ML20127B673

Rev 2 to E-255-961, Calibr Rept RD-72 Wide-Range Gas Monitor High- & Mid-Range Detectors

ML20127B673
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Site:	San Onofre
Issue date:	01/31/1983
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ML20127A193	List: ML20127B673 ML20127B702 ML20127B728 ML20127B955 ML20127B979 ML20127C116 ML20127C195 ML20127C531 ML20127C659
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FOIA-84-885 E-255-961, NUDOCS 8506220022
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Text

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E-255-961 (Rev. 2)

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t t..s we CALIBRATION REPORT RD-72 WIDE-RANGE GAS MONITOR HIGH AND MID-RANGE DETECTORS IMPORTANT If the price or schedule is af fected by this document, Bechtel must be notified prior to fabrication or such cf aims are waived.

l Permission to proceed does not constitute acceptance or approval of documents involving design details, calculation, analysis or test report i

and is only an acceptance of the method used Dy the suppher. Supplier retains full responsibility for design.

Issuance of this document does not relieve the supplier from full responsibility for contract or purchase order requireme-including, i

but not limited to, adequacy and suitability of materi ir and/or equipment represented thereon for the intended fgion.

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h DOCutilEllT STATUS DATE 1

Manufacturer may proceed A

Enceptions as noted. Make changes and resubmit. Manufacturer may proceed.

4 0, correct and resubmit.

7 *..,information only. 4.Jistribution required.

C Copyright GA Technologies Inc.1983 All Rights Reserved I

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Issue Date Pages Affected Original 9/81 All Rev. 1 11/81 Cover, 7 l

Rev. 2 1/83 All l

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l Wherever reference is made in this document to General Atomic Company or one of its divisions, it shall be understood to mean GA Technologies Inc.

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CONTENTS l

1.

INTRODUCTION...........................

1 2.

DETECTOR DESCRIPTION.......................

2 3

3 SETUP AND PROCEDURE 4.

DETECTOR CORRECTION FACTOPS 7

10 5.

ENERGY RESPONSE CURVE......................

l 6.

LINEARITY TEST..........................

16 16 6.1.

Objective 6.2.

Method.

16 16 6.3.

Results...........................

7.

ACCURACY.............................

19 20 8.

BACKGROUND............................

A-i APPENDIX...............................

l FIGURES 1.

Test setup for calibrating the RD-72 detector 4

2.

Half life correction.......................

9 3

Mid-range detector energy response curve.............

12 13 4.

High-range detector energy response curve 17 5.

Setup for linearity test.

TABLES i

1.

Detector response to gaseous and solid test sources 5

14 2.

Solid sources used for energy response curves 3

Example for calculating detector response for an expected hypothetical source term for high range detector.............................

15 18 4

Linearity test data

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

T 1.

INTRODUCTION During the period August through November 1982, calibration tests were performed on the RD-72 detector.

Xenon 133 and krypton 85 radioactive gases were purchased from Isotope Products Laboratories.

After the prototype detector sample chambers were filled to atmospheric pressure, the Xe-133 lecture bottle was sent to the National Bureau of Standards (NBS) for verification of calibration (see Appendix for certificates of calibration).

A number of solid uncalibrated beta and gamma sources were used to obtain counting efficiencies from individual detectors. A number of detec-tors obtained from production stock were evaluated using Ba-133 and Cs-137 solid gamma sources, Cl-36 and Kr-85 solid beta sources, and the calibrated Xe-133 and Kr-85 gases.

eCalibrated beta, beta-gamma, and gamma sources were procured from

(

Isotopes Products Inc. for performing energy-response tests with a number of j

detectors.

(See Appendix for certificates of calibration.) A linearity s

l test was performed on one detector to show response for the full 6-decade l

range of the detector.

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DETECTOR DESCRIPTION The RD-72 is a dual-range beta-gamma sensitive gas detector assembly, consisting of two sample chambers.(approximately 0.02 cc and 30 cc active volume), coupled directly to solid-state CdTe(C1) detectors. These detec-i tors are connected directly to individual charge-sensitive preamplifiers and assembled inside a 6-in.-thick lead background shield.

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1 3

SETUP AND PROCEDURE i

j A number of detectors were obtained for testing from production stock.

I Each detector was evaluated for response to calibrated noble gases Xe-133 and Kr-85 and a number of solid beta and gamma sources. Each detector was aligned for gross counting with a 60 kev threshold. A Canberra model 30 multichannel analyzer was used to obtain the data. (See Fig. 1 for test setup.)

l 1

Solid Ba-133 and Cs-137 gamma sources were used for the detector j

alignment. The initial alignment was performed using 80 kev gamma and Cs X-ray photopeaks from the Ba-133 source. The alignment was verified by observing the Ba-133 356 kev ganas and the Cs-137 662 kev gamma photopeaks.

i

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Counting efficiencies for each detector were obtained from the proto-i type RD-72 sample chambers. The chambers were evacuated to less than one millimeter of mercury absolute pressure, then backfilled to atmospheric pressure with a calibrated Xe-133 or Kr-85 gas sample. The chambers and detectors were installed in the prototype RD-72 lead shield when obtaining the countrates, A fixture was used for locating the solid sources in a j

repeatable counting geometry.

i The CdTe(C1) crystals are approximately 2 mm x 2 mm x 5 mm in size.

