives the alarm function.

The KAMAN manual specifies the following ratemeter and recorder accuracies:

Recorder: + 0.'5X of span Ratemeter: + 5%

Meter Reading Accuracy: 1/2 smallest scale division

', 5.4.5 Precision The precision was determined using all available positioning/

counting data points taken from the Cs-137 transfer source counts taken during the primary calibration. The data and results follow.

T-2 T-3 Gross Bk Net Gross Net Gross Bk Net 1 79282 156 79126 84151 89 84062 80096 213 79883 2 79402 156 79246 83907 89 83818 t 77589 94 77495 78958 111 78847 84252 117 84135 77176 77020 4 79515 111 79404 84522 117 84405 I 79982 259 79723 Z= I 316623I 336420I 31412ll mean = 79156 mean = 84105 mean = I 78530 I

std. dev. = 203.7ll std. dev. = 209.24( etd. dev. = I 1285.031 I

X error = I 0.26K I X error = I 0.25X I X error = I 1.64K

. 4.~ ~T' All three precision errors are within + 10K The response time is adequate to achieve the required accuracy as demonstrated in other sections of'his report where the RC time con-stant was used. Since no delay circuits or devices are encorporated into our electronic circuits after the log ratemeter the nominal value of'.2 time constants is easily met.

From the KAMAN manual, the response time f'r given signal changes and the 2.2 time constants values are shown below.

Response Time Si al Chan e RC Time Constant (2.2) (RC) 10 102 12 sec. 26.4 sec.

10 103 3.5 sec. 7,7 sec 10 - 104 1.0 sec. 2.2 sec.,

10 - 105 0.1 sec. 0.22 sec.

10 - 106 O.l sec. 0.22 sec.

10 107 O.l sec. 0.22 sec.

~

I

~ ~

The recorder, power supply and ratem ter are located in the.Radwaste Control Room which is designed for human habitability under normal and analyzed abnormal conditions and which will never exceed 140'F (60'C). The ambient temperature at the detectors which are located in pipe wells with air space between the pipe walls and the detector would be very unlikely to exceed 140'F. The following information was taken from the KANAM manual:

emperature Effect E ui ment 0 eratin Limits Based on 80'F Midpoint IMo. 7723 Recorderl 0~ to 140'F + 0.2X Span for + 40~F IBailey 7000 AC/DCI + 0.5X DC for + 40'F Power Supply 0'o 140'F + 1.0X AC for + 40'F Log Count + 5X over range (total Ratemeter 0 to 60<C error all effects)

Gamma Scintil- Cal. drift would be very lation Detector 32oF to 140~F small and is typically ignored, energy cal. would change but does not effect function.

5.4.7.2 Pressure The TGB sump radiation monitoring components are open to building atmosphere; therefore pressure response is not applicable.

5.4.7.3 ~Huaidit The components of the TGB sump radiation monitoring system are sub-ject to environmental conditions dictated by the TGB HVAC system and so humidity should not significantly effect their operation, how-ever, the KAMAN manual provides some information which follows:

Lo Count Ratem ter Operating limits 0 - 95K relative humidity Gamma Scintillation Detector No operating limits given, but these are assumed to be the same as the storage limits given "by Kaman Instrumentation, of 0 - 95K relative humidity.

t l ~

5.4.7.4 Other Environmental Effects Not applicable and none expected.

5.4.7.5

~ ~ ~ Power Re uirements The detector, including preamp, ratemeter and recorder are powered from instrument buses in the Radwaste Control Room. The power supply is stabilized and variations of 15X will not be seen.

Model 7723 Recorder DC Voltage Effect: + 0.2X of span for

+ 2 volt change from 24V DC Baile 7000 AC/DC Power Su 1 Volta e variation of -10X, +5X results in output variation of

+ 0.5X DC voltage and -12X, +6X AC voltage at 50X load Fre uenc variation of + 1 Hz results in + 0.2X output frequency variation. he input voltage is 120V AC X 230V AC at 50/60 Hz. The operating voltage is -15X h +10X of input. The operating frequency limit is + 2X of input. (Normal frequency range inputs are + 1 Hz)

Lo Count Ratem ter Operating Voltage Range 90 to 130V AC at 50 to 60 Hz Gamma Scintillation Detector Operating Limits: +12V + 0.5V OC 8 lma

-12V + 0.5V OC 8 1 ma 600 to 1100V OC 8 1 ma 5.4.7.6 Electrical Effects, i.e. RF and Microwave Interference This has been a problem especially when instrument racks are pulled out. The use of radios is being controlled administratively to avoid the problem.

5.4.7.7 Mechanical Effects The TGB sump monitoring system is not seismic I qualified, however, the system would divert any flows to radwaste for processing in case of system failure. Therefore its function is maintained although not required by exception.

V

~ ~

5.4.8 The ratemeter is equipped with two upscale alarms (Hi and Hi Hi) which can be set at any point over the range of the instrument.

These alarms are latching type and must be manually reset. The alarms illuminate a light (Hi amber, Hi Hi red) at the ratemeter and open a solenoid which causes a trouble light on an annunciator panel to illuminate and a buzzer to sound.

The Hi h Hi Hi alarm setpoints can be adjusted externally without removing the instrument from service.

5.4.9 Failure Alarm The ratemeter provides a latching alarm in case of power failure, HV below the HV INOP setpoint, or counting rate below the setpoint value.

5.4.10 Calibration aO Primary calibrations were performed on the TGB sump radiation monitoring systems using a 55 gal. barrel mock-up of the sump geometry. A detector well in the barrel corresponds to the pipe well in. the sumps. An NBS traceable liquid solution of.

Cs-137 was continually circulated through the mock-up during the calibration and a "stand pipe" apparatus was used to insure that no air was trapped within the system.

b. Transfer standards (Cs-137) were counted during the primary calibrations to establish a baseline for use in subsequent periodic calibrations.

c. Source to detector geometry for the transfer standards is main-tained by by the use of, and insertion in, a standard KAMAN calibrator.

d. The .transfer source is 1 inch in diameter and is positioned directly below the l-l/2" x 1" NaI detector.

e. A remotely actuated check source is provided (Cs-137).

Calibrated electrical signals are provided and can be ex-ternally inputted prior to ratemeter amplifier and discrimi-nator circuits.

FSAR REQUIREMENTS 11.5.1.2.2 Systems Required for Plant Operation

a. Provide continuous indication of radiation levels in the Main Control Room.

Yes, but in Radwaste Control Room

b. Provide warning of increasing radiation levels indicative of abnormal conditions by alarm annunciation.

Yes

c. Insofar as practical, provide self'-monitoring of components to the extent that power failure or component malfunction causes annuncia-tion and, for systems initiating protective action, channel trip.

Yes - failure alarm for low count rate, low HV and loss of power

d. Monitor a sample representative of the bulk stream or volume.

Yes, monitor TGB sump liquids

e. Have provisions f'r calibration, function and instrumentation checks.

Yes - 3 cal. check buttons for ratemeter an external signal can be put into the ratemeter

- Cs-137 check source

f. Have sensitivities and ranges compatible with anticipated radiation levels and technical specification 1'mits.

Yes

g. Register full scale output if radiation detection exceeds full scale.

Probably not, but alarm latches

- change FSAR

APPLICABLE GENERAL DESIGN CRITERIA OF 10CFR50 APPENDIX A

13. erable under ex ected normal h abnormal conditions' Yes

60. (1) Control radioactive ef fluent2 (2) Is ade uate hold u volume provided?

(1) Yes, by closing release path if abnormal rad levels detected.

(2) Yes, the sump volume serves as a hold up volume. The hold up volume is not really needed since the release path is isolated on High High Alarm.

64. Monitorin Rad. Releases The TGB sump radiation monitoring system monitors the potential release path of the TGB non-rad. floor drains and automatically diverts flow to the radwaste systems on High High Alarm. It whould operate under accident conditions but is not required since the release pathway can be manually diverted.

4 ~ ~

Attachment 3 ANSI 13.10 COMPARISON Li uid Effluent Monitorin Systems Residual Heat Exchange RHR Loop A Residual Heat Exchange RHR Loop B Reactor Closed Cooling Liquid Effluent FDR RCC'adwaste 5.4.1 Detection Capabilities .

The liquid monitors in this report are off line units which contin-uously sample, or sample when fluid is in the line, a portion of the liquid stream for gamma emitting isotopes. The liquids are pumped into a marinelli type stainless steel chamber, which is four pi shielded with lead, having a 2" x 2" NaI(tl) detector for a gamma sensor; the liquid is then returned to the original stream.

5.4.1.1 Not appl i cable 5.4.1.2 Detection in Li uid Streams The monitor's ability to detect small quantities of radiation is dependent upon the detector size, liquid chamber size and adequate shiel ding. The following table summarizes the minimum detection parameters. See Table 1 5.4.2

~ ~ ~Ran e The requirem nt is exceeded, see Table 2.

5.4.3 Sensi tivity The sensitivity is noted as uCi/ml in Column 7, Table 1; also in Table 2.

5,4,4 Accuracy The systems described in this report were calibrated with liquid solutions. The liquid solution results and the transfer and linear-ity sources were compared and tabulated to form the primary calibra-tion package. Only one monitor required additional work after the primary calibration, this was the RHR Loop A, SM-RE-4 detector.

Upon completion of the task the unit was recal ibrated with the NBS traceable transfer and a set of linearity sources. The result was

+2.32% using the following relationship Rr -Rt x 100 percent t

ANSI 13.10 arison: Table 1 Detector RHR Loop A SW-RE-4 Isotope 137Cs 60Co(3)

Background

(Installed) cps 1.6 Calibrgtfon factor<1>,CF cps/uCi/ml 2.98 E+6 4.97 E+6 LLO=

~

Tech. Spec.

4.66 1.2 E-7 7.2 E-8 Sb Detection Limits in uCi/ml MDA=

~ ~

Nor mal 1.96 Sb 5.1 E-8 ANSI 13.10 MDA=

1.96 6.0 E-8 N

ANSI 13.10 Design NDA

4. E-7 3.1 E-8 3.6 E-8. 3. E-7 RHR Loop B 137Cs 1.9 3.09 E+6 1.2 E-7 5.0 E-8 6.6 E-8 4. E-7 SW-RE-5 60Co 5.16 E+6 7.2 E-8 3.0 E-8 4.0 E-8 3. E-7 RCC-RE-7 137Cs 3.8 3.69 E+6 1.6 E-7 6.7 E-8 8.6 E-8 4. E-7 60Co 6.16 E+6 9.6 E-8 4.0 E-8 5.2 E-8 3. E-7 FDR-RE-6 137Cs 5.6 2.92 E+6 2.5 E-7 1.0 E-8 1.4 E-7 4. E-7 60Co 4.28 E+6 1.5 E-8 6.2 E-8 8.4 E-8 3. E-7 Notes: l. Calibration factor is calculated at the count rate of the transfer source.

2. Sb is calculated at the 95% confidence level of attaining the meter reading, i.e. Sb = (Bckgnd/3 RC)1/2

3. The Colbalt 60 results are a constant factor of 1.67 for a 2 x 2 NaI(4L) detector versus Ceasium 137.

Information via Har shaw Inc. additional information indicates the factor could be 1.88, Kaman Sciences Corporation, the more conservative factor of 1.67 was used.

Accur acy (Continued)

The transfer source at the time of manufacture was 0.092 uCi + 5% at the 95% confidence level.

The accuracies of the ratemeters and recorder s output as specified by General Electric as as follows:

Recorder Output + 2% of Equivalent linear full scale Ratemeter + 5% in the bottom decade Precision The precision for this monitor is stated on Table 2 from results of the primary calibration. The precision of these units is within the

+ 3% as required by the approved calibration procedures. The indi-cation is that a + 10%. precision error can be met or exceeded by these liquid monitors.

Response Time The FDR-RE-6 monitor provides signals for valve closure, the others in this report provide trip signals to the alarm annunciator s. The FDR-RE-6 controlled valves will complete their stroke from open to fully closed in 4.2 seconds, as measured in the system lineup test.

This time is well within the response time of the ratemeter modules. The following table, Table 3, lists the response time parameters for these modules.

ANSI 13.10 parison: Table 2 Men 5 tor Range Sensi tivity Accuracy Precision (1) Mefer Scale N5 = 1 96 L0b/2 RC)l/2 R - R Xn n = number of (2)>>ICs in uCi/ml MDL range l~igs from x 100% determinations (3) Co in uCi/ml MDL to MDL 10~ Primary Cal = N/A + X error at 1 6 RHR Loop A (1) 10-1 to 106 cps N5 = 0.198 cps 1.315 - 1.285 x 100% 74 + 1.02%

SW-RE-4 (2) 3.10E-8 to 3.53E-1 6.02E-8 to 6.02E-4 uCi/ml (3) 1.86E-8 to 2.11E-1 within meter range = 2.3X RHR Loop B (1) 10-1 to 106 cps N5 = 0.217 cps N/A X3 + 0.53%

SW-RE-5 (2) 2.67E-8 to 3.65E-l 6.64E-8 to 6.64E-4 uCi/ml (3) 1.60E-8 to 2.18E-l within meter range RCC-RE-7 (1) 10-1 to 106 cps N5 = 0.306 cps N/A X3 + 0.85K (2) 2.83E-8 to 3.64E-l 8.62E-8 to 8.62E-4 uCi/ml (3) 1.69E-8 to 1.58E-1 within meter range RCC-RE-6 (1) 10-" to 106 cps N5 = 0.372 cps N/A 73 + 0.41%

(2) 3.83E-8 to 3.18E-l 1.41E-7 to 1.41E-3 uCi/ml (3) 2.30E-8 to 1.91E-1 within meter range

Table 3: Response Time of GE Process Radiation Monitor*

Decade RC Time Constant (seconds) Response Time (cps) Upscale Downscale (seconds) 2.2 x RC 10-1 1 8 .8 78 172 100 2.3 78 172 101 0. 24 78 172 1.02 0. 02 78 172 103 0. 02 3.0 6.6 104 0.02 0.3 0.66 105 0.02 0.03 0.066 2.6 x 105 0.02 0.001 0.0025

• Note: This ratemeter module is is a GE model 368X103AAGl common 8 G2.

to the monitors in this report, it 4.4.1.1 ~Tt The ratemeters and power supplies are located in the Main Control Room which is designed to be habitable under normal conditions; see Technical Specification 3/4.7.2, an 85'F (29.4'C) limit. The FSAR limit is 104'F (40'C). For this temperature range, temperature cal-ibration drift would be very small and is typically ignored.

Detectors and Pre-Am lifiers

a. The IJaI(tl) scintallator will in sensitivity from 0'o 60'C.

undergo no change

b. The photomultiplier tube, P.M., can operate from -30 C to 50 C (122 F) normally, but can operate from -30 C to 80'C (176'F) for short periods.

c. The preamplifier, mounted near detector and skid, has tempera-ture rating limits of 0 to 60 C. The ideal opertion is at 25 C. The temperature drift factor is 0.3X/'C and a + 1% per 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> of operation can occur.

The ratemter and power supply are in the same drawer, the tempera-ture range of the combined unit is from 5 to 50'C (122 F).

5.4.7.2 Pressure All the liquid monitors are mounted in a Marinelli type stainless steel chamber. The 2.4 liter chamber used for RHR SM-RE-4 and 5 is rated at 35 psi while the 3 liter chamber used for the RCC-RE-7 and FDR-RE-6 is rated at 225 psig. All other components are designed to operate at ambient atmospheric pressures.

5.4.7.3 Humi di ty The detector assembly can operate from 0 to 95% humidity. The rate-meter module can operate from 20 to 90K relative humidity. It oper-ates best'at 50K relative humidity. The preamplifier operates from 20 to 90K relative humidity.

5.4.7.4 Corrosive Atmos here No specification and no corrosive atmospheric or liquid conditions expected. The liquid chamber is stainless steel.

5.4.7.5 Power Re uirements The detector and preamplifier derive their power from the ratemeter module.

The ratem ter module requires 26.5 volts D.C. and can operate with-out degradation of readings and alarms with an input variation from 19 to 29.5 volts D.C.

5.4;7.6 Electrical Effects The ratemeter drawer assembly has each of its component boards mounted inside a metal shield. No RFI was noted during the pre-operational test which involved keying a hand held 4 watt trans-mitter near the ratemeter drawer.

5.4.7.7

~ ~ ~ Mechanical Effects (Seismic Testing)

Not required on this equipment as it is Class II.

5.4.7.8 Radiation Alarms The ratem ter is equipped with two upscale alarms Hi and Hi-Hi which can be set at any point over the range of the instruments. The cir-cuitry latches the alarm even though the detector input may have returned to normal; the alarms must be manually reset. Indicator lights alarm at the rateoeter and causes a light on the annunciator panel 'to turn on along with a buzzer to sound, P602-A5.

5.4.9 Failure Indi cators A downscale or H.V. failure light (INOP) is on each ratemeter and will illuminate when tripped. A corresponding light will indicate on a panel on the control console and a buzzer will sound. This circuit will self reset when the voltages return to normal.

