ML20207J369

Rev 2 to Evaluation of Dose Rate & Shielding Requirements for Post-Accident Sample Sys

ML20207J369
Person / Time
Site:	Palisades
Issue date:	09/30/1982
From:	Gaston D SENTRY EQUIPMENT CORP.
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References
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Download: ML20207J369 (32)

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EVALUATION OF Tile DOSE RATE AND SHIELDING REQUIREMENTS FOR Tile POST ACCIDENT SAMPLE SYSTEM 7

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Prepared by Sentry Equipment Corp.

David M. Gaston June,1932 Rev. 1 - July 1982 Sept.1982 Rev. 2 O

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i.

5 TABLP. OF CONTENTS

!)cseriotion Page Section 1,0 INTRODUCTION 1

2,0 SHIELDING EVALC ATION METHOD 2

Introduction 2

lR2 D!scussion of Methods 2

Shield Penetration 5

3.0 ElCELI)!NG EVALUATION RESULTS 9

Lesign Criteria 9

l R2 GSP Shicidin; Evaluation 9

CASP Shic: ding Evaluatloa 11 l Rl, R2 so N

Tables S

2-1 LINEAR ATTENTUATION COEFFICIENTS 6

2-2 COEFFICIENTS USED IN CAPO'S FORM 7

OF THE BUILDUP FACTOR 3-1 SOURCE TERMS 14 3-2 SOURCE VOLUMES 16 7

3-3 DOSE RATES 17 3-4 GSP !NTEGRATED DOSES 18 l R2 3-5 CASP !NTEGRATED DOSES 19 l R1 Figures i

FIGURE 2-1 8

FIGUltE 3-1 20 FIGURE >2 21 FIGURE 3-3 22 FIGURE 3-4 23 FIGURE 3-5 24 R1 FIGURE 3-6 25 i

REFERENCES 2 f.

(s i

o' 1.0 INTT.ODUCTION k

/7 Sentry Equipment Corp. (SEC) has~ evaluated the shiciding design for the Post e

w Accident Sample System (PASS) equipment being provided by SEC for use in -

nuclear powcr stations. The PASS equipment consists of the following:

Grab Sample Panel (GSP)

Containment Air Sample Panel (CASP)

This equipment is designed to enable an operator to obtain samples of primary reactor coolant or containment atmosphere, which may be highly radioactive in the event of a reactor accident involving substantial fuel failure.

The results of the shielding analyses'ce: fies ;;

the maximum integrated dese ~

3 to an o;,;;: ;.: ;,2:ferming t.ny sam;: Sng opt Ac. ;;!ng the GSP or CASP :s ap&roximctoly 400 mrem.T N

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Page 1 of 26 i

1-

r -~_- ~~ :- : -, _--, ~,_ ~3 g;_3 ;; ---- _ _ _,__~

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2.0 SHIELDING EVALUATION METIIODS j

%)

C-2.1 rotroducuen The dose rates due to direct radiation omitted from the process piping behind the GSP and CASP were determined by the SEC radiation shielding design system computer codes. The methods used are discussed in section 2.2 and are based on the equations given in volume 1, section 6.2 of the Engineering Comoendium on Radiation Shielding (Springer-Verlag New York Inc., 1968).

j The dose rate contributions to the front of the GSP and CASP due to backscatter from the walls and Door behind the panels is not considered.

There are no "thin" sections or ducts in the shielding that would make 3

scattered radiation of more concern than direct radiation.

The dose rate contributions due to various shield psnetrations are discussed N

in section 2.3 0

9 2.2 Discussion of Methods The dose rates were calculated using the equations for shielded line sources.

.o Model!n; was simplified by not considering shielding contributions of the

~

piping walls or self absorption in the process fluid.

Obviously, this will result in a more conservative dose rate than if they had been considered.

M The equations used for the geometries shown in Figure 2-1 are BSy Ax Ps D.R. (mrad /hr) =

At F(O,X)+F(0 sX) t i

2 4m' z C

~

t l

BS Ax y

At P2 &P: D.R. (mrad /hr) =

F(0,X)-F(O,X) 3 2

i 1

4vzC

~

l where l

B=

scattered buildup factor as discussed in section 2.2.1.

lD e

1(/'\\

i Page 2 of 2G s

l 1

3 sy = volumetric source strength (photons /sec/cm ) as discussed in section

~

3.2.1 y

Ax = cr ss-sectional area of source material J

F(0,x) =

exp {->: sec 0] dO' R2 01 X=

pjtj L

i=1 photons /cm2/sec C=

flux to dose conversion mrad /hr y

7 tj =

shield. laminate thickness (cm) o' pj =

linear attenuation coefficient of shield laminate (cm-1)

(Table 2-1)

N

• 9.1. Scattered Dose Buildup Factors The scattered buildup factor for multiple shields was determined by a

Broder's method discussed in chapter 3 of Weaoons Radiation Shielding Handbook (DNA-1893-3, Rev.1; March 1972). This method is based on a buildup factor being calculated at each shield interface; once for each laminate material as if the entire.h'a1.d consists of that material.