Because of manufacturing tolerances when cutting the crystals to size and when assembling the unit, each detector has a specific counting efficiency I

for beta and gamma radiations. A relationship was obtained between the

]

gaseous sources and the solid sources. A solid Kr-85 source was selected to relate beta response to radioactive gases. A solid Ba-133 source was selected to relate gamma response to radioactive gases. Ba-133 has the same f

Cs X-rays as Xe-133 and an 80 kev ganssa as compared to Xe-133 with an 81 kev i

I gamma. The ratios of the solid Kr-85 beta source to the gaseous Kr-85 varied 1

3 1,__-_.

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i DETECTOR I

i LINEAR a

AIAPLIFIER POWER SUPPLY CA ER PREARIP H.P. NO. 5002A 0R FIXTURE WITH i

SOLID SOURCE g

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t IAULTICHANNEL ANALYZER CANGERRA SERIES 30 l

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1 Fig. 1.

Test setup for calibrating the RD-72 detector l!

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9 4

n by less than 165 from the mean value for all the detectors tested. The ratios of the solid Ba-133 gassna source to the gaseous Xe-133 varied by 1125 from the mean value for all the detectors tested. The test restilts are given in Table 1.

TABLE 1 l

DETECTOR RESPONSE TO GASEOUS.AND SOLID TEST SOURCES l

Co mm eorW.

l Response to re-133 cas

" "7

'## /" 'N **

l b fl* l en k}. SW l

Mid-range chamber 1295 spread from a mean of 1.42 x 10" cpm (microcuries/cm )-1 3

High-range chamber 3

2305 spread from a mean of 49.4 cpm (microcuries/cm 3-1 Ratio of responses, mid versus high chambers 8

1 51 spread from a mean of 294

"####!! ##**' ##"[/ orr f*V. h y

@8 Response to Kr-85 Gas

1. /'"

M J e d / o p /o Mid-range chamber 1405 spread from a mean of 1.51 x 10" cpm (microcuries/cm )-1 3

High-range chamber 3

1365 spread from a mean of 58.9 cpm (microcuries/cm 3-1 Ratio of responses, mid versus high chamters l

1 7% spread from a mean of 252 5

I Responses to Solid Sources

(***!*h f/esye, ys'n yn /O'4*$

Kr-85 (source S/N KR85-109) on 9 #Y 1415 spread from a mean of 35618 cpm Ba-133 (source S/N BA81-001) on 9-1-82 1265 spread from a mean of 14550 opa 5

1 j

TABLE 1 (continued)

Responses of Solid Sources Versus Gaseous Sources

[e m eres [

- [/k Md.

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Mid-Range Chamber ssY en or

,Ar fx e.

I Xe-133 gas versus Be-133 solid source (BA81-0 ggj 112% spread from the mean

,9 A,

,p Kr-85 gas versus Kr-85 solid source (KR85-109) cf,, p,,y 1 8% spread from the mean 2

High Range Chamber Xe-133 gas versus Ba-133 solid source (BA81-001) 112% spread from the mean Kr-85 gas versus Kr-85 solid source (KR85-109) 1 9% spread from the mean 5

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4 DETECTOR CORRECTION FACTORL l

Since there is s' definite relationship betwee the solid Ba-133 source and Xe-133 gas and between the solid Kr-85 source and Kr-85 gas, these solid sourcescanbeusedtoobtai(correctionfactoryfortheindividualdetec-tors. After a detector is aligned for gross counting with a 60 kev thresh-old, a beta and gamma correction factor can be calculated as follows:

Beta correction factor (Cg) can net Kr-85 source C

Fb mean cpm Kr-85 source x C.71/2 Gamma correction factor (CFq) l pm net Ba-133 source C

s Fq mean epm Ba-133 source x CT 1/2 where net cpm for the Kr-85 and Ba-133 source response is obtained from the transfer calibration procedure 0360-9010 for each detector.

l Half life correction (C

)

\\

L/T,,y C.7 s 0.5 l

1/2 1

where t s time in years since 9-1-82 10.4 years for Ba-133 T

s 1/2 10.73 years for Kr-85 s

5

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N*h : %u umafu K,4 AN **/ for. red bores The correction factors are now (com KR85-109)

C 3 56 x to u o.5(t/10.7) for beta counting F

4 (cpm BA81-001)

C s

for gamma counting p

1.45 x to x 0.5(t/10.9) 4 Half life corrected values for the Ba and Kr sources can be obtained from the graph in Fig. 2.

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5.

ENERGY RESPONSE CURVE The energy response curve can be useful when calculating a counting efficiency for an expected source term. The source ters of interest has to contain the following information when calculating an expected detector response.

1.

Isotopes of interest and their intensities (the sum of the indi,

vidual intensities is equal to one) 2.

Each beta and gamma with its energy in MeV and ntsober produced per disintegration.

Beta and gamma responses can now be obtained from the Energy Response 3

urv (see Figs. 3 and 4).