. ~ 5.4.10 Calibration a0 Primary Solutions The primary solutions, 137Cs, were made from uncalibrated source material. Aliquots of,the solution were taken and com-pared directly with NBS reference standards, 137Cs, after assuring the geometries of the samples were identical. During the calibration the solutions were pumped and circulated con-tinuously in a closed system; three liquid samples were with-drawn into glass'mpoules and then flame sealed. The liquid samples were counted along with identical liquid samples, in flam sealed vials also, that were directly traceable to NBS.

The calibration error ranged from 5.9% downward with the bulk of the errors about 4%; this error was at the 95% confidence level.

b. The transfer calibration sources are 137Cs sources supplied by Kaman Sciences Corporation. They are disk sources designed to fit into a portable calibrator. The 137Cs sources were calibrated by ICN Inc. on an instrument calibrated with NBS traceable sources. Their calibration error was stated to be +

5% at 2r.

Linearity sources are 1338a, provided by Kaman Instrumentation.

C. Cons tant Geometry The detector rests against the bottom of the well and can be repositioned within the detection of the counting statistics, i.e. better than 0.3X. ~

The portable shielded calibrator with source drawer assembly has demonstrated repeatability of better than 0.3%.

d. The flow rate device is a rotoaeter capable of measuring from 0.2 to 6 gpm on the RHR SM-RE-5 and 5 with an error of + 20% at any reading. The flowmeters on the RCC-RE-7 and FDR-RE-6 measure from 0.5 to 5 gpm with an error of + 10X on an individual r eading.

e. Check sources, 137Cs, are mounted only on RCC-RE-7 and FDR-RE-6 and are solenoid activated devices The RHR SM-RE-4 and 5 are manually activated by sliding a '~7Cs source mounted in a rod in a port on the detector shield.

Electronic calibration signals are provided for in each rate-me)er module. Two specific pulse rates are generated 10 and 10 pulses per second for a rateoeter check. Also the oscil-lator sweeps the range of the instrument for alarm trip test.

c~ 4

~

a

Attachment 4 ANSI 13.10 REVIEW MAIN CONTROL ROON FRESH AIR INTAKE MONITORS (MOA's)

EPN's:

SNPLE RACK DETECTOR RATEMETER RECORDER MOA'-SR-18A WOA-RE-31A MOA-R IS-31 A WOA-RR-31 MOA-SR-18B MOA-RE-31B MOA-RIS-31B WOA-RR-32 MOA-SR-19A WOA-RE-32A WOA-R IS-32A MOA-RR-31 WOA-SR-19B MOA-RE-32B WOA-R IS-32B WOA-RR-32 General System Descri tion The "Main Control Room Fresh Air Intake Monitors" (also called remote air in-take monitor s or WOA's) are four identical off line air monitoring systems.

These instruments monitor the concentration of radioactivity in the air sup-plied to the Control Room in accident conditions. The major contributions to the activity is expected to be Xe-133 and Kr-85.

Normally, the Control Room obtains intake air (1000 cfm) from a local intake and 21,000 cfm is recirculated. In addition to the local intake there are two remote air intakes that normally do not supply air to the Control Room. One of these intakes is located 518 feet NW of the Reactor Building vent and the other is 404 feet SE. A purge flow of 150 cfm is maintained in each remote air supply duct. The purge is exhausted by the WEA system.

Upon r ecei pt of a F, A or Z signal, the dampers in the local intake close and the dampers in both remote air supply ducts open. A total of 1000 cfm is then drawn from either or both remote air intakes. The air from each intake is monitored for radioactivity by redundant air monitoring systems (WOA's).

After being monitored, each stream passes through separate HEPA and charcoal filtering system. After the filtration system the air becomes the make-up air for the Control Room.

Upon receipt of a Hi Hi radiation alarm from the associated WOA monitor, the dampers in the affected remote air supply duct close. However, the dampers are interlocked so that one remote air supply remains open even in the highly unlikely event that a Hi Hi alarm is received on both channels.

The sample for each monitor (2 per supply duct) is obtained via a 1/2 inch diameter probe centered in and pointed upstream in the 12 inch supply duct.

The sample probe is upstream of the purge exhaust which in turn is upstream of the dampers. The sample passes through a chamber containing a beta detector.

The sample chamber, which contains 2. 2 liters of sample, and detector are shielded with 3 inches of lead. The sample then passes through a 0 to 6 SCFM ratemeter which has low flow detection/alarm capabilities, a vacuum pump and back to the duct. The sample flow is typically 2 to 3 cfm.

'The detector is a 2 inch dia. by 30 mil thick NE 102 scintillator optically coupled t'o a photo-multiplier tube and followed by a preamplifier. This detector is immersed in the gaseous sample. The signal is sent to a 6 decade (10 to 107 cpm) log ratemeter and recorder which are located in the Main Control Room. The ratemeter provides power to the detector, displays the counting rate, and provides alarm functions. The ratemeter has three internal calibration points and provisions to input a calibrated signal. An alarm test, function is also provided. A 1 uCi Cl-36 check source is provided at the detector to check overall system response. The check source is controlled from the ratemeter.

The WOA monitors are seismic I, guality Class I qualified and are powered by Class lE power. Operability requirements are given in Technical Specification 3.3.7.1.

Com arison of the Remote Air Intake Monitors (WOA's) to ANSI 13.10 "Standards o er ormance 5.4.1 Detection Ca abilities The WOA Monitoring System is composed of 4 identical off line air monitoring systems wich two divisionally separated monitors on each of the two remote air intake supply ducts. This system monitors the concentration of radioactivity in the air supplied to the Control Room in accident conditions. The major contributions to the radio-activity are expected to be Xe-133 and Kr-85 which are beta emitters.

The sample for each of the monitors is obtained via a 1/2 inch diameter probe and sample line. The sample probe is located on the center line of the 12 inch remote air supply duct served by that monitor and faces upstream. The sample probe is located upstream of the redundant isolation dampers. Typically the sample flow is 2 to 3 cfm.

The detector consists of a 2 inch by 30 mil thick NE102 plastic scintillator optically coupled to a PM tube and followed by a preamp. The detector is immersed in a shielded chamber containing 2.2 liters of sample gas. Three inches of lead shielding are provided to decrease the background from the ambient radiation in accident conditions. This type and thickness of phosphor maximizes the response to. beta radiation while minimizing the response to gamma radiation, providing optimum detection capabilities in the analyzed accident environment.

5.4.1.1

~ ~ ~ Detection in Gaseious Streams Detection of Xe-133 and/or Kr-85 at a concentration of 1-3 E-6 uCi/ml, per letter to the NRC, will provide adequate protec-tion to Control Room personnel because the particulates and other radio nucl ides with more restrictive limits will be filtered out of the air stream.

The primary calibration was made by the vendor, Kaman Instrumenta-tion. For Xe-133 the counting efficiency ranged from 4. 29E7 cpm/uCi/cc to 5.20E7 cpm/uCi/cc as the activity of the sample varied from 7.511E-2 to 1.085E-5 uCi/cc. The slope using these points (average of 2 measurements) is 0.998. At the time of the primary calibration, the counting efficiency for the transfer standard source was established as 9.83E5 cpm/uCi. of Sr-90. The calibration made in Jan. - Feb. 1984 reestablished the counting efficiency of the transfer standard source for these 4 monitors as 9.44E5 cpm/uCi

+ 3X. The calibration curve for these monitors was adjusted by the ratio of the transfer source counting efficiency - 0.960. The slope of the counting rate v.s. activity agreed well with the slope obtained on the primary calibration. Therefore, this factor is applicable across the range of calibration. The same factor would apply to the primary Kr-85 calibration data.

The LLDs at the 95% confidence level have been calculated using the Technical Specification method, the method typically used in in-dustry and the method given in ANSI 13.10. The results are tabu-lated in both cpm and uCi/ml Xe-133 below. The background is based on a 10 minute count for each monitor. The efficiency factor used is average factor obtained during the primary calibration at the lowest counting rate adjusted by the facto obtained during the recalibration i.e. (5.068E7) (0.960) = 4.87E7 cpm/uCi/cc.

I Ins tal 1 ed I Cal ibrati on ANSI 13.10 I Bkg t Factor Tech. Spec. Typical Monitorl (c m) l(c m/uCi/cc) tLLD = 4.66 ~g IMDA = 1.96 v%g 1.96 31A 15 4. 87E7 18.0 cpm 7.6 cpm 12.0 cpm

3. 7E-7 uCi/cc 1.5E-7 uCi/cc 2.5E-7 uCi/cc 31B 21 4.87E7 24.5 cpm 9.0 cpm 14.2 cpm 5.0E-7 uCi/cc 1.8E-7 uCi/cc 2.9E-7 uCi/cc 32A 4. 87E7 13.2 cpm 5.5 cpm 8.8 cpm 2.7E-7 uCi/cc 1.1E-7 uCi/cc 1.8E-7 uCi/cc 32B 16 4. 87E7 18.64 cpm 7.8 cpm 12.4 cpm 3.8E-7 uCi/cc 1.6E-7 uCi/cc 2.5E-7 uCi/cc Detection in Liquid Streams

~ ~ ~ ~

5. 4.1.

~ ~ ~ 2

~

Not applicable 5.4.2 Range The range which should be 104 MD's 10".

calculated by multiplying each MDL in section 5.4.1.1 by The resulting values should be within the instrument range of 10 to 1E7 cpm.

The maximum MLD in section 5.4.1.1 is 25 cpm or 5.0E-6 uCi/cc. The counti ng rate for 104 MDLs can be approximated by:

(5. OE-7 uCi/cc)(E4)(5. 20E7 cpm/uCi/cc) + BKg - 2.6E5 cpm This is within the range of the instrument.

Sensiti vity g

The sensitivity as given by NS = 1.96 VZE was calculated and tab-ulated in Section 5.4.1.1. A time constant of 12 seconds was used for sensitivity calculations.

Accuracy The accuracy of the 4 BOA monitors is tabulated below using the formula X error Rt - Rr (100)

Rt = Counting rate of the transfer standard established by vendor at the time primary calibration = 9.83E5 cpm/uCi.

Counting rate of the transfer standard when field cal-ibrated. Rr is the average of the two counts, except for MOA-32A which is the average of 3 counts, taken on a calibrated sealer.

Monitor Error 31A 9.35E5 4.9 31B 9.44E5 4.0 32A 9.70E5 1.3 32B 9. 2355 5.1 7=9.43E5 7=4.1 cr =1.99E4 6'2.0

, Precision The precision was determined using the net counting rate of the transfer standard as neasured by the sealer. In most cases only two counts were available.

31 A 81921 31B 8.2408E4 81666 8.2734E4 7=8.18E4 7=8. 26E4 132 163

l. 9Q= 259 1. 96'= 31 9 1.96 cr = 0.4%

7 7 8.45E4 cpm 32B 80555 cpm 8.53E4 cpm 80999 cpm 8.48E4 cpm 7=8.49E4 7=8.08E4

<=3. 30E2 6 =3.84E2

1. 96'"=6. 60E2 1. 966"=5. 57E2 19660 1 .966 0 7

The precision is within + 10% at the 95% confidence level.

~RTi With a time constant of 12 seconds for the first decade and a NDA of less than 2E-7 uCi/ml, the monitors will easily see required detec-tion level of 4.0E-6 uCi/cc.

5.4.7.1 Tem erature The ratemeter, recorder, and power supply are located in the Main Control Room. The Control Room is designed for human habitability under normal and analyzed abnormal conditions. The temperature in the Control Room will not exceed 104'F.

Ratemeter Per vendor specification, + 5% change over a temperature'ange of 0-60 C (0-140'F).

Recorder Per vendor specification, the normal operating range is 4-49 C (40-120'F). The operating limit is 60 C (0-140'F). The temp-eratures effect is 0.2% of span for 40 F to 120 F.

Power Su ly (for recorder)

Per vendor specifications operating range and limits are the same as for the recorder. The temperature effects are DC + 0.5% and AC + 1%

for a + 40 F based on 80'F midpoint operating range.

Detector Per vender specifications the normal operating temperature is 0-60'C (32-140'F). The effect on the calibration is not defined.

Under normal conditions, the ambient temperature at the sample rack is maintained for human comfort. Under extreme accident conditions the temperatures might increase to the upper limit of human oc-cupancy (120 F). Experience indicates that calibration drift (counting efficiency) over this range is probably negligible.

The temperature of the air stream being monitored could conceivably reach the same extremes as the outside air (-27 F to 115'F). The upper temperature is within the specification. The lower tempera-ture's outside the specification but is expected to have essential-ly no effect on the system.

Blower/Motor/Rotameter The range of temperatures will have minimal effect rotameter calibration changes with the density of air.

if any. The 5.4.7. 2 Pressure Except for the vacuum head created by drawing the sample, the range of pressure variation will be the same as outside air.

5.4.7.3 Humi di ty The environmental conditions at the sample rack are dictated by the Radwaste Buil ding Ventilation System. The humidity even in accident conditions should not be extreme. The environmental conditions in the Control Room where the ratemeter and recorder are located is controlled to within a narrow range. Kaman provides the following information.

Detector (scintillator/preamp) - Vendor gives no operati ng specifi-

~ca ions. Since storage in a humidity range of D-ggg is approved by vendor, operation in this range of humidities should be permis-sible. The calibration and accuracy will not be affected.

Other com onents at skid - The motor, blower, flow meter etc. should no e a ecte y um> imp.

Ratemeter/Recorder - No effect expected because of the controlled a osp ere ~n e Control Room.

5.4.7.4 Other Environmental Effects There are no anticipated environmental conditions, other than those previously discussed, that will effect these monitors.

5.4.7.5 Power Requirements, i.e., Voltage and frequency variations of + 15%

should not result in readout variations in excess of + 5%.

The detector, including preamp, ratemeter and recorder are powered from instrument power buses in the Control Room. This power supply is stabilized and variations of 15% will not be seen.

Per Kaman specs: for the ratemeter 90 - 130 VAC, 50-60 Hz is ac-ceptable. Kaman Spec for the recorder power supply and recorder indicate that the recorder would easily meet a -10K +5% variation in power supply.

Motor/pump - no significant effect.

5.4.7.6 Electrical Effects This has been a problem. Kaman Instrumentation specs indicate that the power supply for the recorder is sensitive to RF. Experience indicates that the system is sensitive to RF generated at either the sample rack or the ratemeter, locations. Use of radios is being controlled administratively to eliminate this problem.

5.4.7.7 Mechanical Effects The WOAs are qualified to seismic I standards. The detectors presently installed are not seismic I qualified.

5.4.8 Radiation Alarms The ratemeter is equipped with two upscale alarms (Hi and Hi Hi) which can be set at any point over the range of the instrument.

These alarms are latching type and must. be manually reset. The alarms illuminate a light at the ratemeter and open a relay which causes a trouble light on an annunciator panel to illuminate and a buzzer to sound. Opening of the relay on Hi Hi alarm causes the Control Room Ventilation System to switch to the emergency mode'of operation and also causes the dampers in the associated remote air intake duct to close.

The downscale, Hi and Hi Hi alarms are reset and the setpoint can be checked from the face of the ratemeter.

The Hi and Hi Hi alarm points can be adjusted at the meter face.

The low high voltage alarm and the downscale alarm setpoints are adjusted internally but the instrument does not have to be removed from service to adjust them.

5.4.9 Failure Alarm The ratemeter provides a latching alarm in case of power failure, HV below the HVINOP setpoint, or counting rate below a setpoint value.

5.4.10 Cal ibrati on A. The primary calibration of the 4 WOA monitors was made by the vendor, Kaman Instrumentation. The primary calibration using Xe-133 and Kr-85 gas was related to Kaman's secondard standard source and WNP's "transfer standard" source and 3 "linearity" sources. Kaman's secondary standard and the transfer standard are solid Sr-90 sources about 1 inch in diameter and at the time of calibration about 0.09 uCi. The linearity sources are identical to Kaman's secondary standard and the transfer stan-dard and had activities of about 0.5, and 0.005 uCi of Sr-90.

The sources were precisely positioned under the detector using a "calibrator" (shielded calibration jig). The calibrator was also furnished to WNP-2 to assure reproducible geometry when making transfer calibrations. All sources, including Xe-133 and Kr-85 gas, are NBS traceable.

The primary calibration consisted of exposing a detector to three different concentrations of Xe-133 and Kr-85 in the geo-metry actually used. Kaman 's secondary standard, the transfer standard and the linearity sources were counted in the calib-rator. The counting efficiency for each isotope of noble gas was established over the range of concentrations used. This counting efficiency is related to the counting rate obtained on the secondary standard and transfer standard sources. The remainder of the detectors are cross calibrated to the transfer standard and Kaman's secondary standard sources.

FSAR Table 11.5-1 requires these monitors to be calibrated to Xe-133. The primary calibration covered the expected range of acti vity.

B. The primary calibration source is related to a transfer stan-dard and linearity sources which are NBS traceable. The lin-earity sources are used to assure that instrument responds properly over the r ange of activity of interest.

C. The transfer standard and the linearity sources are small (about 1 inch diameter) compared to the detector (about 2 inches diameter). However, the source to detector geometry is precisely maintained by using the calibrator. Using the cali-brator, the error due to source positioning is negligible. An exception to the requirement for the transfer standard to the same surface area as the detector was requested.

Since this is a noble gas monitor, the loss in the sample line is nonexistent.

The flow rate measuring device (rotameter) was calibrated in September 1983.