These buildup factors are then combined by Broder's recurrence equation:

N N-1 N

N-1 B (Epi i) = B (Epjt ) + BN (b #i j) - BN (b#i j) t i

t T

!=1 i=1

!=1

!=1 where B ( ) indicates a function not a product.

Thus, the formula for total buildup is:

N N

n N

n-1 B (C#itj) =[. Bn (.b #nti) -[2Bn (b#nt[)

i= 1 n=

i=1 n=

i=1 i

Page 3 of 26 l

Each individual buildup factor was calculated using Capo's point i

source polynomial approximation:

C 3

B=[

j (ut)I (after Encincering Compendium on i=0 Radiation Shiciding, Vol.1) where [g are the coefficients listed in Table 2-2 2.2.2 Gamma Scurce Definition The source terms were divided into nine groups as follows:

Representative Energy Range Energy (MeV)

(MeV) 0.4 0.1 - 0.5 0.8 L.5 - 0.9 1.3 0.9 - 1.35

!n 1.7 1.35 - 1.8 2.2 1.8 - 2.2 o

2.5 2.2 - 2.6 N

2.8 2.6 - 3.0 4.0 3.0 - 5.0 d

6.1 6.1 2.2.3 Flux to Dose Conversion The gamma flux calculated at the dose point is quantified in units l

~

2 of photons /sec/cm. These are converted to dose rates in mrad /hr

~

for each energy group as follows:

7 Energy Group Conversion Factor (MeV)

(photons-hr/sec/cm2/ mrad) 0.4 1357 0.8 696.9 1.3 467.2 1.7 380.6 2.2 320.4 2.5 297.7 2.8 275.8 4.0 210.4 6.1 157.0 V(s (af ter Nucione Endncering Handbook, Section 7; McGraw-Hill)

Page 4 of 26

,n.-

2.3 Shield Penetration

/3 All penetrations passing through the shield are offset to minimize the dose due to radiation streaming and have negligible contribution to the dose mV rato. However, the shielding evaluation for Sentry Equipment Corp. High Radiation Sample System considered the valve stem penetrations (which are identical to those used on the PASS) to have no offset.

Therefore, the evaluation of the valve stem penetrations will be included, realizing this will provide a conservative analysis.

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Table 2-1: Linear Attenuation CoefficienL4 Energy Lead Iron (MeV)

(:m-1)

(em'l) 0.4 i'.4948 0.7165 0.8 L.9707 0.5174 N

1.3 0.6430 0.4139 1.7 0.5477 0.3571 0

2.2 0.5012 0.3182 N

2.5 0.4888 0.3026 q

2.8 0.4785 0.2894 i

~#

4.0 0.4695 0.2575

~

'b 6.1 0.4933 0.2373

~3 (citer Nt clear Encineering Handhn*, Section 7; McGraw-Hill)

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Table 2-2: Coefficients Used in Capo's Form of the Buildup Factor j

0 LEAD Encrw DieV)

'30 B1 B2 B3 0.4 0.99993E+00 0.24413E+00

-0.17836E-01 0.59319 E-03 0.8 0.10118 E+ 00 0.30992E+00

-0.14248 E-01 0.48683E-03 1.3 0.10179E+01 0.36963E+00

-0.78522E-02 0.26797E-03 1.7 0.10152E+01 0.38419E+00

-0.28531E-02 0.11143 E-03 2.2 0.10076 E+ 01 0.37505E+00 0.26969E-02

-0.30058E-05 2.5 0.10026E-01 0.36026E+00 0.54705E-02

-0.11432 E-04 2.8 0.99805E+00 0.34141E+00 0.77384E-02 0.31761E-04 4.0 0.99061E+ 00 0.25670 E+00 0.11135E-01 0.71922E-03 M

6.1 0.10044E+ 01 0.19172 E+00

-0.14075 E-02 0.29838E-02 7

s r3 1RON Energy ulcV)