This response in ope /(microcuries/cm ) (assuming one gamma or beta per disintegration) must be corrected for the intensities of the isotope and the number of betas or gammas produced per disintegra-tion. The sums of all the corrected beta responses and all the corrected gamma responses must be multiplied by the individual detector's beta or gamma correction factor. These correction factors are obtained from Section 4 of this report. The sus of the detector's gamma and beta responses is the 3

detector's expected response in ope /(microcuries/cm ) for the source term of interest.

The reciprocal of the detector response is the detector conversion 3

factor (microcuries/cm )/ cpm. This conversion factor, when factored into 3

the RM-80 data base, can provide a microcurie /cm equivalent for a known source term.

The shape of the energy response curves was obtained from eta and gamma sources in a fixture simulating the actual detector sample chamber Gar 5 east'l WasseM rwu 10 to rntled Sa-ra h's of e seeas.*Me y

hr.f*/*'A.' WAn h 4 es asod,!

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geometry. The sources used are listed in Table 2.

After the shapes of the curves were established, they were superimposed over the actual responses for Kr-85 and Xe-133 to produce the curves shown in Figs. 3 and 4.

Sample calculations for a source term response are shown in Table 3 4

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TABLE 2 SOLID SOURCES USED FOR ENERGY RESPONSE CURVES Major Energy Intensities Isotope Radiations (MeV)

(5)

Cd-109 gamma 0.088 5

Co-139 gasuna 0.165 80 Cr-51 gaussa 0 320 9

0.662 85 Cs-137 gamma beta 0.514 93 beta 1.176 7

Co-60 gamma 1.173 100 1.25 av 1 332 100 beta 0 314 99+

Tc-99 beta 0.292 100 Cl-36 beta 0.714 100 Sr-90/Y-90 beta 0.546 100 beta 2.27 100 fkASt pl$

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{

AN EXPECTED HTPOTHETICAL SOURCE TERM FOR HICH RANGE DETECTOR HICH RANGE DETECTOR f

' (DETECTOR CORRECTION FACTORS) = 8 s 1.12 y

7 a 0.98 I

Source Ters Radiations Produced ese e

wC1/cc Espected Intensity Energy No. per fron D s E or Yield Concentration MeV B or y Die Graph Actual A F C y

Isotope or Activity (C1)

A B

C D

E F

G emmesll Ie-133 2.14 to 0.39 N/A 49 4 21.6 The*r ve des.

• //f*'8 /*

• Actual response obtained free Calib. report

1. /e /d e [

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Ie-135 2.04 10 0 37 0.25 y

0.91 54 49.1 17.8 8

0.61 y

0.03 20 0.6 0.2 0 92 s

1.00 103 103 37 3 Er-88 1.22 x 10 0.22 0.166 y

0.07 110 7.7 1.9 8

0.191 y

0 35 90 31.5 7.8 0.36 y

0.05 29 1.5 0.4 0.85 y

0.23 18.5 4.2 1.0 1.55 y

0.14 17.5 4.0 1.0 2.19 y

0.18 15.5 2.8 0.7 2.4 y

0 35 15 5.2 13 2.8 8

1.00 l 480 480 103 0

N/A Ie-133M 52 10 l

<0.01 Less than 15 of Source Ters Total Espected Yield for Source Ters ops (uC1/ce)~I 194 I*' Notes:

Obtained free transfer es11bration proc (dure (0366-9010)

C F

A Calculated froe source ters B,C and D obtained from table of isotopes E

Obtained froe graphs Fig. 3 and 4 in RD-72 Calibration Report F

D times E cc 'from Table 1 of RD-72 Calibration Report G

A times F times CF 15

6.

LINEARITY TEST 6.1.

OBJECTIVE The objective is to show response of the detection system for count rate versus activity strength.

6.2.

METHOD A monoenergetic radioactive nuclide,10 mci cesium 137, was placed at a fixed distance from the detector. Lead attenuators of similar thickness, 1/4 in. (approximately one-half-value layer thickness), were inserted one at a time between the detector and the source. Countrate readings taken before and after adding each attenuator were compared and the percentages of countrate changes were calculated. The tests were repeated to cover the i

operating range of the detection system for the decade above background (10 l

6 7

to 10 cpm) thecush the last decade or response (10 g,3n

,,,),

3,, pig, 3

5 for test setup and Table 4 for test data.

6.3 RESULTS The actual change in countrate within the operating range of the l

detector from the decade above background (10 to 10 cpe) through the last 0

7 decade (10 to 10 cpm) was found to be between 485 and 545 for one 1/4-in.

thick lead attenuator. The change varied 135 from a mean of 515. There-fore, it can be concluded that the detection system is linear within 135 when actual countrate is compared with activity strength for the operating I

range of one decade above background to the uppermost decade.

16

l LEAD ATTENUATORS CdTe (CI) DETECTOR ASSEMBLY 10 mci Cs-137 POINT SOURCE

,y i

l OlSTANCE KEPT CONSTANT FOR l

=

=

EACH SETUP EL 3739 Fig. 5.

Setup for linearity test O

17 e'

TABLE 4.