F. A remotely actuated 1 uCi Cl-36 check source is provided to check the overall response of the monitor.

G. Calibrated electrical pulses are provided by the ratemeter and externally generated signals can be inputted at the ratemeter.

In both cases, the signals are inputted downstream of the gain and discriminator circuits in the ratemeter.

~ e Comparison of MOAs to FSAR 'll.5.1. 2;1 (Systems Required for Safety)

a. Mithstand the effect of natural phenomena (e.g., earthquakes) without loss of capability to perform their functions.

o WOA systems were designed to Seismic I and gC I requirements.

o, Presently, the detec'tors have not been qualified detectors are on order.

as Seismic I. New

b. Perform its intended safety function in the environment resulting from normal and postulated accident conditions.

The WOAs are normally in an environment controlled for human comfort and is therefore no problem.

During postulated accident conditions the pressure, temperature and humidity may increase slightly but should not exceed the upper range of human comfort.

Although there will be no significant sources of radiation in the hallway where the sample racks are located, the radiation level in the Reactor Building will contribute to the background of the instruments. Based on data given in the Shielding Evaluation Report (SER), the major contributor s to the dose rate in the Reactor Building are:

o Airborne concentration which contributes lE3 R/hr max or 2E5 cumu-lative integrated dose (CIND).

o The RHR pumps located about 15 feet from the wall on the 422'evel.

o A horizontal run of 6" RCIC piping located about 10'rom the wall.

o A vertical run of 6" RCIC piping about 2 feet from the wall. This 6" vertical pipe is near WOA-SR-18B.

The maximum dose to vital equipment on the 441'evel of the Reactor Building is 1.7E6 Rad CIND. Apparently this maximum does is at and from the 6" vertical RCIC line.

Using the method given in Appendix C of the SER the maximum does rate at WOA-SR-18B can be approximated as follows. The dose rate at the other MOA sample racks will be lower. For ease of calculation, the total dose and dose rates will be &+modeled as the standard 8" pipes.

Total dose from std pipe = 1E5 Rads CIND. Maximum dose rate at 8 feet from standard pipe is 3E3 Rads/hr.

1.7E6 = 17 p1pee From SER Figure C-13 dose rate from 17 pipes through Reactor Building wall (40" concrete) is (17)(0.28 R/hr) = 5 R/hr Attenuation through 3" (7.67 cm) of Pb is 0.0003, there- fore dose rate in shield is (5E3 mR/hr)(0.0003) = 1.5 mR/hr gamma plus some auger electrons.

This detector (30 mil thick NE 102) has a minimal ( 0.4% to 100 Kev X-rays) response to gamma radiation. On a typical GM type detector the counting rate in a 1.5 mR/hr field would be about 3E3 cpm. The counting rate on this detector would be lower by at least a factor of 3.

c. Meet the reliability, testability, independence and failure mode require-ments of engineered safety features.

Rel iabil i ty:

o Redundant monitors on each air supply.

Tes tab ili ty:

o Any one unit can be completely isolated for testing, calibration and/or maintenance.

Independence:

o Any one unit can be isolated.

o Loss of two units places the Control Room Yentilation System in safe mode.

o Powered by divisionally separated class 1E power.

o There are no shared components in any of the monitoring systems.

Failure Mode:

o Alarms 5 annunciates on downscale reading, loss of power, or HV below a specified setpoint.

d. Provide continuous output on Control Room panels.

o Dial, recorder and annunciation in the Main Control Room.

o MOAs input into TDAS.

e. Permit checking of the operational availability of each channel during reactor operation with provision for calibration function and instrument check.

o Can isolate any one unit.

o Has "Ext. Calib." for input of calibrated pulses at the count rate meters.

o Has check source to check the overall system response.

.o Has alarm test; alarm setpoint; Low, Mid, Hi, cal. point; and HV pushbuttons to check these parameters. These parameters can be tested without activating the control functions.

f. Assure an extremely high probability of accomplishing its safety function in the event of anticipated operational occurrences.

The MOA monitors are Seismic I qualified (except for the presently used detector), guality Class I, redundant, and are driven by Class .IE power.

This provides an extremely high probability of operation during any anticipated operational conditions.

g. Initiate .prompt pr otective action prior to exceeding plant technical specification limits.

The systems monitor the concentration of radioactive material in the remote air intake ducts. Upon a Hi Hi alarm, the damper in the affected inlet is closed and the Control Room ventilation system is switched to the emergency mode.

h. Provide waring of increasing radiation levels indicative of abnormal conditions by alarm annunciation.

Yes - Have a failure alarm (see i below), Hi alarm, and Hi Hi alarm. The failure alarm and Hi Hi alarm activate an annunciator and buzzer. The Hi Hi alarm also Hoses dampers in the affected air duct.

i. Insofar as practical, provide self-monitoring of components to the extent that power failure or component malfunction causes annunciation and channel trip.

Yes - The'failure alarm trips and causes annunciation in case of loss of power, HV below a setpoint and downscale meter reading.

Register full scale output if radiation detection exceeds full scale.

No, if PM tube driven to current mode, the alarm stays latched and the meter drops to zero.

k. Have sensitivities and ranges compatible with anticipated radiation levels.

Yes - see comparison to ANSI 13.10 Sections 5.4.1, 5.4.2, and 5.4.3.

Comparison of WOAs to the Applicable General Design Criteria 10CFR50 Appendix A guality Standards and Records The remote air intake monitoring system is designed to guality Class I, Seismic Class I criteria. Appropriate records have been maintained.

2. Design Bases for Protection Against Natural Phenomena The design basis is given in the FSAR and does consider appropriate natural phenomena.

3. Fire Protection Fire protection that is consistent with the design basis is provided, i.e., Halon System in the Control Room, administrative control of combustible etc.

4. Environmental and Missile Design Basis The design basis is given in the FSAR and does consider environmental effects and protection from missiles.

13. Instrumentation & Controls The remote its air intake monitor is designed to assure that expected function over the anticipated range of all normal and it will perform t

acci den con di ti ons.

19. Control Room A Control Room is provided that is safe under normal or accident con di ti ons.

20. Protection System Functions The remote air intake monitors will sense radioactivity in the intake air and automatically close dampers to terminate the intake of contaminated air.

21. Protection Reliability and Testability Each remote air intake has redundant monitors. Any single unit can be taken out of service for maintenance, calibration, etc.

22. Protection System Independence System is designed to guality Class I, Seismic Class I criteria and has Class IE power. This assur es that the equipment will operate in all normal and expected accident conditions.

~

~ ~,

A \ ~

VW

23. Protection from System Failure Failure upscale of anyone of these monitors places the Control Room in a safe condition. Failure downscale requires manual action and is admin-i strati vel y controlled.

24. Separation of Protection and Control Systems The protection system that closes is isolated from the monitoring sys-tem. Any one unit of the monitoring system can be removed from service.

29. Protection against anticipated operational occurrences.

N/A

60. Control of releases to the environment.

N/A

64. Monitoring radioactive releases.

N/A

~ l 0,

Attachment 5 ANSI 13.10 COMPARISON LOll RANGE GASEOUS EFFLUENT MONITORING SYSTEM Reactor Building - REA-RIS-19 Radwaste Building - WEA-RIS-14 Turbine Generator Building - TEA-RIS-13 Detection Ca abilities The Low Range Gaseous Effluent Monitoring Systems, REA-RIS-19, WEA-RIS-14 and TEA-RIS-13, all utilize plastic (polyvinyl-toluene) beta scintillators supplied by Kaman Instrumentaiton.

The detectors are mounted in a 2.2 liter stainless steel sample chamber surrounded by a three inch 4'if lead shield. A continuous gas sample is pulled through the sample chamber after the sample stream has passed through a charcoal cartridge and particulate filter.

These monitors provide continuous indication of the radioactive gas concentration for the three plant effluent pathways. The sample system for the REA and TEA employs isokinetic samplers which assures representative sampling. The WEA system utilizes isokinetic probes with a fixed flow rate expected to be isokinetic over the normal ventilation operating range.

These monitors provide downscale, Hi and Hi Hi alarms in the main control room. The Hi Hi alarm point corresponds to reaching 80% of an MPC based on Xe-133 equivalent setting for the percent of total allowable effluent discharge as listed in the WNP-2 ODCM.

These monitors were calibrated by Kaman Instrumentation using NBS traceable quantaties of Xe-133 and Kr-85. These gas calibrations are used as the primary calibration, with transfer calibration performed to within +205 accuracy on the monitor as installed in their sampling configurations at WNP-2.

The principle nuclides these detector systems are required to measure are Xe-133 and Kr-85. The response as determined by the primary and secondary (transfer) calibration indicate that the ANSI

13. 10 MDA's are within the capabi lities of the installed instrumentation. As these systems employ beta scintillators that are relatively insensitive to gamma photons, the detectors are expected to be able to see low levels of beta activity from noble gases in appreciable external gamma fields.

Detection In Gaseous S stems The Reactor Building, Radwaste Building and Turbine Building gaseous effluent monitors are shielded from gamma radiation and monitor air

'I streams that are preconditioned by passing through particulate filters and charcoal cartridges. This design reduces the system background and helps achieve a low system t1DA or LLD. The LLD was calculated using the technical specification method. The ADA's were calculated using the method typically used in the industry and by using the ANSI 13.10 method incorporating the RC time constant.

The listed LLD and HDA's represent the 95% confidence level.

Tech Spec Normal ANSI 13.10 ANSI 13.10 Instal 1 ed Cal ibr ati on LLAMA.668k MAA=~ARk 606=1.66~~6k I I Design HDA Detector Nuclide Background Factorl Cal. Factor Cal. Factor Cal. Factor REA Xe-133 24.4 cpm 4 EEE+7~cm 5.'06E-07 uCi/cc 2.13E-07 uCi/cc 3.36E-07 uCi%cc 5.0E-7 uCi/cc uCi/cc WEA Xe-133 20.1 cpm 4.8GE+7~c m 4.35E-07 uCi/cc 1.83E-07 uCi/cc 2.89E-07 uCi/cc 5.0E-7 uCi/cc uCi/cc TEA Xe-133 27.3 cpm 4.82E+7~c m 5.05E-07 uCi/cc 2.12E-07 uCi/cc 3.36E-07 uCi/cc 5.0E-7 uCi/cc uCi/cc REA Kr-85 24.4 cpm 7.32E+7~c m 3 14E-07 uCi/cc 1.32E-07 uCi/cc 2 09E-07 uCi/cc 3.0E-.7 uCi/cc uCi/cc WEA Kr-85 20.1 cpm 7.71.8+7~urn 2 71E-07 uCi/cc 1 14E-07 uCi/cc 1 80E-07 uCi/cc 3.0E-7 uCi/cc uCi/cc TEA Kr-85 27.3 cpm 7.74E+7~cm 3.15E-07 uCi/cc 1.32E-07 uCi/cc 2.09E-07 uCi/cc 3.0E-7 uCi/cc uCi/cc The calibration factor is evaluated at 8.625 E+4 cpm, the transfer standard count in year = 84.00000.

The LLD and MDA's from the three methods used compare closely with the MDA listed in Table 1 of ANSI 13.19. The normal and ANSI 13.10 MDA's'both meet or exceed the design specification levels "

suggested in Table 1 for Xe-133 and Kr-85.

5.4.1.2 Detection In Li uid Streams The rangy of these three instruments meets the criteria of at least 10" minimum detectable levels. The range of the detectors is 10 to 107 cpm. The table below gives the specifics.

Ran e REA WEA TEA Meter Scale 10 to 10 c m 10 to 10 c m 10 to 10 c m Xe-133 uCi/cc 2.2E-7 to 0.22 2.1E-7 to 0.21 2.0E-7 to 0.21 Kr-85 uCi/cc 1.4E-7 to 0.14 1.3E-8 to 0.13 1.2E-7 to 0.13 MDL c m 15.3 13.9 16.19 MDLx 10cm 1.53 x 10 1.39 x 10 1.62 x 10 5.4.3 Sensitivit The sensitivities of the REA, TEA and WEA monitoring systems were calculated according to ANSI 13.10 definition based on the RC time constant for the instrument. The RC time constant used was 12 seconds as this is the time constant for the decade of the background level.

.Following is a tabulation of the sensitivities.

Ins tr ument REA WEA TEA Sensitivity Ns=l.96 Nb/2RC Ns=l.96 24.4 Ns=1.96 20.1 Ns=l.96 27.3 2 x 12 2 .x 12 2 x 12 60 60 60

= 15.3 cpm = 13.9 cpm = 16.19 cpm 5.4.4 ~Accucac The accuracy of the REA, WEA and TEA systems was determined based on the count rate of the WNP-1 standard Sr-90 transfer calibration source activity as was determined at the time of the primary calibration. The transfer source is NBS traceable and ngminal count rate at time of manufacture is cpm/uCi = 9.83 x 10~

at the 95% confidence level.

i 5.025 .

The REA, WEA and TEA monitors were calibrated using the transfer source and the count rate off from a sealer system hooked into the output of the detector module to determine the accuracy. During the calibration performed on the installed configuration, the detectors were all determined to be within the +10% accuracy meeting the %20% in ANSI 13.10.

The formula used to determine error was percent error =(Rt-Rr x 100 Rt where Rr was the sealer output and Rt the NBS traceable transfer source activity. The following table lists the accuracies for each unit.

REA ~

WEA TEA Accuracy -4.11% +1.06% -1.49%

The accuracies of the ratemeters and recorder are specified by the Kaman Instrumentation manual as follows:

Recorder: +0.5% of span Ratemeter: %5%

teeter reading accuracy: 4 smallest scale division 5.4.5

~ ~ Precision The precssion was determined for the REA, WEA and TEA systems during the transfer source calibration with the data being taken from Sr-90 source counts. The precision for these units was determined to all be within"%3%. This was a requirement of the approved calibration procedures used during the calibration.

The indication for other counts on similar beta scintillation indicates that +10% precision error can be met or exceeded for the REA, WEA and TEA low range effluent monitoring systems.

5.4.6 Res onse Time The response time is adequate to achieve the required accuracy as t

demonstrated in the other sections of this repor where the RC time constant was used. Since no delay circuits or devices are incorporated into our electronic circuits after the log ratemeter the nominal value of 2.2 time constants is easily met.

From the Kaman manual, the response time for given signal changes and the 2.2 time constants values are shown below.

r ~

I h

Response Time

~5i 7CR RCPT C 2.2 RC i 10-10 12 sec. 26.4 sec.

10-10 3.5 sec. 7.7 sec.

10-10 1.0 sec. 2.2 sec.

10-10 0.1 sec. 0.22 sec.

10-10 O.l sec. 0.22 sec.

5.4.7.1 T~

The 10-10 O.l sec. 0.22 sec.

ratemeters, recorders and power supplies are located in the main control room which is designed to be habitable under normal and analyzed abnormal conditions and will never exceed 140 F (60oC). At this temperature calibration drift would be very small and is typically ignored.

Detectors - Kaman states normal operating temperature to be 32-140 F (0-60oC).

a. The beta scintillator is a polyvinyltoluene based plastic. The plastic will undergo no change in sensitivity from -60oC to 20 C, but will decrease to 95/ of the 20 C response at 60oC (140oF). The beta scintillator will have about 0.345 response to lOOKeV gamma rays.

b. P.M. tube is a 10 dynode stage unit, which is intended to operate from -30oC to 50 C (122 F) normally but can operate from -30 C to 80oC (176oF) for short periods.

c. Preamplifier, contained in the beta scintillator housing can operate to a temperature limit of 60 C. The lower limit was not specified but would definitely be below 0 C.

Ratemeter Module The module is rated to operate between the temperature limits of 0 C to 60oC, maintaining the accuracy stated of one-half the smallest scale division, 0.395 ELFS. No statement is made concerning the 4-20 MA output with respect to accuracy vs. temperature.

Recorder Module The recorder is designed to operate normally from 4 to 49 C (40 to 120 F) for a normal operational limit. Maximum limits are stated to be from -18o to 60 C (0 to 140 F). Its power supply operates from 18o to 60 normally.

~PR

. The operating range of the power supply is the same as the recorder.

The temperature effect as stated by Kaman Instrumentation is +0.5%DC and +1.0%AC for +40oF based on an operating range mid point of 80 F.

I 5.4.7.2 Pr'essure The detector chamber and detector are the devices that could be pressure sensitive. "0" rings are used to seal the detector into its housing, and the housing into the chamber. When grab samples have been taken with indicated systems pressure at 5 inches of mercury (approximately 630 torr), no apparent changes in back-ground radiation levels have been noticed (130 torr = 5 inches mercury = 2.5 psi). No specific statements relating to pressure/

vacuum were found in the operating manual.

5.4.7. 3 ~Humidi t Detector assembly - Vendor suggested storage can be from 0 to 95K humidity. Operation should be over the same range.

Ratemeter module has an operating limit from 0 to 95K relative humidity.

Recorder operating limit, not specified.

5.4.7.4 Corrosive Atmos here No specification and no corrosive atmospheric conditions expected, but detector housing and chamber is stainless steel. The alumized Mylar windows could be sensitive to organics as Acetone, etc., but be used in close proximity.

none'hould 5.4.7.5

~ ~ ~ Power Re uirements Detector - Derives its power from the RIS module.