B0 B1 B2 B3 O

0.4 0.10025E+01 0.86091E+00 0.97034E-01

-0.15664E-03 0.S 0.96274 E+00 0.50173E+00 0.10918E-00

-0.15172 E-02 3

1.3 0.10160E+01 0.73677E+00 0.57451E-01

-0.48387E-03 1.7 0.10141E+01 0.C3360E+00 0.42602E-01

-0.45168 E-03 2.2 0.10074E+01 0.52410E+00 0.33554E-01

-0.45419E-03 2.5 0.10043E+ 01 0.53796E+00 0.30177E-01

-0.43507 E-03 2.8 0.10019 E+01 0.55378E'00 0.27590E-01

-0.40323E-03 ry 4.0 0.99780E+00 0.44092E+03 0.21099 E-01

-0.22404 E-03 6.1 0.99809E+00 0.31496E+00 0.15465E-01 0.69837 E-04 Iy en, a 26

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3.0 Sil!ELDING EVALUATION RESULTS t

3

^d 3.1 Desitrn Criteria The shiciding provided on the Grab Sample Panel (GSP) and the Containment Air Sample Panel (CASP) is designed to limit the integrated dose to an operator st<tnding one (1) meter in front of the panel to 3 rem whole oody 9

and 18.75 rem extremities from a single exercise.

l R2 3.2 GSP Shielding Evaluation 3.2.1 Source Terms l

The radiation source terms used in the GSP shielding evaluation are based on:

• an equilibrium cor: operating at a power Icrel of 2561 MW t

• Ielease of 1001o of tne noble gas, 50?o of the halogen, and 1% of the solid radfor. :lides to the reactor coolant o

[

• recetcr coe..c.: w.;..a. of 5500 cuvic f4at These source terms are listed in Taole 3-1.

~

3.2.2 The shielding evaluation is based on the " crst es ser accident defined by the source terms above.

The types of samples wnich can be obtained during accident conditions are:

3

• 30 ml in-liac pressc! ed reactor coc!=t sample from which t gases are stripoed

• a m1 sample of undiluted,' gas-stripped reactor coolant Mr

• A,000,:1, diluted, gas-stripped reactor coolant sample

• ! '5,000:1 diluted, stripped ' gds'es'.'

1 A purge of alllines connecting the GSP to the reactor coolant system precedes the acquisition of each sample. After the purge is complete, the 30 ml in-line pressurized reactor coolant sample is isolated. At this time, any lines in the panel containing reactor coolant would be flushed with demincralized water to reduce the total active volume.

Then the in-line sample is strippcd, separating the gases from the liquid. Now, any or all of the romaining samples may be l

taken. Upon completion of the sample acquisition, the entire panci

..n

'h Page 9 of 26

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is flushed with domineralized water to remove the remaining active liquids and gases.

g.-

The process piping and component data used for this evaluation is:

all lines in the panel are either 1/4 inch diameter by 0.166 inch bore tuoe or 1/8 inch diameter oy 0.067 inch bore tuoe.

the volume of all 1/4 inch tuoe rising stem valves is 1 ml the volume of the thermocouple is the same as an equal length of 1/8 inch tube the volume of the VREL is the same as an equal length of 1/4 inch tube the flow element is 3/8 inch diameter by 0.315 inch bore tube ell beii vJ/es have the same bore as eMr connecting tubing the volume of all 1/F inch tube rising stem valves is 0.1 ml a

'n the volume of SF1 is 30 ml the volume of EV1 and EV2 is 300 ml (150 ml cach)

The total source voluines ar = listed in Table 3-2.

S' T Specific details on GSP operation are given in the Operation and Maintenance Manual.

3 3.2.3 GSP Shielding

.3 The GSP shiciding design consists of a main panel shield and a shield surrounding the opening for the undiluted sample cask. The main panel snield is comprised of 7 inches of lead shot held between two 1/2 inch steel plates and runs from the floor to the top of the panel.

The shield surrounding the opening for thetundiluted sarb'plb cisk'is}

comprised ~of 4'ing;!es of ' solid Tead b~et' vie'en 'two 1/2 inchitect plates.

This shield is connected to the opening in the main panel shield and covers the interior side wall, rear wall, and ceiling of the opening.

Refer to Figure 3-1 for an illustration of the shiciding.

Tho' lead shof density used in the.. analysis was ?.14'g/cni3 This value corr 6sponds to 63W.~of the theoretical lead densit((of 11.3[

g/cm3 and is based on mechanical and raciometric measurcinents 3

made oy Sentry liquipment Corp.

O

^h.

Page to of 26

~

The maximum whole body and extremity dose rates are considered

. (;

to be one and the same since use of the reach rod requires that the ij ';

hands be close to the body. These dose rates are listed in Taole 3-3.