LINEARITY TEST DATA

• No. of Countrate atten-attenuation l

untors ops (5)

Setup

,1 1512613 52 1

2 784432 1

560576 l

51 Setup 2

285194 2

50 3

143968 50 4

71354 Mean atten-untion 1

326948 in 49 countrate 2

159146

=

50 515 Setup 3

79874 3

49 4

38824 50 5

19501 50 6

9843 1

6645 50 2

3337 52 3

1750 48 Setup 4

844 4

54 5

458 49 6

223

• The above data are from General Atomic Laboratory Notebook 7416, pp. 81 and 82.

18

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ACCURACY f / l r<fes/rol ak// fa, y

foure e /er,.a 7

(/ d' A.

Radioactive Gases Xe-133 1 95 1

Kr-85.2205

[(1.9)2 + (205)2 1/2 20.15 3

=

1 35 7

B.

Solid Sources for Energy Response Curves =

C.

Counting Error ( All counts were >3000) 1 85 1

x 100 =

3000 D.

Spread, Solid Sources to Gaseous Sources Beta 15.95 Gamma 125

[(5.9)2 + (12)2)1/2 13 45

=

Overall Accuracy 125 35 l

A

+B

+C

+D

=

19

u.

8.

BACKGROUND The RD-72 detector assembly was scanned with a 5 sci co-60 point source producing a gamma flux of approximately 29 mR/hr. This gamma flux produced approximately one count-per-esinute increase over the ambient background.

The anbient background was 3 counts in c 10-min counting period.

The above data is recorded in General Atomic notebook No. 8185 on pages 130, 131. and 135.

l

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e' 20

1 O

4 e

e WO e

9 APPENDIX e

O e

1 1

CERTIFICATE OF RADIOACTIVITY CALIBRATION Isotope: Ce #39 Half-Life: /37.4,tv.02 d Source No.: th6f 1 G

Was assayed as coiltaining: 8f.o37 As of: #1-f 92-METHOD OF CALIBRATION:

( /)

The source was assayed on a 3" x 3" Nal (TI) crystal in conjunction with a single-channel analyzer, using the o/(W MeV peak (a value of c.7994 gamma rays per decay was used in the calculations), against e standard No.

, in the same geometrical arrangement. *cryrbs.f.Nem7 cuac.

(

)

The source was assayed in a windowless internal proportional counter against standard No.

(

)

The source was assayed by alpha spectrometry on a surface barrier detector in conjunction with a single-channel analyzer, against standard No.

In the same geometrical arrangement.

(

)

The source was prepared from a weighed aliquot of a solution whose activity in uCi/gm was determined by the method indicated above.

ERROR CALACULATION:

a) Systemauc errors (SE) b)

Randon errors (RE)

1. Accuracy of the standard: 1 3. O */*

1. Precision of source count, e,:

2.

2. Precision of standard count, e,:

3. Error due to background, e :

3 c) Total Error TE=SE + RE = 2 4 3Y-RE=

+ e ' + e ', + e *3 = 2 /. S'/.

IPL participates in a NBS measurement assurance program to establish and maintain implicit traceability for a number of nuclides, based on the blind assay (and later NBS certification) of Standard Reference Matenals.

NOTES

(/}

The error given is calculated at the M % confidence level.

(

)

This calibration is directly/ indirectly based on NBS Standard Reference Material No.

1 YN.7 A

l'.

J - *' *-

prios A. Henkel Quality Assurance i

kvd/

\\

1 ISOTOPE PRODUCTS LABORATORIES 1800 No Meystone si. Burmann. Cal formall5W I

.. ~ ~

CERTIFICATE OF RADIOACTIVITY CALIBRATION Isotope: 0d-809 Half-Life: 84VtIel Source No.: 10064. i Was assayed as containing: /s4 sC As of: II'l*S'"

METHOD OF CAllBRATION:

( /)

The source was assayed on a 3" x 3" Nat (TI) crystal in conjunction with a single-channel analyzer, using the v.cti MeV peak (a value of g.ohJ gamma rays per decay was used in the calculations),against dP standard No.yr a,

, in the same geometrical arrangement.

(

)

The source was assayed in a windowless internal proportional counter against standard No.

(

)

The source was assayed by alpha spectrometry on a surface barrier detector in conjunction with a sing'e-channel analyzer, against standard No.

in the same geometrical arrangement.

(

)

The source was prepared from a weigined aliquot of a solution whuse activity in uCi/gm was determined by the method indicated above.

ERROR CALACULATION:

a) Systematic errors (Sii) b)

Randon errors (RE)

1. Accuracy of the standard: 14. T*/.

1. Precision of source count, e,:

2.

2. Precision of standard count, e,:

3. Error due to background, e :

3 c) Total Error TE=SE + RE =

• iWe RE=

+ e * + e * + e 's = * (. 2 */

IPL participates in a NBS measurement assurance program to establish and maintain implicit traceability for a r, umber of nuclides, based on the blind assay (and later NBS certification) of Standard Reference Materials.

NOTES

(/)

The error given is calculated at the 99 % confidence level.