RIS h1odule - Can operate with power ranging from 90 to 130 volts and over a frequency range from 50 to 60 Hz.

The recorder obtains its power from a rack, mounted power supply.

The input variation of -lOX to +5% or from 103.5 to 121 volts will cause a change of 0.55 in the DC voltage. Beyond that range the changes'in the supply output is not specified. A frequency of +1 Hz will cause a 0.35 change in the DC supply.

5.4.7.6 Electrical Effects This has been a problem. Kaman Instrumentation specs indicate that the power supply for the recorder is sensitive to RF. Experience indicates that the system is sensitive to RF generated at either the sample rack or the ratemeter/recorder locations. During the pre-operational testing, a hand-held transmitter was keyed (this was prior to the ban of such items in the control room). If an effect was noticed, it summarizes the test:

was entered in the pre-op test summary. The following With the module mounted in its rack, key a walkie talkie in the vicinity and note the effects. The test was repeated at the monitor skid location.

The walkie talkies output approximytely 4 watts into the antenna. Assume a function of 1/r~ at first approximation for energy at the module face. At approximately 6 feet the power would be about 12 w watts. The result was the rack mounted module alarmed (all alarms). All Kaman In-strumentation modules responded in a similar fashion, yet when the same test was applied to the corresponding skid, no effect was observed. Use of radios is being controlled administratively to eliminate this problem with the Kaman instruments.

5.4.7.7 ~5i i i Not required on this equipment as it is Class II; however, the equipment in the control room i.e., ratemeter recorder, etc., is in a seismically qualified rack and is identical in design and manufacture to other seismically qualified units such as the remote air intake monitors (WOA's). This requirement is probably fully met but it is not documented and is not critical to the monitor functions.

5.4.8 Radiation Alarms The ratemeter is equipped with two upscale alarms (Hi and Hi Hi) which can be set at any point over the range of the instrument.

These alarms are latching type and must be manually reset. The alarms illuminate a light (Hi amber; Hi Hi red) at the ratemeter and open a solenoid which causes a trouble light on an annunciator panel to illuminate and a buzzer to sound, Board "S" ANN panel P851-S1.

The Hi and Hi Hi alarm setpoints can be adjusted externally without removing the instrument from service.

5.4.9 Failure Indicators A down scale or H.Y. failure indicator (green) is on each module and will illuminate when tripped. A corresponding trouble alarm will indicate on Board S, ANN Panel P851. The alarms are the latching type that have to be manually reset.

5.4.10 Calibration a ~ NBS Traceable - Three each of 133 Xe and 85 Kr NBS certified gases were used in the primary calibrations. The gases were introduced into the known volume standard Kaman gas chambers. The detectors used were "generic" Kaman beta scintillator units. The counting and analysis, carried out on the WNP-1 digital system, was completed and entered onto calibration report sheets. This report was forwarded to WNP-2 as part of the equipment package. The total calibration errors, including NBS gas calibration errors, ranged from 9.7X, a low activity sample, to 1.64, a high activity sample at the 95K confidence level.

~ L I

0 0

'I

~ II 6

T

b. Transfer Calibration Sources - Disk sources of 90 Sr were used at the same time as the above mentioned gas caljpgation. A response factor was developed relating 9"Sr to '~~Xe. A further study of 25 different detectors response to the primary and secondary 90Sr transfer sources indicated the true "generic" quality of the detectors. A mean error of 2.6X and 4.3X respectively at the 95K confidence level indicates a very good group. Further, the response to Kaman's standard and WNP-1's secondary transfer sources were within 0.6% at 95K C.L. These secondary sources were and are periodically analyzed on beta detectors which are calibrated with NBS and NBS traceable sources.

C. Constant Geometr - The vendor, Kaman, has a shielded portable constant geometry rack (field calibrator). Demonstrated reproduceability of source placement is within +0.35.

d. ~gtPT I -Th I ti ptdp hi f hi I and sample lines. DOP testing not required and an exception was taken to the ANSI 13.10 criteria in the December 8, 1983, memo.

e. Flow Rate Devices - Each sample skid has a rotometer that ranges from 0 to 10 cfm, a measureable range of 0.5 to 9.5 is repeatable to within 205 at any reading. Furthermore, the WEA skid has a flow totalizer which is periodically calibrated and is accurate to +104 of its reading.

Coupled to flow rate measurement is the pressure measurement on each monitor skid. Each skid is provided with a vacuum gauge that reads from 0 to 30 inches at .+25 of reading according to the vendor.

~pdin fthe controlihunit I;dsolenoid Check Source module 661 Each has a room.

activated check source d h Ilg

g. Electronic Calibration Si nals - Each RIS module has 1) an internal oscillator which allows a sweep across the output range for alarm test and 2) a calibration signal input (pulse) for accurately establishing the setpoints. 6

c REVIEW TO FSAR CRITERIA 11.5.1.2.2

~ ~ ~ ~ ~Res onses a ~ Yes,- see M893.

TEA-RIS-13, TEA-RR-13 on BD-RAD-24 WEA-RIS-14, WEA-RR-14 on BD-RAD-24 REA-RIS-19, REA-RR-19 on BD-RAD-24

b. Yes. See 5.4.8.

c~ Yes. See 5.4.9.

d. Representative Sample:

1. REA and TEA utilize air monitor sampling systems which assure isokenetic and representative sampling. Air flow changes are monitored and inlet flows are adjusted accordingly.

2. WEA utilizes isokenetic probes and a fixed sample flow rate.

The fixed flow rate will be isokenetic over the expected operational range.

e. Each RIS module allows for:

Check Source Alarm Test H.V.

Calibration Signal Input Alarm Reset

f. See monitor summary sheet, RANGE.

g. These monitors have a holding circuit for the alarm when tripped. It requires manual reset. The meter will record the it is signal status on the detector.

Desi n Criteria A endix A

13. Met as far as range of instrument intends.

60. Measures release to the environment. Does not control release. as per system design. Administrative controls are imposed upon alarm trips to initiate action to assure the safety of the public is assured.

64. Monitors measure rad gas actively in reactor unit gas release pathways.

Attachment 6 ANSI 13.10 REYIEW Turbine Service Water Monitor Plant Service Water EPN'ample Rack TSW-SR-34 Detector TSW-RE-5 Flow h1eter TSW-FIS-1 Recorder None General Descri tion of System The Turbine Service Water Monitor measures the activity in Plant Service Water return header. The Plant Service Mater draws water from the circulating water intake str ucture and provides cooling water for about 25 pieces or groups of equipment. 'bout half of this equipment has no potential for contaminating the service water and these streams enter the discharge header downstream of the monitor. The remainder have only a small potential for contaminating the service water however, the TSM monitor draws its'ample downstream of the latter group of equipment which have the low potential for contamination.

The Sample probe is a 3/4",SS line inserted through the side of the 18" header. The sample line extends 2 1/2 inches into the'18" header and is cut on a 45'ngle. The sample is passed through sample chamber, a rotameter, a pump, and back to the header.

The sample chamber is a 2.4 liter stainless steel marinelli beaker with the detector position to the chamber in an essentially a 2W configuration. A 7 inch thick 4 ~ shield is provided for the sample chamber and detector. From the sample chamber, the sample stream flows through a rotameter with a range of 0.2 to 6 gpm. The rotameter has low flow detection/alarm capabilities and is typically set to alarm at 2.0 gpm. The sample flow is maintained by a centrifugal pump which returns the sample flow to the service water header.

The detector consists of a 1 x 1-1/2 inch NaI (Tl) crystal optically 'coupled to a photomultiplier tube and followed by a preamplifier. The signal is sent to a 6 decade (10 to 107 cpm) ratemeter which is in the main control room.

The ratemeter has three internal calibration points and provisions for inputting an external calibration signal. An alarm test function is also provided. A 8 uCi Cs-137 (11/14/78) check source is provided at the detector. The check source is controlled from the ratemeter. The TSW monitor does not have a recorder. The TSW monitor is guality Class II, seismic II and covered by Technical Specification, Section 3.3.7.11.

The release rate via the plant service water is expected to be zero to very low. This monitor provides no automatic control function.

Gom arison to ANSI 13.10, 5.4 "Standards of Performance" 5.4.1 Detection Ca ability The TSW monitor detects gamma radiation using a 1" x l-l/2" NaI (tl) cyrstal..This type and size of crystal provides a good counting efficiency for radiation emitted from the expected radio nuclides which are Cs-137 and Co-60. The monitor was calibrated with an NBS traceable Cs-137 solution and was set to measure gamma radiation w'.th energies greater than 80 kev. The alarm set point is set at 80% of the MPC for Cs-137 and allows for a 20'X error in calibra-tion. The MDA from Section 5.4.1.2 (below) of 3.65 E-7 uCi/ml meets the MDA criteria of ANSI 13.10. The other nuclide of interest, Co-60 detection at MPC will be no problem as two gamma per disinte-gration are emitted.

Periodic samples from the service water system will be taken to verify that the monitor calibration remains representative.

5.4.1.1 Detection in. Gaseous Streams Not applicable.

5.4.1.2 Detection in Liquid Streams The TSW monitor employes a shielded detector system as described in the General Discription of System section. The shielded off line monitor provides a fairly stable background level resulting in low MDA. The LLD for this monitor was calculated by using the Technical Specification definition. The MDA's were determined by using the method typically used in the industry and by the ANSI 13.10 method using the R.C. Time Constant. The LLD and MDA's are expressed at the 95% confidence level based on a Cs-137 primary calibration.

I Tech. Spec. I Normal I ANSI I I I I I Calibra- I .I I I ANSI 13.10I Back-I tion ILLD= 4.66 Bkg IMDA=1.96 Bkg IMDA=1.96 Bkg/2RCI IDetectorl Criteria I roundl Factor Cal. Fac. Ca . Fac. Ca . Factor TSW l4.E-7uCi/mll 155 I6.68 E7C ml8.69E-7 uCi/mll3.65E-7uCi/mll 1.07E-6uCi/ml I I I

'C> m I I I The RC time constant for the second decade or decade of background is 3.5 sec and was used in the ANSI 13.10 calculation.

~

(

TSW Primary Calibration Data Liquid Sources Source CPM BKg Net Ct (X - 7) ~u i's-137 cpm 1 '037 4895 169 7.60E-5uCi/ml 5033 4891 81 6.424E7

+ 7.0% 5009 142 4867 225

'F 2 5016 4874 64 7 = 4882 2539 (x - )l)

= 13 C Pill Sour ce CPM BKg Net Ct (X - 7) ~%7mm Cs-137 2 . 70279 70117 9

1. 025E-3uCi/ml 70496 70334 48,406 6.84E7

+ 2. 47% 69823 162 70661 299,209 F 2 69507 69345 591,361 70114 Z 938,979 C ill Source CPM BKg Net Ct (X - 7) u s m Cs-137 3 790,639 790,479 498,436 1.168E-2uCi/ml 791,208 791,148 1,369 6.77E7

+ 1.61% 791,310 160 791,150 1,225 F2 792,121 791,961 602,176 X = 791,185 Z654,606

= 467 Calibration Factors .

Bkgrd Counts Cpm/ uCi/cc (X - X)  % From 7 Bkg cpm (X - 7) 64.24 E6 6.45 4% 142 169 68.4 E6 6.26 2'X 162 49 67.7 E6 0.85 1% 160 25 7 = 66.78 E6 K= 13.56 E12 X = 155 F243 6.68 E7 cpm/uCi/ml 4 = 2.13 E6 6=11

5..4.2 ~Ran e MDA = 1.96 VBKg = 24 cpm MDA = 24 cpm = 3.65 E-7 uCi/ml (24) (104) = 2.4 E5 cpm Range of ratemeter 10 to 107 5.4.3 Sensi tivity Nb Based on Ns = 1.96 J

Time constant for second decade = 3.5 sec.

Ns = 1.96

~~155 = 71 cpm 5.4. 4 Accuracy A primary calibration was made which established the ratio of the transfer standard sources to the liquid standard sources and the counting rate of the transfer standard source. The counting rate for the transfer standard, based on 6 counts, is 8.50 E4 cpm, 115 cpm. This is equivalent to 8.50 E4 cpm + 0.3% at 95% CL. This counting rate when corrected for decay will 5e't for future calibrations.

The calibration factor at the 3 concentrations used in the primary liquid calibration agree within + 5% of the mean.

Transfer Std.

Source Ct BKg Net Ct (X - X)2 85206 142 85064 1089 8506-* 8492- 12321 85264 '64 85100 4761 851 849 17161 85364 160 85204 29929 852 850 961 X 85031 266222 6 = 66222 = 115 cpm

• original data. rounded

~*

1 0

5.4.5 Precision Based on 6 counts of the transfer standard.

7 = 8.50 E4, ~ = 115, 1.96' 225 cpm

~~ 225 = 1.2 E-5 which is much less than 10% Y.

5.4.6 Response Time Bkg = 155 cpm Ns = 1.96 155 = 71.44 cpm mTKKT'0 KMPcpm/uCi/ml With a time constant of 3.5 sec for the second decade, the instrument will easily see the required detection level of 4E-6 uCi/ml. The time delays in the alarm circuit etc. are insignficant (milli seconds).

5.4.7.1 ~Tt The ratemeter and power supply are located in the main Control Room which is designed for human habitability under normal and analyzed abnormal conditions and will never exceed 104'F.

Detector o Normal operating temperature per vendor is 0-60 C.

o The effect of temperature on the calibration (counting efficiency) is not defined.

o Under normal and analyzed abnormal conditions the ambient temperature is maintained for human comfort. Calibration drift (counting eff) in this temperature range, if any, is typically ignored in analytical counters. Energy calibration does change.

Under very abnormal operating conditions the temperature of the stream being sampled may approach 60 C. However, unlikely that the detector would reach this it is temperature. Per Kaman spec. sheet max. temp. = 100 F (38 C). Undefined changes in Ptl tube performance (i.e., increase/decrease in noise level) and energy calibration would be expected. This should not have a deleterious effect on the intended purpose of the instrument.

Pum /Motor/Rotameter: This range of temperatures should have mini-ma e ec . e wa r should never freeze in this system. Per vendor spec. components rated for 60 C rise above ambient of 40 C.

Ratemeter Module:

ratemeter will Per vendor specifications +

bi tt p t never exceed 40'C (= 104'F) even tti afterti 5%

1 change over range fth LOCA.

5.4.7. 2 Pressure This range of pressure should not affect any component in the system. Also, all components are open to the turbine building or

. control room atmosphere and will, therefore, never see these extremes.

5.4.7. 3 Humi di ty Detector (scintillator/preamp) - Vendor gives no operating

~speci ications. Since storage in.a hosiidi ty range of 0-99% is approved by vendor, operation in this range of humidities should be permissible. The calibration and accuracy will not be affected.

Other components at skid - The motor, pump, flow meter etc. should not be a fecte y umph ity.

Ratemeter/Recorder - No effect expected on ratemeter as it is in ontro Room. o recorder on this instrument.

5.4.7.4 Other Environmental Effects Detector - None expected.

Motor - None expected.

Pump, flow meter s check valve - Foreign material in the plant serv>ce water - ~.e., res n beads, blow sand, etc. - causes clogging problem which decreases flow rate. Occasional flushing is needed.

Visual inspections and the low flow alarm adequately monitor this probl em.

Ratemeter - None expected.

S.$ .7.5 Power The detector including preamp, ratem ter, and recorder are powered from instrument power buses in the control room. This power supply is stabilized and variations of 15% will not be seen.

I Per Kaman specs: for the ratemeter 90 - 130 VAC, 50-60 Hz is acceptable. Kaman spec for the recorder power supply and recorder indicate that the recorder would easily meet a -10K + 5% variation in power supply.

Motor/pump - no si gni, ficant, e ffect.

5.4.7.6 Electrical Effects This has been a problem. Kaman instrumontation.specs indicate that the power supply for the recorder is sensitive to RF. Experience indicates that the system is sensitive to RF generated at either the sample rack or the ratemeter locations.

Use of radios is being controlled administratively to eliminate this problem.

5.4.7,7 Mechanical Effects The TSW is not seismic I qualified. However, the equipment in the control room i.e., ratemeter recorder etc. is in a seismically qualified rack and is identical in design and manufacture to other seismically qualified units such as the remote air intake monitors (WOA's ). Likewise the detector and sample rack is not seismically qualified but probably could be. This requirement's probably fully met but documentation is not available.

5. 4e8 Radiation Alarm The ratemeter is equipped with two upscale alarms (Hi and Hi Hi) which can be set at any point over the range of the instrument.

These alarms are latching type and must be manually reset. The alarms illuminate a light at the ratemeter and open a solenoid which causes a trouble light on an annunciator panel to illuminate and a buzzer to sound.

The alarms are reset and the set point of each alarm can be checked from the face of each count ratemeter.

The alarm setpoints can be adjusted externally from the meter face for the Hi and Hi-Hi alarms. An exception was requested for this requirement, however, the alarm setpoints can be adjusted externally for this instrument, meeting the intent of this requirement.

5.4.9 Failure Alarm The ratemeter provides a latching alarm in case of power failure, HV below the HYINOP setpoint, or counting rate below a setpoint value.