The line source geometries are shown in Figures 3-2 through 3-4.

The dose point considered was directly in front of SF1 at a distance of one (1) meter from the front of the panel.

No other points were considered as SF1 will always contain the greatest concentrated active volume during sampling.

3.2.4 Valve Stem Penetrations The valve stem penetrations used on the PASS are identical to those used on the HRSS. Therefore, the results from the HRSS stuoy were used in this study.

It should be undcrstood that the radiatien N'

streaming from ene penetration is so.t.;hly collim=d that it.zili

'U not be additive to the exposure from any other penetration.

o Therefore, the dose rate of 10 mrem /hr was used for valve stem 3

penetrations cased on "Evaluation of the Dose Rate and Shielding m

Requirements for the HRSS Equipment", NUS 3872; October 1981.

3.2.5 GSP Integrated Dose Results The integrated dose results are compiled in Table 3-4.

L.d v

..s O

are7dII'b610w the requir-ents of 3 rem whols :mcy t U.D

-m i E2 extr'6mities sp;cified by the integrated dcse c:Mrja.

M 3.3 CASP Shielding Evaluation 3.3.1 Source Terms The raalation source terms used in the CASP shielding evaluation are based om an equilibrium core operating at a power level of 2561 MWt R1 release of 100% of the noble gas and 25% halogen radionuclides to tne containment atmosphere

• containment free volume of 158,562 cubic feet i

These sourec terms are listed in Table 3-1.

f Pago 11 of 26 1

. ~...

'l gg 3.3.2 The shielding evaluation is based on the "worst case" accident defined by the source terms above.

The type of sample obtained during.

C accident conditions is:

~

624:1-sampTe~of the~ containment atmosphere (the' volume of the tsample.. before..dllution is 24 pil A purge of the sample lines in the CASP and its interconnecting lines to the containment precedes the acquisition of the sample.

After the purge is complete, the sarnple is trapped in the diluter valve and swept into the sample vial. Upon completion of tae sample ; R1 acquisition, the entire panel is flushed with nitrogen to remove the remaining active gas.

I The process piping and compe.cnt data used for this evcluation is:

all Ifnes in the panel are eithe: 1/4 inch diameter by 0.166 inch bore tube or 1/8 inch diameter by 0.067 inch bore tube.

l M

.o the eductor exhaust line has a 0.106 inch bore containing N

radioactive gas the remainder of the bore is nonradioactive nitrogen.

the flow element is 1/4 inch diameter by 0.166 inch bore tube.

all ball and plug valves have the same bore as their interconnecting tubing.

The total source volume is !!s'.ed in Table 3-2.

Specific details en CASP operation are given in the Operation and Maintenance Manual.

y 3.3.3 CASP Shielding The CASP shiciding design consists of a front panel shield and two side panel shields.

The front panel shield is comprised of seven inches of lead shot held between two 1/2 inch steel plates and runs from the floor to the top of the panel. The side shields are five Inches of lead shot held between 2 1/2 inch steel plates and run from the floor to the top of the panel.

Refer to Figure 3-5 for an illustration of the shiciding.

The lead shot used in the analysis was 7.14 g/cm3 This value i

O Page 12 of 26 r

corresponds to 63% of the theoretical lead density of 11/34 g/cm3

( m' The maximum whole oody and extremity dose rates are considered

(

)

to be one and the same since use of the reach rod requires that the ys hands be close to the body. These dose rates are listed in Table s.

3-3.

The line source geometry is shown in figure 3-6.

The dose.

point considered is one meter from the panel face, 0.8128 meter R1 coove the floor, and 0.2032 meter from tne panel's right side.

3.3.4 Valve Stem Penetrations See Section 3.2.4.

1 3.3.5 CASP Integrated Dose Results The integrated dose results are comp: led in Table 3-5.

These results j

'T ure well below the rc:quircments of e rem whole dedy := 15.75 rem l R2 m

extremitics specified oy *.he integrated dose criteria, O

N L

9 M

N j

Page 13 of 2ti

I )

Table 3-1 Source Terms O

Liquid Sources for a Non-Linebreak Accident 1 Hour Representative Production Rate @3)

Energy (MeV)

(photons /sec/cm 0.4 0.3379E+11 O.8 0.42.25E+11 1.3 0.1403E+11 l

1.7 0.6152E+10 2.2 0.3334E+10 2.5 0.2544E+10 2.8 0.1511E+10 4.0 0.3101E+10 6.1 0.9508E+09

'A Degased Liquid Sources (30cm3 total volume) 1 Hour Representative Production R.ite @3)