( /)

This calibration is(My/ indirectly based on NBS Standard Reference Material No. Ifroo-t

/C~%

I C t$

lM \\

parlos A. Henkel Quality Assurance s

ISOTOPE PRODUCTS LABORATORIES 1800 No Keystone st. Suroant, Cahtome $1504 l

e CERTIFICATE OF RADIOACTIVITY CALIBRATION lsotope: C/~ SI Half-Life:2i,7042 o.co4 d Source No.: (0004-I Was assayed as containing: /2s C

As of: 11-g. (2., g ar p.s a

METHOD OF CALIBRATION:

(/)

The source was assayed on a 3" x 3" Nal (TI) crystal in conjunction with a single-channel analyzer, using the 0.b MeV peak (a value of

o. or;s 3 gamma rays per decay was used in the calculations).against.*fd**y ca-

standard No.

, in the same geometrical arrangement. = &<Wy/r

(

)

The source was assayed in a windowless internal proportional counter against standard No.

(

)

The source was assayed by alpha spectrometry on a surface barrier detector in conjunction with a single-channel analyzer, against standard No.

In the same geometrical arrangement.

(

}

The souice was prepared from a weighed aliquut of a solution wnose activity in uCi/gm was determined by the method indicated above.

ERROR CALACULATION:

b)

Randon errors (RE)

Systematic errors (SE) a)

1. Accuracy of the standard:13.0Y.

1. Precision of source count, e,:

i 2.

2. Precision of standard count e,:

1

3. Error due to background, e,:

c) Total Error TE=SE + RE = i 4.4*/-

RE=

+ e ' + e * + e *3 =

• 7. 4 */.

IPL participates in a NBS measurement assurance program to establish and maintain implicit traceability for a number of nuclides, based on the blind assay (and later NBS certification) of Standard Reference Materials.

NOTES

(/)

The error giv'en is calculated at the 90 % confidence level.

(/)

This calibration is _M/ indirectly based on NBS Standard Reference Material No. 39't 9;

i cah) l L.M garios A. Henkel "3[

Quality Assurance ISOTOPE PRODUCTS LABORATORIES 1800 No Meystone st. Burmann. Califorma 9j504 l

___.__2.._____..

mo nes me e

U.S. DEPARTMENT OF COMMENCE NATH>NAL SUMEAU OF WTANOAftOS WASH 19eSTON. D.C. SMS4 e

REPORT OF TEST for l

General Atomics l

San Diego, California l

Radionuclide Xenon-133 Source description Gas in a Lecture Bottle provided by General Atomics Gas composition Xenon-133 and nitrogen Bq mol-1 s-Imol-1)

Activity 1.29 x 109 Sq (cm3}-1(at STP (0*C,1 atm 5.28 x 104 Reference time 1200 EST August 16, 1982 Random uncertainty 0.13 percent (1)

Systematic uncertainty 1.75 percent (2)

Total uncertainty 1.88 percent (Random plus systematic)

Photon-emitting impurities 131mXe/133 e: 0.021 t 0.001 (3)

X (Activity ratios at reference time)

Half life 5.245 t 0.006 days (4)

Measuring instrument NBS pressurized "43"Y ionization chamber A calibrated by internal gas-proportional counting for the Director.

o...

Washington, D.C.

20234 Dale D. !ioppes. Group Leader August 20, 1982 Radioactivity Group P.O. #806253 Center for Radiation Researth

• Notes on following page

' ' ~ ^

FOOTNOTES (1) Half the 99-percent confidence interval of the mean (2.640 times the standard error computed from 89 ionization-chamber measurements).

(2) Linear sum of estimated uncertainty limits due to:

a) calibration of pressurized "4w"Y ionization chamber A, which is the linear sum of the estimated uncertainty limits due to:

1) half the 99-percent confidence interval of the weighted mean of three series of gas-counting measurements 0.66 percent

2) extrapolation of the gas-counting data 0.22 percent

3) half the 99-percent confidence interval of the mean of three series of ionization-chamber measurements 0.01 percent l

4) radium-226 reference sources ratios 0.36 percent b) gram mole measurement 0.50 percent (3) Limits of detection as a percentage of the gamma-ray-emission rate of the 81-kev gamma rays emitted in the decay of xenon-133 are 0.1 percent between 37 kev and 76 kev 0.01 percent between 86 key and 1900 kev, provided that impurity photons are separated in energy by 5 kev or more from l

photons emitted in the decay of xenon-133.

l (4) NCRP Report No. 58, 1978, p. 387.

e l

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6tpetMAL aTo#mC COMPANY P.O. tox e tos SAM DIEoO. CALFORNIA 9213 (714) 45H000 CERTIFICATION OF RADIOACTIVITY STAhTARD Radionuelide Kr-85 Nominal A:tirity 10jaci/cc Method of Measurement

[X]

1.

Calibration derived from Sigma 2 Computer Gamma Ray Spectrometer calibrated with NBS Standards.

[]

2.

Calibration derived from Ionization Chamber Calibrated to Sigma 2 Computer Gama Ray Spectrometer.

[]

3.

Calibration derived from 27 internal gas proportional counter calibrated to Sigma 2 Computer Gamma Ray Spectrometer.

)

Accuracy Overall T.imit of Error (lc A S ys te-ta tic) i 20%

Ressrks Recalibration of IPL Standard S/il 65010A.