Cal ibration a) Primary calibration of the,TSW monitor was performed on site by circulating three different concentrations of a NBS traceable Cs-137 solution through the sample chamber.

b) A Transfer Standard source (Cs-137), and three sources (Ba-133) which are also NBS traceable, activity were counted. The 3 Ba-133 sources are used to determine the system's response v.s.

activity. The energy response of the system was also evaluated and the low energy cut-off was set to 80 Kev.

c) The Transfer Standard source, the linearity sources, and energy response sources are small (about 1" diameter) solid sources.

The detector to source geometry is precisely maintained by using the Kaman Calibrator which is a shielded jig. The Transfer Standard count was used to establish a baseline for use in subsequent periodic calibrations. Cs-137 is used for calibration per FSAR Table 11.5-2.

d) The surface area of the Transfer Standard is not the same as the surface area of the detector window. When the detector is in the sample chamber which is a marinelli beaker, 3 n'geometry is approximated which cannot be easily reproduced in a calibra-tion jig. The Transfer Standard source and detector is pre-cisely repositionable in the calibrator and therefore error in source positioning is negligible.

e) As this is a liquid sampling system, the loss in the sample line is expected to be negligible. An exception was taken to this requirement in the December 8, 1983 memo to NRR on ANSI 13.10.

The flow rate measuring device (rotameter) was calibrated in October 1983. Presently, there are no plans for periodic recalibration.

A remotely actuated check source is provided.

h) Calibrated electric signals are provided by the ratemeter and externally generated signals can be inputted at the ratemeter.

In both cases the signals are inputted downstream of the gain and discriminator circuits in the ratemeter.

C Com arison of the TSW Monitor to FSAR Requirements 11.5.1.2.2 Systems Required for Plant Operation

a. Provide continuous indication of radiation levels in the main control room.

Yes - Dial indication only no recorder TSW-RIS-5, BD RAD-24

b. Provide warning of increasing radiation levels indicative of abnormal conditions by alarm annunciation.

Yes - Ratemeter has 3 latching type alarms, Failure, Hi and Hi Hi. The failure alarm and Hi Hi alarm activate an annunciator on other control panels. All alarms light on panel but the Hi alarm does not annunciate.

c. Insofar as practical, provide self-monitoring of components to the extent that power failure of component malfunction causes annunciation and, for systems initiating protective action, channel trip.

Yes - Failure alarm (down scale, low HV, and no power ) causes annunciation.

d. Monitor a sample representative of the bulk stream or volume.

Yes - Draws 2-4 gpm from 18" header.

e. Have provisions for calibration, function and instrumentation checks.

Yes - 3 built-in calibration checks for the ratemeter. Provisions for inputting an external signal into ratementer .

Cs-137 check source for overall system check.

f. Have sensitivities and range compatible with anticipated radiation levels and technical specification limits.

Yes - See NSI 13.10 information.

g. Register full scale output if radiation detection exceeds full scale.

Doubtful - However, alarm will latch.

If PM tube is driven to current output, meter reading will probably drop to zero.

~ ~

~

Com arison of the TSW to A licable General Design Criteria of 10CFR50, Appendix A Requirements Qi 3 Operable under expected normal and abnormal conditions7 Yes - Environment normally controlled for human access and comfort as this monitor is located in the turbine generator building.

60 - Control radioactive effluent? Is adequate hold up volume provided.

The TSW measures the radioactivity in-leakage into the Service Water System, manual action is needed for control if control becomes necessary.

Holdup volume is not provided. However, the plant service water system can be shutdown in emergencies and the circulating water blowdown system flow to the river terminated.

64 - Monitoring radioactive releases The TSW monitors one effluent stream, which has a very low potential for release of radioactivity, under normal and abnormal operating condi-tions. It will probably continue to operate in accident conditions but is not required. The discharge is to the Circ Water Basin, and can be terminated as stated in GDC 60.

~' ~

~ 4

Attachment 7 ANSI 13.10 (Section 5.4)

OFF GAS PRE-TREATMENT RADIATION MONITOR System Objective The objective of the "Off Gas Pre-Treatment Radiation Monitor" is to provide indication and record of gross gamma radiation level in the effluent, upstream of the Off Gas Charcoal Recombiner System.

S stem Descri tion This monitoring system normally samples from downstream side of the hydrogen recombiner units prior to the charcoal beds. The aggregate monitoring system consists of a gamma sensitive ion chamber detector, indicator and trip unit (monitor ) and a strip chart recorder. No automatic trip functions are associ-ated with the system, there are two upscale alarms set at radiation levels approaching the Technical Specification limit the Hi alarm corresponding to an action level and downscale (inop).

The detector (ionization chamber) is located outside of, and against, the off-gas pipe inside a shielded cubicle on the 441'levation of the Turbine Building.

5.4.1 Detection Ca ability Does not apply to this system. The gamma sensitive ion chamber is used for detecting gamma flux level. The chamber yields a direct current proportional to the gamma radiation level in which ates. An ionization chamber was chosen for this monitor as ititoper-will respond to mixed fission products. It is used to alert Chemistry to sample and perform an isotopic analysis of the offgas gas stream.

5.4.1.1 Detection in Gaseous Streams Does not apply (see 5.4.1 explanation).

5.4.1.2 Detection in Liquid Streams Does not apply (see 5.4.1 explanation).

5.4.2 ~Ran e The instrument range is from 100 mR/hr to 10 mR/hr in 6 (six) 10 'o evenly spaced decades. The input current range is from 3.33 x 3.33 x 10 7 ampers. The normal background is expected to be 400 mR/hr or less and with a range of 106 mR/hr, the MDA times 104 is not applicable to this monitoring function.

ft Sensi tivity For a gamma responding system that reads out in mR/hr the "Response Time" is the characteristic used for sensitivity. The following is the system response times:

6 sec (3.33 x 10-13 to 3.33 x 10-12 amp) 1 sec (3.33 x 10-12 to 3. 33 x 10-11 amp) 1 sec (3.33 x 10-13 to 3.33 x 10 7 amp)

For specific radiation levels, the conversion to ampers can be made by multiplying the radiation level by the chamber sensitivity (the normal sensitivity is 3.7 x 10-10 ampers/R/hr). The ranges stated above can be determined in mR/hr/R/hr by the same method. The RC time constant for the various decades can be found by dividing the response time by 2.2.

Accuracy The detector was subjected to a 9.18 curie NBS Traceable Cs-137 source at approximate gamma levels of 100 mR/hr (.1R/hr), 1000 mR/hr (1R/hr ), 5000 mR/hr (5R/hr) and 10,000 mR/hr (10R/hr ). A NBS traceable calibrated set of condenser "R" chambers was used as the reference standard for determining Rt (true quantity) in the percent error equation. The following are the results of the 6-22-84 cal ibration:

NOTE A primary radiological calibration was completed on 11-28-83 with the results matched against the ELFS criter ion. The 6-22-84 radiological calibration results were matched against a + 20% relative error criterion.

R Monitor Corrected Condenser Control Room Percent Number "R" Reading Meter Reading Error Type NA05 Cat $ 327X7316001 Serial ~TNNKG-029 138 mR/hr 120 mR/hr 13%

842 mR/hr 800 mR/hr 5%

5286 mR/hr 5000 mR/hr 5'X 7956 mr/hr 7750 mR/hr 3%

percent error =

~

The above was determined Rt - Rr using:

x 100 T

Precision The system used is as follows:

1) Based on the source strength (total curies) and the conversion to R/hr exposures were made to estimate distances. The specific source was an Amerisham - Cs-137 source of 9.45 curies.

'1 o Source strength at factory = 9.45 curies o Source strength 471 days later on 12-9-83 = 9.18 curies o From Rad Health Handbook - 10 curie source reads 3.3R/hr/meter.

o Using this conversion a 9.18 curie source reads 3.026 R/hr/meter.

This information was used to determine the approximate distance the detector would be placed from the source center. The inverse square formula was used for these distance estimates with:

Il = 3.026 R/hr Rl = 1 meter I2 = Desired reading R2 = ?

The center of "a" condenser "R" chamber was placed at the center of R2. The exposure time was based on the condenser "R" chambers range, requiring that the final exposure be near or above the mid point of the range. The exposure reading was then corrected for inherent error (as recommended by the mfg. ),

barometric conditions and temperature. This result is Rt.

Each detector was placed, in turn, at the Rt location and exposed. This result is Rr.

The X

The error =

~

final error determination is:

Rt Rr x 100 definition of precision applies only to the distance Rr is from the traceable standard Rt. Repeatability of measure-ments between the source and condenser R chamber and the source and detectors substantiates precision easily within + 10%.

Res onse Time Does not apply, but is the time in seconds stated for the specific decades in Section 5.4.3. The RC time constant would be that stated response time divided by 2.2.

f I

0

~ ~

5.4.1.1 ~tt The detector temperature upper response = 200'C (392'F). This exceeds the ANSI criteria of 60'C. Logarithmic Radiation Monitor (LRM) temperature = 5 to 50 C and will be sufficient as the readout is in the Main Control Room that is habitable through all analyzed accidents.

5.4.7.2 Pressure Detector operating pressure 250 psig or 12,925 torrs.

5.4.7.3 Humidity Relative humidity range for the LRM is 20 to 98% (with no condensa-tion). The chamber is not normally used where temperatures and humidity conditions are such that moisture cannot collect inside the connectors.

5.4.7.4 Other Environmental Effects Manufacturers specifications were followed for installation and operation. Industry history substantiates durability and resistance to adverse environmental effects. The detector is in a shielded closed room and will not be exposed to corrosive elements.

5.4.7.5 Power Requirements The power supply is from a stable and predictable source (RDS, Reactor Protection System).

5.4.7.6 Electrical Effects Not applicable 5.4.7.7 Mechanical Effects Not applicable 5.4.8 Radiation Alarm Not applicable 5.4.9 Failure Alarm A HV-INOP Trip Circuit is employed on this system. The circuit will indicate a trip condition whenever the LRM high voltage level becomes abnormally low or whenever the front panel mode selector switch is in any position other than operate.

5

I 5.4.10 Cal ibrati on The system was calibrated agains (using) NBS traceable condenser "R" chambers.' Cs-137 source of sufficient strength was used (see above) to allow a quantative response for three different intensi-ties. The system can be placed in any of four different test and ca'libration configurations (HiCAL, LOCAL, ZERO and TRIP TEST).

The detectors are inspected and verified in working condition at the time of receipt. System operation and readout adjustment is done at the time of radiological calibration. Trip functions are tenta-tively set at the time of radiological calibration and, as back-grounds warrant, are adjusted using calibrated electrical impulses.

The trips are adjusted to comply with the WHP-2 Technical Specifi-cations. No check sources are incorporated in this system.

OFF GAS PRE-TREATMENT RADIATION MONITOR CALIBRATION

~

Discussion This moni toring system was radiologically re-calibrated on 6-22-84 to comply

~ ~

with ANSI 13.10 "American National Standard Specification and Performance of On-Site Instrumentation for Continuously Monitoring Radioactivity in Ef-fluents". A previous radiological calibration was made on 11-23-83 with the results matched against the ELFS criterion. The 6-22-84 radiological calibra-tion results are matched against a + 20% relative error.

Method Calibration was conducted per PPM 12.13.1, "Off Gas Pre-Treatment Radiation Monitor Calibration". A brief summary of the operation is as follows:

o Using an approximate 9.08 curie Cs-137 source (NBS Traceable AMERSHAM)

NBS traceable condenser "R" chambers were exposed at distances approxi-mating 100 mR/hr, 1000 mR/hr, 5000 mR/hr and 10,000 mR/hr.

o After completing the condenser "R" exposure the detector was placed in the same location, exposed and control room meter read.

o The control room meter is matched against the condenser "R" chamber results for + 20% relative error accuracy.

Results

1) 100 mR/hr (.1 R/hr) exposure:

o Condenser "R" reading = 18 mR/8 min = 135 mR/hr o Correction factor for condenser "R" chamber:

CT (Temp) = for 77.8'F (25.4'C) = 1.01 CB (Barometer ) = for 29.63 in Hg = 1.03 CR (Condenser "R" chamber [Correction Factor Techniquej) = 0.984 (CT)(CB)(CR) = (1.01)(1.03)(0.984) = 1.02 o Actual condenser "R" reading = (1.02)(135 mR/hr) = 137.7 or 138 mR/hr o Control room meter reading = 120 mR/hr o Relative error:

138 mR/hr -120 mR/hr ]3$

m r x 100

I

2) 1000 mR/hr (1R/hr) exposure:

o Condenser "R" reading = 110 mR/8 min = 825 mR/hr Correction factor is the same as 100 mR/hr expsoure = 1.02 o Actual condenser "R" reading = (1.02)(825 mR/hr) = 841.5 or 842 mR/hr o Control room meter reading = 800 mR/hr Relative error:

842 mR/hr -800 mR/hP x 100 5g m r

3) 5000 mR/hr (5R/hr) exposure:

o Condenser. "R" reading = 950 mR/ll min = 5182 mR/hr 0 Correction factor is the same as 100 mR/hr expsoure - 1.02 Actual condenser "R" reading = (1.02)(5182 mR/hr) = 5286 mR/hr o Control room meter reading = 5000 mR/hr o Relative error:

5286 mR/hr -5000 mR/hr m r 10,000 mR/hr (10R/hr) exposure:

o Condenser "R" reading = 1040 mR/8 min = 7800 mR/hr o Correction factor is the same as 100 mR/hr expsoure - 1.02 o Actual condenser "R" reading = (1.02)(7800 mR/hr) = 7956 mR/hr o Control room meter reading = 7750 mR/hr o Relative error:

7956 mR/hr -7750 mR/hr r x 100 = 5%

m

Conclusion:

All exposures are within + 20% relative error .

Equipment

1) 100 mR/hr (.1 R/hr) exposure:

Thermometer WPPSS 810158, Cal. Due Date 3-2-85, Case 8 19158-02 Barometer MPPSS 832854,- Cal. Due Date 8-3-84, Case P, 31859-02 Stopwatch WPPSS 039192, Cal. Due Date 12-22-84, Case 0 39192-02 Condense~ "R" Chamber 188-0.025R Cal. Due Date 10-14-84 8 12768

2) 1000 mR/hr (1 R/hr ) exposure:

Thermometer, Barometer and Stopwatch = Same as 100 mR/hr exposure Condenser "R" Chamber 130-0.25R Cal. Due Date 10-14-84 8 12750

3) 5000 mR/hr (5 R/hr) exposure:

Thermometer, Barometer and Stopwatch = Same as 100 mR/hr exposure Condenser "R" Chamber 552-25R Cal. Due Date 10-14-84 8 12270

4) 10,000 mR/hr (10 R/hr) exposur e:

Thermometer, Barometer and Stopwatch = Same as 100 mR/hr exposure Condenser "R" Chamber 552-2.5R Cal. Due Date 10-14-84 8 12270 Monitor Information o Monitor/Detector Serial Number: Type NA05 Catt 237X7316001 Serials TNNKG-029 o Control Room Module H13-604 o Background Before Calibration 0 mR/hr Background After Calibration 0 mR/hr High Voltage 240 volts

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(

an Attachment 8 a

ANSI 13.10 (Section 5.4)

MAIN STEAM LINE MONITOR System Descri tion The objective of the Main Steam Line Radiation Monitoring System is to monitor for gross release of fission products from the fuel passing through the main steam lines from the reactor to the high pressure turbine. Upon detection of a gross release of fission products fr om the fuel, this monitoring system initiates a prompt scram and isolation of the reactor.

Four gamma sensitive ion chambers monitor the gross gamma radiation from the main steam lines. The detectors are physically located near the main steam lines just downstream of the outboard main steam line isolation valves in the steam tunnel. The detectors are geometrically arranged so that the system is capable of detecting significant increases in radiation level for any number of steam lines.

5.4.1 Detection Ca ability Does not apply to this system. The gamma sensitive ion chamber is used for detecting gamma flux level. The chamber yeilds a direct current proportional to the gamma radiation level in which ates. Ionization chambers were chosen for these monitors as they it oper-will respond to mixed fissio n products and N-16 gammas.

5. 4.1.1

~ ~ ~ Detection in Gaseous Streams Does not apply (see 5.4.1 explanation).

5.4.1.2 Detection in Liquid Streams Does not apply (see 5.4.1 explanation ).

5.4.2 Range The instrument range is from 100 mR/hr to 106 mR/hr in 6 (six) evegly spaced decades. The input current range is from 3.33 x 10-'3 to 3.33 x 10-7 ampers. The range of the instrument pro-vides two decades of reading above the alarm setpoint that shuts off all steam flow. As these monitors are only required to read to three times background at 100% power, the range of the instruments are sufficient.

5.4.3 Sensi tivitg For a gama responding system that reads out in mR/hr the "Response Time" is the characteristic used for sensitivi+. The following is the system response times:

6 sec (3. 33 x 10-13 to 3. 33 x 10-12 amp) 1 sec (3. 33 x 10-12 to 3. 33 x 10-1" amp) 1 sec (3. 33 x 10-13 to 3. 33 x 10-7 amp)

For specific radiation levels, the conversion to ampers can be made by multiplying the radiation level by the chamber sensitivity (the normal sensitivity is 3.7 x 10-10 ampers/R/hr). The ranges stated above can be determined in mr/hr/R/hr by the same method. The RC time constant for the various decades can be found by dividing the response time by 2.2.