(photen.=/;ec/cm Energy (MeV)

.o 0.4 0.3171E+11 0.8 0.4108E+11 1.3 0.1363E+11 1.7 0.5915E+10 h

2.2 0.3117E+10 2.5 0.2200E+10 2.8 0.1511E+10 4.0 0.3008E+10

'O 6.1 0.5COSE+09

~

Gas Sources (270 cm3 total volume)

'O Representative Production Rate C g) Hour Energy (MEV)

(photons /sec/cm 0.4 0.2084 E+10 0.8 0.1174 E+10 1.3 0.3970E+09 1.7 0.2371E+09 2.2 0.2175E4 09 2.5 0.2538 E+09 2.8 0.2488E+06 4.0 0.3374E+06 6.1 0.2492 E+ 01 l

.r~.

V Page 14 of 26

• J G

Table 3-1: Source Terms (Con't)

>~,)

a Containment Atmosphere Sources for a Linebreak Accident R1 Representative Production Rate @ 3) 1 Hour (photons /sec/cm Enerev (MeV) 0.4 0.27 09 h+ 10 0.8 0.1253 E+10 1.3 0.4237E+09 1.7 0.202SE+09 2.2 0.1450E+ 09 2.8 0.2528 E+08 4.0 0.2606E+07 6.1 0.1357E+02 o

in o

N N

(Source terms were prepared by Sargent & Lundy Engineers) ci l

to

)

Page 15 of 2G

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Table 3-2: Source Volumes GSP j

Operation Volume (em3)

Purge 86.4 Capture in-line flask 116.4 N

Diluted or undiluted liquid 36.0 sample

.9 Diluted gas 303.4 (gas)

,o 30.0 (liquid)

N 3

e

}

CASP

")

Operation Volume (cm3)

R1 Purge & Sampling 12.4 79 1

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Table 3-3: Dose Rates i

GSP Operation Dose Rate (mrem /hr)

Purge 1907

,o

.o

, Capture in-line flask 2532 o

Diluted or undiluted liquid 554.7 sample Diluted gas 33'1.6 CASP O

~

Operation Dose Rate (mrem /hr)

R1

?')

Purge & Sampling 15.6

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Page 17 of 26 R

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l Table 3-4: CSP Intenated Doses Occration Time in field (min)

Dose (mrem) 158.9 Purge 5

Capture in-line flask 3

126.6 Strip gas 6

I 62.5 Subtotal for initial operations 348

'O To obtain undiluted or 5

46.2 l R2

' diluted liquid sample

,g of Total 394.2 R2 O

9 To obtain diluted gas 5

27.6 7

Total 375.6

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' Tchle ' 3-5: CASP Integrated Dos R1 t

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Operation Time in field (min)

Dose (mrem)

Purge 3

0.8 Sampling 1

0.3 0

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TOTAL 1.1 N

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Arcieri, W.C., "Evaluation of the Dese Rate and Shielding Requirements l

for the HRSS Equipment", NUS 3872, (October 1981).

1 Etherington, Harold, Nuclear Engineerine Handbook, McGraw-Hill.

Jaegar, R.G., Engineering Comoendium on Radiation Shielding, Volume '1, Springer-Verlag New York, Inc., (1968).

i Sicvens, Paul N. and Trubey, Dr.. :. '.., "Weapons Radiation Shielding Hand-N Book", DNA-1893-3, Rev.1, (. Iarch 1972).

0 7

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C M TIFICATE OF ATJM FFICITf This is to certify that the microphotographic O

ima6es appearing on this roll of mocrofilm are accurate reproductions of the records of Consm ers power ca,

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company policy for systat.s utilization and/

or for the maintenance and preservation of O

such records through the storage of such microfilms in protected locations.

It is furthee certified that the photographic O

Processes used fer microfibing of the above records vare accc=plished in a nanner and on j

microfi.la which nests the recomended require-ments of the Records Mauge=ent Department for permanent microphotographic reproductions.

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1 CERTIFICATE OF AtTUDCTICITT This is to certify that the microphotographic i= ages appearing on this roll of moerofilm are accurate reproductions of the records of t Consumers Power Co.,

and were microfilmed in the regular course N

of business pursuant to established routine company policy for systems utilization and/

or for the maintenance and preservation of

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such records through the storage of such microfilms in protected locations.

It 14 ftzrther certified that the photographic processes used for microfilming of the above O

records were accomplished in a manner and on microfilm which meets the reco1:xcended require-ments of the Records Mana;ement Department for permanent microphotographic reproductions.

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Datd derofilmed Ca'mers Operster Mr M N b

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