We certify that the activity (ies) was(vere) as follows:

11.1 pCi/cc on 6/25/80 at 1200.

I 1

~ _ b. Gb 2Ghc s

CERTIFICATE OF RADIOACTIVITY Call 3 RATION isotope: Sr. c)o Half-Life: 29.e2 e0.g4 7 Source No.f:dd4.8 C

Was assayed as containing: lo.17:

As of: Il-J -f a-METHOD OF CAllBRATION:

(

)

The source was assayed on a 3" x 3" Nai (TI) crystal in conjunction with a single-channel analyzer, using the MeV peak (a value of gamma rays per decay was used in the calculations), against standard No.

,in the same geometrical arrangement.

(v)

The source was assayed in a windowless internal proportional counter against standard No. rUs-l (&.9u)

(

)

The source was assayed by alpha spectrometry on a surface barrier detector in conjunction with a single-channel analyzer, against standard No.

in the same geometrical arrangement.

(/)

The source was prepared from a weigheci aliquot of a soiunon wnose activity in uCi/gm was determined by the method indicated above.

ERROR CALACULATION:

a) Systemauc errors (SE) b)

Randon errors (RE)

1. Accuracy of the standard: 22.0'4

1. Precision of source count, e,:

2.

OKji,a'j do-l M.

2. Precision of standard count. e,:

c

3. Error due to background, e :

3 c) Total Error TE=SE + RE = S.2 %

RE=

+ e * + e ' + e '3 = * /. N.

3 IPL participates in a NBS measurement assurance program to establish and maintain implicit traceability for a number of nuclides, based on the blind assay (and later NBS certification) of Standard Reference Materials.

NOTES

(./ )

The error given is calculated at the 99

% confidence level.

(j)

This calibration is 6 =..j5ndirectly based on NBS Standard Reference Material No.499 b l

4 N*

E f...

' arlos A. Henkel 99.

uality Assurance l

ISOTOPE PRODUCTS LABORATORIES l

1800 No Meystone st.. Buroana. Cstifom+9 t'.04

y

~

CERTIFICATE OF RADIOACTIVITY Call 3 RATION M-Isotope: 01 %

Half-Life: U.o' t a.01) co#f Source 'No.Aio64 7-4 Was assayed as containing: /0 47-As of: 12 -1 f 2.

METHOD OF CALIBRATION:

(

)

The source was assayed on a 3" x 3" Nal (TI) crystal in conjunction with a single-channel analyzer, using the MeV peak (a value of gamma rays per decay was used in the calculations), against standard No.

, in the same geometrical arrangement.

(/)

The source was assayed in a windowless internal proportional counter against standard No.67037 (C/ 3')

(

)

The source was assayed by alpha spectrometry on a surface barrier detector in conjunction with a single-channel analyzer, against standard No.

in the same geometrical arrangement.

(/)

The source was prepared from s weighed aliquot of a solution v.i.o=6 activity in uCi/gm was determined by the method indicated above.

ERROR CALACULATIONj a) Systematic errors (SE) b)

Randon errors (RE)

1. Accuracy of the standard: 1 2 f*/

1. Precision of source count, e,:

Idds5 4+y ms'r 87'l

2. Precision of standard count. e,:

A 2.

3. Error due to background, e :

3 c) Total Error TE=SE + RE =

• S 01-RE =V + :+

+ '- * ' 'S IPL participates in a NBS measurement assurance program to establish and maintain implicit traceability for a number of nuclides, based on the blind assay (and later NBS certification) of Standard Reference Materials.

NOTES

(/)

The error given is calculated at the 99 % confidence level.

This calibration is d? ::$ / indirectly based on NBS Standard Reference

(/)

/

Material No. 4c/vi 7

j.<

N-l l;jd*.

wuality Assurance parlos A. Henkel

..a.

ISOTOPE PRODUCTS LABORATORIES 1800 No Keystone st.. Burbana California 91504

i i

~

CERTIFICATE OF RADIOACTIVITY CALIBRATION I

r

(

Half-Life:h.s930.05)St/f isotope: Tf.99 B

Source No.:#8th-(,

C Was assayed as containing: /0.

As of: 12 9 S METHOD OF CALIBRATION:

(

)

The source was assayed on a 3" x 3" Nal (TI) crystal in conjunction with a single-channel analyzer, using the MeV peak (a value of standard gamma rays per decay was used in the calculations), against No.

, in the same geometrical arrangement.

(/)

The source was assayed in a windowless internal proportional counter 7

against standard No. 89-9s-f CTc-99)

The source was assayed by alpha spectrometry on a surface barrier

(

)

detector in conjunction with a single-channel analyzer. against standard No.

In the same geometrical arrangement.

The source was prepared from a weighed aliquot of a solution whose (f) activity in uCi/gm was determined by the method indicated above.

ERROR CALACULATION:

a) Systematic errors (SE) b)

Randon errors (RE)

1. Accuracy of the standard: 2 J,2 /,

1. Precision of source count, e,:

2.