Accuracy Each detector was subjected to a 9.17 curie NBS Traceable Cs-137 source at approximate gamma levels of 100 mR/hr, 1R/hr, 5R/hre An NBS traceable calibrated set of condenser "R" chambers was used as the reference standard for determining Rt (true quantity) in the percent error equation. The following are the results of that determinati on.

Rt Rr Monitor Condenser "R" System Percent Number Reading Readi ng Err or (Correct E) 3C-TMV-52-026 100 mR/hr 86 mR/hr 14'X 930 mR/hr 1012 mR/hr 12%

4800 mR/hr 4587 mR/hr 5%-

3B-TMY-52-030 88 mR/hr 95 mR/hr -8X 927 mR/hr 824 mR/hr 11%

4625 mR/hr 4000 mR/hr 14%

3A-TMV-52-025 97 mR/hr 100 mR/hr 3%

950 mR/hr 900 mR/hr 6%

4900 mR/hr 4250 mR/hr 13%

3D-TNNK6-001 95 mR/hr 100 mR/hr 6%

940 mR/hr 910 mR/hr 3%

4400 mR/hr 4300 mR/hr 2X percent error =

~

The above was determined Rt - Rr using:

x 100

r 5.4. 5 Preci sion The system used is as follows:

1) Based on the source strength (total curies) and the conversion to R/hr exposures were made to estimate distances. The specific source was an Amerisham - Cs-137 source of 9. 45 curies.

Source strength at factory = 9.45 curies Source strength 471 days later on 12-9-83 = 9.18 curies From Rad Health Handbook - 10 curie source reads 3.3R/hr/meter.

Using this conversion a 9.18 curie source reads 3.026 R/hr/meter.

This information was used to determine the approximate distance the detector would be placed from the source center. The inverse square formula was used for these distance estimates with:

Il = 3.026 R/hr Rl = 1 meter I2 = Desired reading R2 = ?

The center of "a" condenser "R" chamber was placed at the center of R~. The exposure time was based on the condenser "R" chamber s range, requiring that the final exposure be above the mid point of the range. The exposure reading was then cor-rected for inherent error (as recommended by the mfg. ), baro-metric conditions and temperature. This result is Rt.

Each detector was placed, in turn, at the Rt location and exposed. This result is Rr.

The X

The is error =

~

final error determination is:

Rt - Rr t

x 100 definition of precision applies only to the distance from the traceable standard Rt.

Rr 5.4.6 Res onse Time Does not apply, but is the time in seconds stated for the specific decades in Section 5.4.3. The RC time constant would be that stated response time divided by 2.2.

5. 4.7.1 Temperature The detector temperature upper response = 200'C (392'F). This exceeds the ANSI criterion of 60'C. Logarithmic Radiation Monitor (LRM) temperature = 5 to 50'C and will be sufficient as the readout is in the Main Control Room that is habitable through all analyzed accidents.

.5.4.7.2 Pressure Detector operating pressure 250 psig or 12,925 torrs.

5.4.7.3

~ ~ ~ Humi di ty Relative humidity range for the LRM is 20 to 98% (with no condensa-tion). The chamber is not normally used where temperatures and humidity conditions are such that moisture cannot collect inside the connectors.

5.4.7.4 Other Environmental Effects Manufacturers specifications were followed for installation and operation. Industry history substantiates durability and resistance to adverse environmental effects.

5.4.7.5 Power Requirements The power supply is from a stable and predictable source (RDS, Reactor Protection System). In the event this power source is interrupted the one out of 2 taken twice logic initiates a "C" signal that prompts MSIY closure and reactor isolation.

5.4.7.6 Electrical Effects Not applicable 5.4.7.7 Mechanical Effects Not applicable 5.4.8 Radiation Alarm Not applicable 5.4.9 failure Alarm A HV-INOP Trip Circuit is employed on this system. The circuit will indicate a trip condition whenever the LRM high voltage level becomes abnormally low or whenever the front panel mode selector switch is in any position other than operate.

5.4.10 Cal ibra ti on The system was calibrated agains (using) NBS traceable condenser "R" chambers. A Cs-137 source of sufficient strength was used (see above) to allow a quantative response for three different intensi-ties. The system can be placed in any of four different test and calibration configurations (HiCAL, LOCAL, ZERO and TRIP TEST).

A secondary source is not used for the MSL monitors calibrations and placement of the Cs-137 source is controlled by measured placement of the detector in -the same configuration as the Condenser "R" chamber. This was more elaborately explained in 5.4.5, Precision, above.

The detectors are inspected and verified in working condition at time of receipt. System operation and readout adjustment is done at the time of radiological calibration. Trip functions are tenta-tively set at the time of radiological calibration and will be adjusted as backgrounds dictate, using calibrated electrical impulses as required by the MNP-2 Technical Specifications. No check sources are incorporated in this system.

Attachment 9 ANSI 13.10 REYIEW Primary Containment Air Monitoring Systems Sampl e Rack Detectors Ratem ter Recor der CMS-SR-20 CMS-RE-12-1A CMS-R IS-1 2-1 A CMS-RR-12A CMS-RE-12-3A CMS-R IS-12-3A CMS-RR-12A CMS-SR-21 CMS-RE-12-1B CMS-R IS-1 2-1 B CMS-RR-12B CMS-RE-12-3B CMS-RIS-12-38 CMS-RR-12B General Discri tion The Primary Containmnt Air Monitoring system consists of two redundant subsystems, one to measure particulates (1A and 1B), and one to measure noble gases (3A and 3B). Additionally, there is a charcoal cartridge in each subsystem to trap the halogens. These systems are used to monitor the concentration of noble gases and airborne particulates in the primary containment atmosphere during normal and most abnormal operating conditions but not accident conditions. The concentration can be related to the leak rate of primary coolant into the drywell. The major contributors to the activity are the noble gases, daughter s of noble gases, activated corrosion products, and fission products.

The sample for each sample rack is withdrawn form the drywell at the The 1 inch sample lines are equipped with isolation valves which 536'levation.

are located in the drywell and are heat traced. CMS-SR-20 obtains its sample near the containment wall at an azimuth of 195 . CMS-SR-21 obtains its sample at an azimuth of 45'. The isolation valves can be manually opened or closed from the control room at the rate meter. These isolation valves will automatically close and the sample pump will trip to off on a "F" signal (high drywell pressure greater than 2.0 psi ) or an "A" signal (low reactor water level). All trips and alarms must be manually reset before the monitors can be restored to operation. The flow through the sampling system is controlled manually by adjusting the bypass flow through the vacuum pump. The sample racks are located in separate rooms that are insulated and cooled to assure an environm nt that is acceptable for instrument operation after an accident.

At the sample rack, the sample passes through a particulate monitor, a charcoal cartridge, a noble gas mnitor, a flow aeter a vacuum pump and back to the drywell. There is also a sample pressure sensor in the sample rack that closes valves in the sample line and shuts off the vacuum pump and heat trace. This is separate from the isolation valving at the drywell.

The particulate monitors consists of a beta detector viewing moving tape filter in a 3 inch thick 4Tt'lead shield. The beta detector is identical to

'he ones used in the low range noble gas monitors and is described below. The moving tape filter is a 2.5 inch wide fiberglass backed cellulose filter. The filter tape speed can be set at 0.5, 1 or 2 inches per hour or manually

~

stepped in 3 inch increments. Normally the speed is set at 1/2 inch per hour.

~ ~ ~

The noble gas monitor consists a sample chamber containing a beta detector.

The sample, chamber which contains 2.2 liters of sample and the detector, is 4W shielded with 3 inches of lead. The flow indicator is a 0-6 SCFM rotameter with low flow detection/alarm capabilities. Normally the flow is adjusted to 4 cfm. The vacuum pump is a metal bellows type.

Each detector is a 2 inch diameter by 30 mil thick NE 102 plastic scintillator optically coupled to a photo-multipler tube and followed by a preamplifier.

The signal is sent to a 6 decade (10 to 107 cpm) log ratemeter which is located in the main control room. The ratemeter provides power to the detector, displays the counting rate, and provides alarm functions. The ratemeter has three internal calibration points and provisions to input a calibrated signal. An alarm test function is also provided.

A 1 ~Ci Cl-36 check source is provided at the detector for the noble gas monitors and a LED is provided at the detector s for the particulate monitors to check the overall system response. Both are actuated from the control room.

Recorders that continuously record the counting rates are provided in the main control room. The counting rate is also inputted to TDAS.

The CMS monitors are Seismic I, except for the detectors, and guality Class I qualified. However, they provide no control function and are not required to operate during or after an accident. -However, per FSAR Section 11.5.1.2.2 the CMS air monitors are to meet the criteria in FSAR Section 11.5.1.2.1 except item g. Comparison of the Primary Containment Air Monitoring Systems (CMS-RIS-12-1A and lB CMS-RIS-12-3A and 3B) to ANSI 13.10 "Standards of Performance".

Detection Ca abilities The Primary Containment Air Monitoring System consists of the redundant subsystems, one to measure particulates (lA and 1B), and one to measure noble gases (3A and 3B). Additionally, there is a charcoal cartridge in each subsystem to trap the halogens. These systems are used to monitor the concentration of noble gases and airborne particulates in the primary containment atmosphere during normal and most, abnormal operating conditions but not accident conditions. The concentration can be related to the leak rate of primary coolant into the drywell. The major contributors to the activity are expected to be noble gases, daughters of noble gases, activated corrosion products, and fission products.

The sample for each subsystem is. drawn from the drywell at the 536 foot level. The sample lines are 1 inch and are equipped with isolation valves at the drywell wall and also at the sample rack.

These sample lines are heat traced. Typically, the flow rate through each subsystem is 4.0 cfm.>

The four detectors are identical to each other and also to the detectors in all of the low range noble gas monitors. The detectors consist of a 2 inch by 30 mil thick NE 102 scintillator optically coupled to a PM tube and followed by a preamp. The noble gas detector is immersed in a chamber containing 2.2 liters of sample.

The particulate detector views a moving tape filter. The detectors and sample chamber or filter tape is shielded by a 4 A 3 inch thick lead shield. This type and thickness of scintillator maximizes the response to beta radiation while minimizing the response to gamma radi ation.

Since the containments air monitors are not effluent monitors, som of the requirements in ANSI 13.10 are not strictly applicable.

Specifically, the minimum detection levels given in ANSI 13.10, Table I and the required range of 104 MDL is not applicable.

Detection in Gaseous Streams The typical backgound count rat'e due to the expected concentrations of airborne activity in the drywell 'is not adequately defined at this time and must be based on experience. The follwoing provides the MDA and LLD based on the background observed at the time of calibration. The background, at least for particulate monitors, is expected to increase to a much higher count rate as fuel burn up increase and the leak rate approaches the limiting rate.

The CMS airborne monitors employe a shielded detector system to reduce the effect of ambient radiation levels and results in a low detection level. The LLD for these monitors was determined using the Technical Specification definition. The MDA's were determined using the method typically used in the industry and by the ANSI 13.10 method using the RC time constant. The LLD and the MDA's are expressed at the 95% confidence level. The time constant, per vendor specification, is 12 seconds on the first decade and 3.5 seconds on 'the second decade.

Detector Back- Calibration Tech Spec Typical ANSI 13.10 ground Factor LLD = 4.66 +Kg MDA = 1.96 ~/HRg MDA = 1.96 'g (cpm) YZF 1 2-lA 27 4.17E51 24 cpm 10 cpm 16 cpm 5.7E-5 uCi3 2.4E-5 uCi 3.8E-5 uCi 2.8E-12 uCi/cc4 1.2E-12 uCi/cc 1.9E-12 uCi/cc 12-1B '2 5.83E51 30 cpm 5.1E-5 uCi3 13 cpm 2.2E-5 uCi 20 cpm 3.4E-5 uCi 2.5E-12 uCi/cc4 1.1E-12 uCi/cc 1.7E-12 uCi/cc 12-3A 9 7.86E72 14 cpm 6 cpm 9 cpm 1.8E-7 uCi/cc 7.6E-8 uCi/cc 1.1E-7 uCi/cc 12-3B 110 7.86E72 49 cpm 21 cpm 61 cpm

6. 2E-7 uCi/cc 2.7E-7 uCi/cc 7/8E-7 uCi/cc

1. cpm/ uCi of Cs-137 on the filter.

2. 7.864E7 cpm/ uCi/cc is the efficiency provided by vendor for Kr-85 in the 104 cpm range. Field calibration indicates 12-3A reads 6% lower and 12-3B reads 1% higher.

3. D bl ii Hl pp LLD

4. This is the concentration that will deposit the detectable activity on the filter in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> at 3.0 cfm.

5.4.1.2 Detection in Liquid Streams No applicable.

5.4.2 Range The required range per ANSI 13.10 should be 104 MDA's is calculated by mul tiplying the MDA'a given in Section 5.4.1.1 by 104. The resulting values should be within the detector range 10 to 107 cpm.

Detector Tech Spec LLD Typical MDA ANSI 13.10 MDA 12-1A 2.5E5 1. OE5 1.6E5 12-1B 3. OE5 1.3E5 2.0E5 12-3A 1. 4E5 6E4 9E4 12-3B 4. 9E5 2.1E5 6.1E5 5.4. 3 Sensitivity The sensitivity (Ns = 1.96 ~g ) was calculated in section 5.4.1.1.

The time constants used were 12 seconds for the first decade and 3.5 seconds for the second decade.

5. 4. 4

~ ~ Accuracy For the two particulate monitors, a primary calibration was made.

This calibration. establishes the ratio of the transfer standard to the standard source used in actual counting geometry. The error in the primary source at the 95'X Cl is + 6%. The error associated with the counting rate of the transfer standard and the primary standard, based on two 5 minute counts of each source, is as follows:

12-1A Transfer Source Primary Source Net cpm Net cpm 81915 45453 81 655 45293 7 = 81785 7 = 45373

= + 130 1.96 6 = 0. 3g 1.96K= 0.3%,

x The summing the errors to get the total error:

= + 6'X Total error (6)2 + (0 3)2 + (0 3)2

Trans fer Source Primary Source Net cpm Net cpm 84076 63473 83383 63603 7 = 83729 7 = 63539 6 =+346 d =+66 1.96 o- = 0.8%

7 Total error = (6)2 + (.8)2 + (0 2)2 +

The 7 for the transfer source will be used at Rt in subsequent calibrations.

the formula 3 error =

Rt = counting

~

For the two noble gas monitors, the accuracy (Rt-R) vendor at the time t (100) was calculated using rate of the transfer standard established by the of primary calibration = 9.83E5 cpm/ uCi.

Rr = counting rate of the transfer standard when filed calibrated in cpm/ uCi.

12-3A X error = '

9.83E5 - 9.25E5 - 6%

12-3B 9.83E5 - 9.92E5

% error = 0.9%

Preci si on For the two particulate monitor the precision can be determined from the two 5 minute counts of the transfer standard.

12-1 A From Section 5. 4.4, 7 = 81785 cpm and d = 130 cpm.

1.966 = 255 cpm which is less than 10% of Y.

12-1B From Section 5.4. 4 7 = 83729 cpm and 6 = 346 cpm.

1. 964 = 678 cpm which is less than 10% of Y.

Since the detectors, countrate meter, etc., are identical, the precision for the two noble gas monitors will be about the same ma gni tude.

Res onse Time Not all of the CMS air monitors maintain background readings within the required accuracy for effluent monitors. However, these monitors do not monitor effluents.

Temperature The ratemeter, recorder, and power supply are located in the main control room. The control room is designed for human habitability under normal and analyzed abnormal conditions. The temperature in the control room will not exceed 104'F.

The sample racks are located in rooms which are insulated and cooled to assure an environment that is acceptable for the operation of these instruments.

Ratemeter - Per ventor specification, ~ O'X change over a temperature

~range o 0 - 60'0 (0-140 F).

Recorder - Per vendor specification, the normal operating range is- 4

-  %~40 - 120 F). The operating limit is 60'C (0-140'F).

The temperature effect is~0.2% of span for 40'F to 120'F.

Power Su ly (for Recorder) - Per vendor specifications operating range an hami s are t e same as for the recorder. The temperature effects are DC + 0.5% and AC + lX for a + 40 F based on 80 F midpoint operating range.

Detector - Per vendor specifications the normal operating temperature is 0 - 60'C (32-140 F). The effect on the calibration is not defined. The sample line is heat traced to 135 F.

Blower/Motor/Rotameter - The range of temperatures will have minimal e ect s any. e rotameter calibration changes with the density of air.

5.4.7.2 Pressure Except for the sample chambers and detectors, the components are open to room atmosphere. The vacuum in the drywell plus the vacuum head resulting from drawing the sample is seen across the 'detector.

This negative pressure drop is within the acceptable range. Upon positive pressure, the sample racks are isolated.

5.4.7.3 Humidity Detector (scintillator/preamp) - Vendor gives no operating

~spec> scations. Since storage in a humidity range 0-95% is approved by the vendor, operation in this range of humidities should be permissible. The calibration and accuracy will not affected.

Other com onents at skid - The motor, blower, flow meter etc. should not e a ecte y um> ity.

Ratemeters/Recorders - No effect expected on the ratemeters or recor ers ecause o the controlled atmosphere in the Control Room.