(d E q Ai: y o w e c.JM

2. Precision of standard count, e,:

3. Error due to background, e,:

1 c) Total Error TE=SE + RE = 2 7. 3'/,

RE=

+ e ' + e ', + e *3 =

• 3. 4 */,

i IPL participates in a NBS measurement assurance program to establish and maintain implicit traceability for a number of nuclides, based on the blind assay (and later NBS certification) of Standard Reference Materials.

NOTES The error given is calculated at the 93 % confidence level.

(/)

(/ )

This calibration is M/ indirectly based on NBS Standard Reference Material No. a!Es.2 cob Y0 1k,K}

J 4M Cprios A. Henkel (7NJ Obality Assurance

-Y i

ISOTOPE PRODUCTS LABORATORIES 1000 No Meystone St.. Surbana, cas forma-91504 I

e

9 e

9 A

p e

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ElBERIERI

t o'

CERTIFICATE OF RADIOACTIVITY CAllBRATION f

Isotope:- 00 b Half-Life: I. A7tfo.00/ 7 Source No.: /WW.S Was assayed as containing: s t. 6 As of: Il-I-f L METHOD OF CAllBRATION:

( /)

The source was assayed on a 3" x 3" Nal (TI) crystal in conjunction with a single-channel analyzer, using the {-@ lculations),against Cf standa MeV peak (a value of l

gamma rays per decay was used in the ca No. %.L, in the same geometrical arrangement.

(

)

The source was assayed in a windowless internal proportional counter against standard No.

(

)

The source was assayed by alpha spectrometry on a surface barrier detector in conjunction with a single-channel analyzer, against standard No, in the same geometrical arrangement.

The souece was prep 6 red from a weighed aliquot of a solution whose

(

)

activity in uCi/gm was determined by the method indicated above.

l f

ERROR CALACULATION:

Systemauc errors (SE) b)

Randon errors (RE) a)

1. Accuracy of the standard:i 2.fM.

1. Precision of source count. e,:

2. Precision of standard count, e,:

l 2.

3. Error due to background, e :

3 l

Total Error i

c)

TE-SE + RE =

• 4.06 RE=

+ e * + e ', + e's = * /. 3 %

I l

l IPL participates in a NBS measurement assurance program to establish and maintain implicit traceability for a number of nuclides. based on the blind assay (and later NBS certification) of Standard Reference Materials.

NOTES

(/)

The error given is calculated at tha 9c) % confidence level.

( /)

This calibration is 6~#/ indirectly based on NBS Standard Reference Material No. 49'fC S 2Cbl I.,,.,,

Qarlos A. Henkel m(- W [

C[uality Assurance ISOTOPE PRODUCTS LABORATORIES 1800 No. Keystono st. Surcana. Californe'91504

CERTIFICATE OF RADIOACTIVITY CALIBRATION 1

~.

30.060.27 Half-Life:

Isotope: 05.e37 Sourde No.: fo: M 4 Was assayed as containing: 10.:

Ce As of: 11-1-s2-METHOD OF CAllBRATION:

(/)

The source was assayed on a 3" x 3" Nal (TI) crystal in conjunction with a single-channel analyzer, using the 0.G> MeV peak (a value of 0, et;;4 gamma rays per decay was used in the calculations), against dstandard No. s3094, in the same geometrical arrangement.

(

)

The source was assayed in a wie.Jowless internal proportional counter against standard No.

(

)

The source was assayed by alpha spectrometry on a surface barrier detector in conjunction with a single-channel analyzer, against standard No.

In the same geometrical arrangement.

(

)

The source was prepareo from a weigneo aliquot of a solution wnose activity in uCi/gm was determined by the method indicated above.

ERROR CALACULATION:

a) Systematic errors (SE) b)

Randon errors (RE)

1. Accuracy of the standard:

• 3.3'/*

1. Precision of source count, e,:

2.

2. Precision of standard count, e,:

3. Error due to background, e :

3 c) Total Error TE=SE + RE = 2 'f N*

RE=

+ e l + el + e $ = * /. 2"/.

IPL participates in a NBS measurement assurance program to establish and maintain implicit traceability for a number of nuclides, based on the blind assay (and later NBS certification) of Standard Reference Materials.

NOTES

( /)

The error given is calculated at the 99 % confidence level.

( /)

This calibration is nu_ih/ indirectly based on NBS Standard Reference Material No. #001

$ sj I

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CArlos A. Henkel af quality Assurance ISOTOPE PRODUCTS LABORATORIES 1800 No. Keystone st. Bureank, Cat.fomia 9,1504

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28 J-4722r Buyer D. J. Yelton CH ANGE ORDER feo.

f OUALITY CLASS - SAFETY RELATED Procurement I4 vel II Please refer to our Order No. 81500053 dated Nay 3, 1980 covering Eigh Bange Radiation Monitors and Wide Range Gas Nonitors for San Onof re Euclear Generating Station, Unit 1 TMI Project and change as follows:

YTER 50. 136 WOW READS (in part)

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27 J-328Cr D. J. Yehon CH ANGE ORDER No.

Buyer-OUALI'"Y CLASS - SAFETY RELATED Procurement Level II l

Please refer to our Order No. SlS00053 dated October 15, 1981 covering two (2) Migh Range Radiation Monitors and two (2) Wide Range Gas Monitors for San Onofre Nuclear Generating Station, Unit 1 - TMI Project and change as follows:

NOW READS SHOULD READ Item No.