5.4.7.4 Other Environmental Effects There are no anticipated environmental conditions that will cause a f f si gni i cant e feet on these moni tors.

5.4.7.5 Power The detector including preamps, ratemeters, and recorders are powered from instument power buses in the control room. This power supply is stabilized and variations of 15~ will not be seen.

Per Kaman specs: for the ratemeter 90 - 130 VAC, 50-60 Hz is acceptable. Kaman spec for the recorder power supply and recorder indicate that the recorder would easily meet a -10K + 5% variation in power supply.

Motors/blowers - no significant effect.

5.4.7.6 Electrical Fffects This has been a problem. Kaman instrumentation specs indicate that the power supply for the recorders are sensitive to RF. Exper ience indicates that the system is sensitive to RF generated at either the sample rack or the ratemeter location. The use of radios is being controlled administrati vely to eliminate this problem.

5. 4.7.7 Mechanical Effects Except for the detectors, the CMS air sampling systems are Seismic Class I. The detectors are identical to detectors that have been

.qualified. Therefore, this requirement is met.

~ I ~

5.4.8 Radiation Alarm The ratemeters are equipped with two upscale alarms (Hi and Xi Hi )

which can be set at any point over the range of the instrument.

These alarms are latching type and must be manually reset. The alarms illuminate a light at the ratemeter and open a solenoid which causes a trouble light on an annunciator panel to illuminate and a buzzer to sound. The alarms are reset and the setpoint of each alarm can be checked from the face of each count ratemeter.

The Hi and Hi Hi alarm points can be adjusted at the meter face.

The low high voltage alarm and the downscale alarm setpoints are adjusted internally but the instrument does not have to be removed from service to adjust them.

5.4.9 Failure Alarm The ratemeter provides a latching alarm in case of power failure, HY below the HVINOP setpoint, or counting rate below a setpoint value.

5.4.10 Cal ibrati on A. Particulate Monitors a) The primary calibration of the particulate monitors was performed on site by counting a NBS traceable Cs-137 beta source in the filter chamber.

, b) A transfer standard source (Sr-90) and three linearity sources (also Sr-90) which are also NBS traceable were counted. These sources were precisely and repr oducibily positioned under the detector using a vendor furnished "calibrator" calibration jig. The linearity sources are used to determine response vs. activity.

The response vs. beta energy was investigated using a Pm-147, a Tc-99, a C1-36, and a Sr-90 source.

c) The surface area of the transfer standard is not the same as surface area of the detector window. The transfer standard source and the linearity sources are about 1 inch in diameter. The detector to source geometry in the calibrator is precisely maintained and is reproducable. The transfer standard count will be used as the basis of subsequent: period calibrations.

d) DOP testing - An exception was taken to the ANSI 13.10 criteria in the December 8, 1983 memo.

e) The flow rate measuring devices were calibrated 9/83.

The particulate monitors have a LED at the detector to check the overall response of the system. The noble gas monitors have a 1 uCi Cl-36 check source. Both of these devices are activated from the ratemeter.

g) Calibrated electronic signals are provided by the ratemeter and externally generated signals can be inputted at the ratemeter.

B. Noble Gas Monitor a) NBS Traceable th Three each pi y of 133Xe and 8 Kr NBS 1ih ti . Ph g into the known volume standard Kaman gas chambers. The detectors it certified gases d d used were "generic" Kaman beta scintillator units. The counting and analysis, carried out on the WNP-1 digital system, was completed and entered onto claibration report sheets. This report was forwarded to WNP-2 as part of the equipment package. The total calibration errors, including NBS gas calibration errors, ranged from 9.7%, a low activity sample, to 1.6%, a high activity sample at the 95%

confidence level.

b) Transfer Calibration Sources - Disk sources of 90Sr were used at t e same time as t e a ove mentioned gas calibration. A response factor was d veloped relating 90Sr to Kr4 . A further study g 25 different detectors response to the primary and secondary "~Sr transfer sources indicated the true "generic" quality of the detectors. A mean error of 2.6% and 4.3'X respectively at the 95%

confidence level indicates a very good group. Further, the response to Kaman's standard and WNP-1 's secondary transfer sources were within 0.6% at 95% C.L. These secondary sources were and are periodically analyzed on beta detectors which are calibrated with NBS and NBS traceable sources.

c) Constant Geometry - The vendor, Kaman, has a shielded portable cons ant geometry rack (field calibrator). Demonstrated reproducability of source placement is within +0.3%.

d) DOP Testing - There is peg.gght to the ANSI tig t di d no 13.10 criteria in the December 8, 1983, dpi anticipated problem of noble gas and memo.

tt e) Flow Rate Devices - Each sample skid has a rotometer that ranges rom to c, a measureable range of 0.5 to 5.5 is repeatable within 20% at any reading.

to Coupled to flow rate measurement is the pressure measurement on each monitor skid. Each skid is provided with a vacuum gauge that reads from 0 to 30 inches at + 2% of reading according to the vendor.

Check Source - unit has a solenoid activated check source in pPP6tt Each th 1 id 1 d h llid d 1 the control room.

g) Electronic Calibration Si nals - Each RIS module has 1) an internal osci a r ic a ows a sweep across the output range for alarm test and 2) a calibration signal input (pulse) for accurately establishing the setpoints.

Attachment 10 ANS I 13.10 COMPARISONS Intermediate Range Monitors REA-RIS-19A TEA-R IS-13A MEA-RIS-14A 5.4.1 Detection Ca abil ities

.The monitors in this report are an offline noble gas detection unit. These monitors are intended to extend the range of the normal range monitors. This is accomplished by a switching valve which is activated as long as a Hi Hi trip is indicated on the low range mon-itor. The normal sample flow is then allowed to be sensed by these monitors. The units have a modified beta scintillator, the coupling between the beta scintillating plastic and the photomultiplier tube is decreased. It also allows for further sensitivity refinement by altering the high voltage operating point. To ensure only noble gases are detected, particulate filters and charcoal cartridges are placed ahead of the detector. The detector senses the radiation and returns a current signal to the RIS module. The sampled gas is routed to the normal monitoring system exhaust port.

5.4.1.1 Detection in Gaseous Streams t

These monitors, when placed on line, will continuously monitor a sample of the effluent stream. Their purpose is to extend the range of gaseous activity to assure continuous monitoring during an acci-dent situation will occur. The MDL used in the following table will be upper range of the low range monitor. See Table 1 for a sumary of system parameters.

5.4.1.2 Not applicable 5.4.2 ~Ran e The range requirement is exceeded; see Table 2.

5.4.3 Sensi tivity The sensitivity is noted as uCi/ml in Column 7, Table 1, also in Table 2.

J A

A

~

ANSI 13.10

~ Comparison: Table 1

~

Background Ca1ibrgIoo Detection Limits in uCi/ml

( Ins tall ed) factor

~

,CF Detector Isotope PMU PMU/uCi/ml~l) Tech. Spec. Normal ANSI 13.10 Long Range (2) Monitor OMA (3) OMA/Log(uCi/cc ) LLII= 4.66 Sb 1.96 Sb 1.96 Ns Sb pmu(4) NDA= NDA= CN Upper Limit Sb orna uCi/cc REA-R IS-1 9A Xe 1 (0.714) 144. 2 (1 ) 6.93E-3 uCi/cc 6.93E-3 uCi/cc (4) 0. 28

0. 892 1.11374 (2) 1.79E-3 uCi/cc 1. 77E-3 uCi/cc 1 (3.69E-3)

. 001 81 TEA-RIS-13A 133Xe 1 (0.622) 102.5 (1) 9.76E-3 uCi/cc 9.76E-3 uCi/cc 0. 23 0.745 1. 25007 (2) 7.14E-3 uCi/cc 5.48E-3 uCi/cc.

1 (0.0584) 0.034 MEA-RIS-14A 133Xe (0.751) 106.7 (1) 9.37E-3 uCi/cc 1 9. 37E-3 uCi/cc (4) 0. 23

0. 735 1.12843 (2) l. 23E-3 uCi/cc 1.21E-3 uCi/cc 1 (4.98E-3)

0. 00247 Notes: l. PMU means panel meter units.

2. The calibration factor for PMU/uCi/cc is calculated for 1 uCi/cc. The calibration factor for OMA, which is now measured in volts, is the slope of the semilog plot; the intercept must also be used.

3. The lowest scale reading on the panel meter is 1, this is used for the MDA, LLD limit.

4. The electronics is not a pulse system. The MDS results in the normal column will apply.

r 5.4.4 Accuracy The systems described in this report were calibrated with 33Xe gas. The gas was introduced into the system, circulated until no activity or voltage changes were apparent. Two gas samples were removed and analyzed on a HPGe system with an ND6620 analyzer. This was repeated, for each level of 1>>Xe gas level. See the indivi-dual reports for primary calibration errors. The calibration pro-cedure requires instruoent to meet the + 20 percent accuracy as defined by (RR -RT) x 100/RT. Recorder accuracy is + 1% of span.

5.4.5 Precision The precision of this instrument is stated to the + 20 percent on all ranges by the vendor. The precision indicated in Table 2 is that of a series of solid source activations, the data indicates the

+ 20 percent error can be bettered.

5.4.6 Res onse Time These rmnitors are used to indicate accident situations and have no control functions. The response time is constant for all ranges; is two seconds.

it 5.4.7 Tem erature The RIS module, low voltage power supply and recorder are located in the Nain Control Room. The Control Room is designed to be habitable under normal conditions; see Technical Specification 3/4.7.2, an 85 F (29.4 C) limit. The FSAR limit is 104 F (40'C). For the al-lowable temperature range, calibration drift would be very small and is typically ignored.

5.4.7.1 ~T The detector module, which houses the high vol tage supply utilizes temperature compensating components. The overall range at the unit is from -20'C to 50'C. The recorder has a normal range from 15 to 40 C, extreme range fro -9 to 50 C without loss of accuracy.

5.4.7.2 Pressure The vendor pressurized the system for 10 minutes at 5 PSI, no pres-sure loss was indicated. During calibration a vacuum test was made. The systems were able. to hold a 10 inch mercury vacuum.

5.4.7.3 Humidity No statement by vendor about the humidity range for operation. How-ever, moisture condensing out inside the detector will cause circuit board damage. The recorder humidity range is from 0 to 90% relative humi di ty.

$e ANSI 13.10 Comparison: Table 2 Monitor Range Sensitivity Accuracy Precision (1) Meter Scale N5 = 1.96 (Nb/2 RC)1/2 R - R Yn n = number of (2) Voltage Output (1) uCi/cc ~

100% determinati ons (3) 133Xe (meter)uCi/cc MDA to MDA x 104 Primary Cal = N/A + X error at 1 6 (4) "33Xe (voltage)uCi/cc'es or No REA-R IS-1 9A 1 to 105 (1) 6.80E-3 at 1 PMU Y3 + 0.21'X 0.714 to 5.0 (2) 9.49E-4 (volt) 6.93E-3 to 9.63E+2 (3) 104 Range Yes 1.77E-3 to 3.16E+2 (4)

TEA-RIS-1 3A to 105 (1) 9.56E-3 at 1 PMU 1 N/A 74 + 0.45'X 0.622 to 5.0 (2) 7.62E-4 (volt) 6.76E-3 to 9.76E+2 (3) 104 Range Yes 7.14E-4 to 8.06E+2 (4)

WEA-RIS-14A 1 to 105 (1) 9.18E-3 at 1 PMU N/A 74 + 0.11%

0.745 to 5.0 (2) 1.)6E-3 (volt) 9.37E-3 to 9.37E+2 (3) 10" Range Yes 1.23E-3 to 5.24E+2 (4)

Note 1: This module does not meet the noram1 description for the units used in the sensitivity equation.

Corrosive Atmos here No specification and no corrosive atmospheric conditions are expected. ~

Power Requirements The detector and associated electronics in the detector casing derive their power from the ratemeter module. The ratemeter module requires 115 VAC, 60 cycle, 15 watts maximum. No specification about the range of voltages was made.

The recorder power requirements are 120V (107 to 127), 50/60 Hz.

Electrical Effects RIS module was not tested due to ban of radios in the Control Room at the time of calibration. Vendor states "the instrument will not respond to stray electromagnetic or electrostatic fields such as generated by a diesel engine or an electric overhead crane". No statement made about effect of RFI on the recorders was found.

Mechanical Effects The intermediate range noble gas monitors were designed for seismic category II qualification.

Radiation Alarms The ratemeter is equipped with two upscale alarms which can be set at any point over the range of the instrument. The circuitry latches the alarm even though the detector input may have returned to normal; the alarms must be manually reset. There are two alarm lights on each module. There are no additional off board alarms.

There is an alarm test circuit that ramps the RIS in order to check the alarm trip points. Alarm trip points may also be checked by depressing the appropriate alarm reset pushbutton and holding.

Failure Indicators A downscale or H.Y. failure light (INOP) is on each RIS module which illuminates when tripped. A signal will be sent to Board S, Ann Panel P851-S1 to illuminate a BD-RAD-24 trouble light and a buzzer will sound. The failure indicator must be manually cleared.

V~

d A

4

~

ibrati on

~

5.4.10 Cal Primary calibration consisted of introducing 133Xe gas into the detector chamber via a gas rack, then pumping the gas through the closed loop. Upon the count stabilization, two samples were withdrawn by use of inline 100 cc gas vials. This was done for three points in or der to develop a calibration curve. The samples w re then analyzed on a HPGe detector and ND6620 gamma analyzer. The gamma analyzer and detectors have been calibrated with NBS traceable gas samples provided for by an outside laboratory. Additional calibration was done by uti-lizing liquid sources in the same geometry and comparing ali-quots of the liquid solution directly with NBS certified sources. The two calibrations are within a five percent err or. The individual gas samples were analyzed for a time to attain 50,000 counts or better in the 133Xe 81 Kev peak; thus counting statistics would become an unimportant error.

b. The transfer calibration sources are 137Cs sources fabricated in-hguge. Their activities were determined directly against the ~3~Cs NBS reference standard utilizing the high resolu-tion gamma analyzer system. The set of trangfgr/linearity sources includes one NBS reference standard '3'Cs.

c~ The transfer and linearity sources are positioned on the face of the detector and centered. Source repositioning has been reproducable to better than 0.3X.

d. DOP Testing There is no anticipated problem with noble gases and sample lines. DOP testing is not required.

e. The flow rate monitor is an air velocity monitor. It is rated at 2X accuracy of full scale. The flow range is from 0 inches to 8 inches of water. This unit acquires the noble gas sample from the low range noble gas detector. When switched, the flow meter on the WEA can be used and the flow controllers on the REA and TEA system can be used. The flow meter on the off skid locations are accurate to + 10% of its reading.

Check Sources This unit does not have a radioactive check source. Instead utilizes a pulsed LED from an oscillator circuit housed in the it detector assembly. The oscillator is controlled from the RIS module in the Control Room.

g~ Electronic Calibration Same as f above. The oscillator can be controlled by a front panel switch on the RIS module'to calibrate the panel meter and the 4-20 ma output signals.

4 ~

Attachment 11 ANSI 13.10 (SECTION 5.4)

REACTOR BUILDING EXHAUST PLENUM RADIATION MONITORING SYSTEM SYSTEM OBJECTIVE The objective of this monitor ing system is to monitor the concentration of radioactivity in the reactor building ventilation system exhaust duct prior to its discharge from the building. To initiate appropriate action in the event pre-determined activity levels are exceeded.

SYSTEM DESCRIPTION The system consists of 4 seperate monitoring channels, each with:

o a GM detector o indi cator and tri p unit o Recorders, with channel ABC and BSD sharing a recorder respectively The indicator and trip unit is arranged in a one-out-of-two logic with:

o Radiation High High (RAHH) trip in channels A or C causing standby gas treatment train "A" to start and the outboard primary containment vent and purge valves to close (if open) - and - the outboard reactor building ventilation valves to close (if open).

o RAHH in either channel B or D will cause standby gas treatment train "B" to start and the inboard valves as mentioned above to close.

There are sources (bugs) installed at the sensor (approximately 0.2 uci Sr ) to provide a small upscale reading (live zero).

The following are the control room panels where the meters (readouts) are 1 ocated:

REA-RIS-609A (Channel "A"); Panel H13-P606 REA-RIS-609C (Channel "C"); Panel H13-P606 REA-RIS-609B (Channel "B"); Panel H13-P633 REA-RIS-609D (Channel "D"); Panel H13-P633 5.4.1 Detection Capabil i ty Included in a seperate packet is the Z calculation for the plenum monitoring system. The summary on Page 1 of the packet substan-tiates that Cs-137 is the correct isotope for calibration as the energy from accident initiation and the preceeding hour is almost identical to the Cs-l37 gamma energy, .669 mev vs..661 mev respectively.

5.4.1.1 Detection In Gaseous Steams This monitoring system monitors the reactor building final effluent stream for the purpose of initiating a signal (when tripped) that isolates secondary containment and starts standby gas (see "SYSTEMS DESCRIPTION" above). When the series of events occur initiating a trip signal, this monitoring system is no longer required to func-tion. Included are two packets that provide isotopic profiles for the systems'peration, they are:

o Setpoint calculation for reactor building plenum monitor o Z calculations for the plenum monitor .

5.4.1.2 Detection In Li uid Streams Not Applicable 5.4. 2 ~Ran e The monitoring system has a range of 10-2mr/hr to 102mr/hr in 4 (four) evenly spaced decades. The monitor's respond to energy from 80 Kev to 7 mev with the average energy dependence of + 20% over 100 Kev to 3 mev. The criteria of 104 MDA is not applicable for this function.

5.4.3 Sensitivity As this monitoring system performs an isolation and system initiat-ing function it is approprate to consider the time when the monitor-ing system is tripped and completes those functions. All instrument and valve closure times meet the less than, or equal to, 13 sec time limit as indicated in Sections 3/4 3.2, "ISOLATION ACTUATION INSTRU-MENTATION" and 3.6.5.2, "SECONDARY CONTAIhNENT AUTOMATIC ISOLATION VAI VES" of the WNP-2 Technical Specifications. This indicates that the sensitivity of the system is capable of performing their designed function.

5.4.4 Accuracy Each detector was subjected to a 96 mci Cs-137 source at the below mentioned distances. The distances and source intensity were matched to facilitate responses on the lower and near the upper ends of the condenser "R" scale. The results are as follows: A NBS traceable set of condenser "R" chambers was used as the reference standard for determing Rt (true quantity) in the percent error equation:

percent error = (R - R ) x 100 t

Where:

Rt = true value Rr = indicated quantity Rt "R" Rr Condenser System Corrected Reading Channel ~Readin Control Room Percent Error A 87.9 mr/hr 80 mr/hr 9%

13.4 mr/hr 12 mr/hr 11'5 A

B 81 mr/hr 90 mr/hr ill B 12.4 mr/hr 13 mr/hr O'X C 83 mr/hr 90 mr/hr 8%

C 15 mr/hr 15 mr/hr No Error D 61 mr/hr 65 mr/hr 7'X D 16.8 mr/hr 16 mr/hr 3'X The above Rr were taken from the control room meters (readouts) and the chart (recorder) presentations. The meters and charts tracked the same.

5.4.5 Prec" sion The system used to determine precision is as follows:

A 96 mCi C-137 source was hung inside the plenum. The source can be moved to as close to the detectors as possible and at approximately 65" away from the detector, 65" being the most manageable distance before being hampered by the duct (plenum) wall.

The approximate distances of 65" and 25" were chosen because:

1. They tested both lower and upper sections of the systems'oni-toring scale.

2. Provide points that allowed electronic adjustment of the "0" (zero) and SPAN.

A set of NBS tracable victoreen condenser "R" chamber was used as the standard for the percent error evaluations. A condenser "R" chamber was exposed for times that, allowed the final exposure to be near or above the middle of it's scale.

Using the classic relative error formula (Rt - R) x 100 = 'X error Fg The above determinations were made.

The above procedure was conducted individually for each of the four detectors. The measuring, timing and environmental devices (used for temp and barometric pressure correction factors) were the same for all exposures. The results and percent error calculations are clustered such that precision is displayed by their consistancy and repeatabil i ty.

5.4.6 Response Time Does not apply as an instrument response time only. This, monitoring system performs definite protective functions - and - it is more appropriate to consider the entire system's response time. The relay response time is 10 milliseconds to an input step of 100 microamperes. As stated in the sensitivity system, this monitor performed their required trip function initiation within the time limitations.

5.4.7.1 Tem erature The operating temperatures are as follows:

o Monitor - 0 to 50'C o Detector preamplifier - 30'o 70'C 5.4.7.2 Pressure The detector is capable of continuous operation under 500 to 2500 torr pressure.

5.4.7.3 Humidity This system is not used where temperatures and humidity condi tions are such that moisture can not collect inside the connectors or the detectors.

5.4.7.4 Other Environmental Effects Manufacturer's specifications were followed for installation and operation. Industry history substantiates durability and resistance to adverse environmental effects. This is a seismically class I system and the detectors are supported accordingly.

5.4.7.5 Power Requirements

- The power supply is from a stable and predictable power source.

the event this power source is interrupted the 1 out of 2 taken twice logic initiates a "Z" signal that prompts system trip In acti vation.

5.4.7.7 Mechanical Effects Not Applicable .

5.4.8 Radiation Alarm Not Applicable 5.4.9 Failure Alarm A HV-INOP trip circuit is employed on this system. The circuit will initiate a trip condition whenever the high voltage level becomes abnormally low.

5. 4.10 Calibration Prior to conducting a radiological calibration the following instru-ment calibration and preparation is made:

o Power supply and response is checked o Set amplifier "0" o Check meter and recorder response and condition o Check and set trip alarm set points o Perform all vendor recommended test and preparations

~ ~

gzy A'z - Yn'z c,g WASHINGTON PUBLIC POWER SUPPLY SYSTEM r-"c

)NTt:-PQFRCE MEMGRANDUM DISTRIBUTION: MAIL DROP:

P V~NP-1 FILE DATE: January 3, 1984 Q Mr'NP.2 FILE.

WNP-3 FILE To: Yern Shockley Q ADMIN. FILE FRDM: Dave Ot "B"E T: Z CALCULATIONS FOR G~ JD DE Parry Larson 1020 1020 THE PLENUM MONITOR D Ottley/lb 1020 Rad Prog Files 1020

1) F.E. Owen to R.G. Graybeal 3-9-83, "Radiation Monitor-Control Room Intake and Reactor Building Plenum" 50E-FEO-83-006 As per your request, the Average Gamma Energy K for the radio-nuclides expected within the Reactor Building Plenum Monitor was calculated.

Four scenarios were used:

Routine Release .364 MEY LOCA 1 hour .669 MEY LOCA 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> .309 MEY LOCA 1 day .157 MEY These were also compared with the E's, previously estimated in Reference 1, based on isotopic percent concentration.

Isotope and curie content for the routine release scenario was obtained from the WNP-2 FSAR Table 11.3-7, "Gaseous l<aste System Release". For the LOCA scenarios, content was obtained from FSAR Table 15.6-13, "Loss-of-Coolant Accident" (Design Basis).

The nuclide concentration was multiplied by the approximate energies and photon abundances obtained from the Radiological Health Handbook and summed, thus calculating the Z.

The attached summary and accompanying tables can be consulted for detailed calculations. If you have any questions, please call me at 8048.

Z CALCULATIOH, PLENUM i!0tlITOR, SUt~iYiARY Routine LOCA LOCA LOCA Release 1 Hr. 8 Hr. 1 Day REF

. 469 .149 . 081 Kryptons . 057 .294 .072 .002 Xenons .305 .102 .076 .048 Iodines .002 273 .161 .089 Total .364 MEY .669 NEV .309 HEY .157 YiEY

-1

E CALCULATIOH, PLENUM MONITOR, ROUTINE RELEASE CURIE MEY CONTRIBUTION ISOTOPE (FROM FSAR) COIICEIITRATIOH (FROH RHH) ABUNDANCE MEV Kr-85m 3 l .018 .150 .74 .002 l .305 .13 .001 Kr-87 3 I .018 . 403 .84 .005 I 2. 57 .35 .016 I .85 .16 .002 Kr-88 3 .018 2. 40 .35 .015 I .19 .35 .001 I .85 .23 .004 I 1.15 .14 . 003 I 2.19 .18 .007 l

XB-133 66 l .405 .081 .37 .012 Xe-1 35m 46 I . 282 . 527 .80 .119 Xe-135 34 I . 209 . 250 .91 .047 I .61 .03 .004 Xe-138 7 .043 .16 .33 .002 I .26 1.00 .011 I .42 .40 .007 I .51 .08 .002 I 1.78 .66 .051 l 2.02 .58 .050 I

~ ~ ~ C

~ ~

Z'ALCULATION, PLENUM MONITOR, ROUTINE RELEASE (Continued)

CURIE t~iEY CONTRIBUTION ISOTOPE (FROll FSAR) CONCENTRATION (FROM RHH) ABUHDAHCE ViEV I-131 .17 .82 I-133 '68 I

. 001

.004

. 364

.53 .90 .002 I

COl '

+.01 I

Particulates $ .01 I C. 01 I

Subtotal s I Krypton's . 054 . 057 Xenon's .939 .305 Iodine's . 005 .002 TOTALS 1. 00 .364 c = .364 NEY i'I I,

~ ~

JALCULATIOH, PLENUM MONITOR, 1 HOUR CURIE NEV CONTRI BUT IOt<

ISOTOPE (FROM FSAR) COHCENTRATIOH (FROM RHH) ABUNDAt/cE IIEV I-131 2. 2E7 I . 030 '. 364 .82 .009 I .637 .07 .001 I

I-132 2.4E7 I .033 .67 1.44 .032 I . 773 .89 .023 I .955 .22 .007

.52 .20 .003 I -133 4. 7E7 .064 .53 .90 .031 I-134 2.6E7 I .036 .85 .95 .029 I .89 .65 .021

.55 .08 .002 I'.15 I

I .41 .08 .001 I .61 .18 .004

'10

.004 I 1. 79 .05 .003 I 1.62 .05 .003 l 1. 46 .04 .002 I-135 4.0E7 I .055 1.14 .37 .023 I 1.28 .34 .024 I 1.72 .19 .018 I 1.46 .12 . 010 I 1.80 .011 I .86 .005 I 1.04 .09 .005 I .07 .002

K CALCULATION, PLENUM MONITCR, 1 HOUR (Continued)

CONTRIBUTION CURIE MEV ISOTOPE (FROM FSAR) CONCENTRATION (FROM Rl+I) t)EV Kr-83m 9.9F6 I . 014 . 009 .09 Kr-85m 3.8E7 I .052 .150 .74 . 006 I . 305 .13 . 002 Kr-85 I . 002 .514 ,41 Kr-87 I . 064 . 403 . 022

2. 57 .35 . 058 I .85 .16 . 009

8. 6E7 I . 118 2. 40 .35 . 099 I .19 .35 . 008 I .023

.85'.15 I .14 . 019 I 2. 19 .18 .047 l .17 .07 .001 Kr-89 2. 6E2 .0000004 .23 .85 l 1. 00

E CALCULATIOW, PLEWUM llONITOR, 1 HOUR (Continued)

CURIE HEY CONTR IBUTIOW ISOTOPE (FROtl FSAR) COWCEWTRATIOH (FROM RHH) ABUNDAWCE HEY Xe-131m 9.0E5 . 001 .02 Xe-133m 4. 7E6 I .006 2.33 .14 Xe-133 1 9E8 I . 260 .081 .37 .008 Xe-135m 3.6E6 .005 . 527 .80 .002 Xe-135 1 ~ 7E8 I . 233 2. 50 .91 .053 I .61 .03 .004 Xe-137 3. 5E3 I .000008 . 455 .33 Xe-138 8.8E6 I .012 .16 .33 .001 I .26 1. 00 . 003 I .42 .40 .002 I .51 .08 . 001 I 1. 78 .66 .014 I 2. OZ .58 .014 I

t Subtotal s l Iodine's .218 .273 Krypton's .25 . 294 Xenon's . 517 ,102 TOTALS .99 .669 Z = .669 MEV

K CALCULATIOt), PLENUM t<OHITOR, REF. 1 1 HOUR ISOTOPE CONC EHTRATIOH EHERGY ABUHDAHCE COt/TRIBUTIOtt (NEV)

Kr-83m .02 . 009 .09 Kr-85m .04 .150 .74 .004 Kr-87 .05 . 403 .84 . 017

2. 57 .35 .045

.85 .16 .007 Kr-88 2. 40 .092

.19 .35 .007

.85 .23 .023 1.15 .018 2.19 .18 .043

.17 .07 .001 Xe-133m .01 2. 33 .14 Xe-133 .48 .081 .37 .014 Xe-135m .12 .527 .80 .051 X'-135 .13 . 250 .91 .030

.61 .03 .002 Xe-138 .04 .16 .33 .002

.26 1.00 . 010

.42 .40 .007

.51 .08 .002

1. 78 .66 .047

2. 02 .58 .047 1.00 .469 tKY

E CALCULATION, PLENUM MONITCR) 8 HOURS CURIE MEV CONTRIBUTION ISOTOPE (FROM FSAR) CONCENTRATION (FROM RHH) ABU'ADANCE MEY I-131 2 1E7 I  ; 053 . 364 .82 . 016 I . 637 .07 .002 I-132 2-9E6 I . 007 .67 . 007 I . 773 .89 .005 I . 955 .22 I .52 .20 .001 I-133 3. 7E7 . 093 .53 .90 . 044 I-134 1. OE5 I . 0003 .85 .95 I-135 1. 9E7 . 048 1. 14 .37 . 020 I 1.28 .34 . 021 I 1. 72 . 016 l 1. 46 .12 t 1.80 . 010 I .86 . 005

l. 04 . 004 I .42 .07 . 001

E CALCULATION, PLENUM MONITCR, 8 HOURS (Continued)

CURIE MEV CONTRIBUTION ISOTOPE (FROM FSN) CONCENTRATION (FROM RHrl) ABUNDNCE MEV Kr-83m 7.2E5 t . 002 . 009 .09 Kr-85m 1. 3E7 I . 033 .150 .74 ..004 I . 305 .13 . 001 Kr-85 I .004 Kr-87 1.0E6 l . 003 . 403 .84 . 001

2. 57 .35 . 002 Kr-88 1. 5E7 I . 038 2. 40 . 032 I .19 .35 .003 I .85 .23 . 007 I 1.15 . 006 1 2. 19 .18 .015 Kr-89 l .60 1.00 I

I l

E CALCULATION PLENUM MONITOR 8 HOURS (Continued)

CURIE MEY CONTRIBUTION ISOTOPE (FROM FSAR) CONCENTRATION (FROM Rl+l) ASUiilD ANCE MEY Xe-131m 8. 8E5 I . 002 . 164 Xe-133m . Oll .14 Xe-133 1. 4E8 I . 475 . 081 . 014 Xe-135m 1 9E2 l . 527 .80 Xe-135 1.0E8 I . 250 . 250 .91 . 057 I .61 .03 .005 Xe-137 I 4. 55 Xe-138 1.1E2 I 2. 02 .58 I

I Subtotals I Iod'e 's . 201 .161 Krypton's .08 . 072 Xenon's . 738 . 076 TOTALS .309 E = .309 MEY 10

E CALCULATIOH, PLEHUth NOHITOR, REF. 1 8 HOURS ISOTOPE COHCEHTRATIOH ENERGY ABUWDAHCE COHTRIBUTIOH (YiEY)

Kr-83m .01 . 009 .09 Kr-85m .02 .150 .74 .002 Kr-87 2. 57 .35 Kr-88 .02 2. 40 .35 .017

.19 .35 . 001

.85 .23 .004 1.15 .14 .003 2.19 .18 .008 Xe-133m .01 2.33 .14 Xe-133 .61 .081 .37 .018 Xe-135m .08 .527 .80 .034 Xe-135 .25 .250 F 91 .057

.61 .03 .005 Xe-138 2.02 .58 1.00 149 HEY

2 CALCULATION) PLENUM MONITCR ~ 1 DAY CURIE MEV CONTRIBUTION ISOTOPE (FROM FSAR) CONCENTRATION (FROM Rm) ABUNDANCE MEV I-131 2. OE7 I . 077 . 364 .82 . 023 I . 637 .07 .003 I-132 2. 3E4 I . 00009 l. 44 I-133 2.2E7 l . 085 .53 .90 . 040 I-134 3. 2E1 I .85 .95 I-135 I 1.14 .006 I 1.28 . 006 I 1.72 .19 .004 I l. 46 .12 . 002 I 1. 80 .003 I .86 . 001 I 1.0 09 .001 l

Kr-83n 1.8E3 l .000007 .009 .09 Kr-85m 1. 1E6 I . 004 . 150 .74 Kr-85 1.4E6 . 005 . 514 .41 .001 Kr-87 1.6 2 I 2. 57 .35 Kr-88 2.9E5 . 001 2. 40 .35 . 001 Kr-89 l .60 I

I

E CALCULATIOH, PLENUM MONITOR, 1 DAY (Continued)

CURIE YiEV COHTRI BUT ION ISOTOPE (FROM FSAR) COHCEHTRATIOH (FROtl RHH) ABUt<DAt<CE r lEV Xe-131m 8.5E5 . 003 .164 .02 Xe-133m 3.5E6 ) .013 .233 .14 Xe-133 1.7E8 I . 654 .081 .37 .020 Xe-135m I .527 .80 Xe-135 3. OE7 .115 . 250 .91 . 026 l .61 .03 .002 Xe-137 I 4. 55 .33 Xe-138 I 2.02 .58 I

Subtota1s I Iodine's .175 .089 Krypton's .01 .002 Xenon's .785 .048 TOTALS .97 .157 7 = .157 MEV K'ALCULATION, PLENUM l<OHITOR, REF. 1 1 DAY ISOTOPE CONCENTRATION ENERGY ABUNOAt(CE CONTRIBUTIOH (MEV)

Kr-83m . 009 .09 Kr-85m .150 .74 Kr-87 2. 57 .35 Kr-88 2.40 .35 Xe-133m .01 2. 33 .14 Xe-1 33 .76 .081 .37 .023 Xe-135m .02 . 527 .80 .008 Xe-135 .20 .250 .91 .046

.61 .03 .004 Xe-138 2. 02 .58

.99 .081 HEY

0