Ouantity Ouantity 30 11 16 5 6 $35.00 ea) 31 11 1

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Delivery of this me ed by March 4, 1983.

Acceptance of this sh ased on:

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Revised Total Cost

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cccordance with requirements of the Purchase order for San C sfre Nuclear Generating Station, Unit 1 TMI Project and chan@e supplier nLae as follows:

NOW READS SHOULD READ G:neral Atomic Company GA Technologies, Inc.

Special Products Division Total cost remains $ 385,836.60.

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1 SA4 ONOFRE NUCLEAR GENERATING STATION REVISION O PAC.T Aof2 b.IT 1 ICU C -/

6.0 PROCEDURE (Continued)

LOG-COUNT RATE CALIBRATION VALUES

.3 (Pulse / Min]

Allowable Output Pulse / Min (Count / Min)

(

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h fdct aeq 7'C,M o -g 6.0 PROCEDURE (Continued)

.g 6.2.1.3

, Connect the counter to the input of the log pump circu'tt -

l (TP2 to TPI).

6.2.2 Log Pump Circuit

.1 The log pump circuits in the module convert the random 1- -

pulse train input to a direct current voltage which is e

amplified by the meter amplifier to provide the module j

output. With the module output calibrated proper performance of the log pump circuits can be verified.

i

.2 Set $101 to the GROSS position. Connect the precision I

pulse generator to A-El er J1-7. Adjust the pulse amplitude to - 1.0V peak.and the pulse rate to the values in Table 1 connect the OVM to TP3 and verify that the

(

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.3 LO3-COUNT RATE CALIBRATION VALUES Fulse/ Min (Count / Min)

Pulse /Sec = (Pulse /M14 Output Allowable

(

100 T.

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ll) RESOLUTION TO COMMENT FOR OPERABILITY E. SU8VEILI$ANCE PROCEDU M2 4 hheProieetoolievinto incinAa all appmp-4 i t s. fil e !onal l I ", f pnd operational test requirements in 'ING approved gest; pro-gg peduresforeachworkpackage. Any operabili ty anq y veillanci

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lyit should be incorporated into these test procedt{res } The l

procedures are developed from Project Test Pr >cedudeGhidelines l

lthat include requirements to demonstrate opersbilitly, l l

fompliancetocodesandstandards and test special l des 4gn l

l l features. Any special te:hnical specificatio1 test { requirenent l

can be added to the TPG.

Engineering has agr eed'tcgfe l

Station and Startuo reviea and coment on the TPG. _Si[ ice the l

htationapprovesthetest procedure they can ensurd j

l lrechnical Specification a id surveillance proceduredard l

l includes.

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.rt.nr. A t.:

su m - u-a.v UNREVIEWED SAFETY QUESTION AND ENVbONMENTAL EVALUATION so r - s esu - oo sq-Mifj REV NO.

O STATION DOCUMENT NO. * '.

.L. n _ m

(

CFR 50.59 REVIEW FOR STATION DOCUMENTS (See Note 1) implementation of this document pose an unreviewed safety question per 20 CFR 50.597 o

1.

Is the probability of occurrence or the consequences of an accident or malfuntion,of equipment important to safety previously included in the Safety Analysis Report increased?

YES*

WNO 2.

Is the possibility of an accident or malfunction of a different type than any included previously in the Safety

/

YES*

NO Analysis Report created?

3.

Is the margin of safety as defined in the basis for any YES* / NO technical specification reduced?

Negative responses to the above questions require justification.

Ys 15 en dmini.shnl,be lype.prx4re. Nln.t uo #fekou h Justification:

cu sudsah(, assdis uwjsf ASw.'N oNer. Chb 6s, py nu,,'

Does implementation of this document violate the provisions of any YES*

NO Technical Specifications?

Reason: 'Tl/s brocedure. s's ecmh.2f'Ue wi$ CAajeko-G Af $

i i

s N Tiednicad 5) edh, W ble6

.ny one of these answers is yes, NRC concurrence must be sought via Sct Compliance / Licensing organizations prior to Station Document approval.

ENVIRONMENTAL EVALUATION:

l Could implementation of this document pose adverse environmental effects of any type either directly or indirectly? (Unit 1, 2 or 3 Operating License, Appendix B)

POSSIBLY Reason:

(See Note 2)

/ NO "The nature of this document is such that it will not result in a condition which significantly alters the impact of the station on the environment":

PREPARED BY:

/

///9/fd uncti5 Station Manager or Designee

/

'Date l

N tes:

1.

If an unreviewed safety question is posed, document shall not be approved. Return entire package to SPG for transmittal to NARC for l

Unit 1, the Nuclear Safety Group for Units 2&3 and CC&C for all documents.

I

(

If an environmental question is posed, document shall not be l

2.

approved. Return entire package to SPG for transmittal to the l

Environmental Engineer for the environmental review, i

COPY FORWARDED TO THE NUCLEAR SAFETY GROUP:

PERFORMED BY:

CDM Date l

(502/3 and S0123 series dccum nts) 50(123) 109-1, Rev. 0 7-18-83

-