Text

Insp Rept 70-1193/75-10 on 750731-0801.Major Areas Inspected:Details of Licensee Nondestructive Assay Sys for Inventorying in-process Pu.Portions of Rept Details Illegible
	ML20209D355
Person / Time
Site:	07001193
Issue date:	09/05/1975
From:	Hind J, Mcgonnagle W, Peck C; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	;
Shared Package
ML20209D148	List: ML20209D144; ML20209D165; ML20209D191; ML20209D202; ML20209D214; ML20209D237; ML20209D247; ML20209D259; ML20209D265; ML20209D276; ML20209D281; ML20209D289; ML20209D303; ML20209D322; ML20209D331; ML20209D337; ML20209D355; ML20209D364; ML20209D778;
References
	FOIA-86-281 70-1193-75-10, NUDOCS 8609090273
	Download: ML20209D355 (24)
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UNITED STAIES ?WCLEAR REGULATOP.Y CO:0!ISSIO:i

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OFI' ICE OF I!!SPECT10N Ai!D ENFORCEMEPIT

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REGION III

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IE Tuspection Rcrort No. 070-1193/75-10

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Licensee:

Kerr-licGee Nuclear Corporation

Kerr 'icGee liullding

Oklahoma City, Oklahoma

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Cimarren Facility, Plutonium Plant

License No. SIO!-1174

Cresent, Ohlahoma

73028

Category: .A

Priority:

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Type of Licensec:

Plutonium Puel Fabrication

Type of Inspection:

Special, Announced

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Dates of Inspection:

Mulpl 31 ^-" August ' 1,f 19 75 .

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Principal Inspector:

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Accompanying Inspector:

W. J. McGonnagle

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Other'Acconpanying Personnel:

None

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[G..J.A.Ilind, Chi

Reviewed By:

Haterials aa.d Plant

(Date)

Protection Branch

Attacheent:

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(10 CFR 2.790 Information)

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SUtIMARY OF FINDINGS

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Inspection Surmarv

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Inspection on July 31 and August 1, 1975 (75-10):

Fact-finding inspection

to learn deta'ils of licensec's nondestructive assay (NDA) system for

inventorying in-process plutonium.

Information was obtained ca quantitics

of plutonium found and their locations, measurement procedurcs and

equipment, and limits of error assigned to the measurements.

NDA system

has been used on three bi-monthly inventories for the measurement of

inaccessible plutonium, and program is considered to be in developmental

phase.

4

Enforcement Itejg

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Hone.

Liccusce Action on Previously Identified Enf orcer:.ent Items

No previously identified enforcement items.

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_Other Significant_ Items

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Systems and Components

Not applicable.

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B.

Facility Iterta (Plans and Procedures)

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Not applicable.

C.

Manageria! Items

.None.

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D.

Noncompliance Identificd and Corrected by Liccusec

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None.

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Deviations

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None.

F.

, Status of pteviously Reported Unresolved Iteras

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No previously reported unresolved items.

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"IE Inspection Report No. 070-1193/75

IE:III Copy No.

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of 3

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Manar.cment Interview

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Licensee representatives were advised that the data and detailed infor-

mation chtained by the inspectors had resulted in an improved under-

standing of the 1:DA system. The inspectors had no further questions

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at the time.

Ilowever, it was stated that there might be further

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questions concarning the licensce's application of !!DA theory and data

interpretation after additional study of the information obtained.

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REPORT DETAILS

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Persons Contacted

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R. Janka, llanager, Administration and Accountability

R. liarshall, Analytical Supervisor

W. Severc, !!athematician

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R. Adki sson, Supervisor, Safeguards and Security

Status of NDA Progran

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The licensee began the development of a nondestructive assay system

for inventorying inaccessible plutonium in his process system in

October 1974.

Inroduction of this type of measurement was prompted by

a change in license conditions effective in July 1974 requiring that

all plutonium on inventory be measured. Prior to this change, the

licensee had been permitted to includ.c a constant flo3 dup. quantity of

18.7 kilogtmas in his inventory to account for mat 2 rial inaccessible

for,tncasurement by conventional sampling and analyttical techniques.

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The 18.7 kilogton amount was determined from a scr!!cs of four material

balances based un physical- inventories conducted in early 1973.

For

the ptrpose of determining the holdup quantity, thr IIUF component of

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the r:cterial balance was considered to be .cqual to holdup.

From the

availabic materir.1 balance data, the licensee selezted 18. 7 kilograas as

his " constant" holdup quantity, and 'used this as ar inventory const:nt

f rom July 1973 through January 1975.

Although the revined license conditions.of July 1974 prescribed that

all plutenium be measured, the .licenscc was not prapared to initiate

a full-scale !!!B ucasurcrent system at that time md was found to ba

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in nuncempliance shortly thereaf ter for continuing to assume the 16.7

kilograms of unmearured holdup.

lhe licensee contruded that an NDA

measurement systen vould require several c.onths of experiment and

development and that the Jarge uncertainty associatted with this type

of ucasurenent would make it impossibic to ncet the LEMUF limit of

the licence, which cas 1.S kilograms cf plutonium. In January 1975,

Licensing increased the permissible LtJIUF limit to 5.0 kilograms.

In

subsequent bi-ocuthl/ inventorics in liarch, May cul! July, plutonium

measured by NDA has been of ficially a part of the aatal physical

inventory.

Ostensibly the tiDA progran has been successful barnure the IRIP cor.ponent

of the three naterial halances conducted since its inception has hcon

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icss than hDIVI' and LE tul' has been less than 5.0 kiilogrcms.

It was

cone,1uded by the inspectors, houever, that the prmram is still evolving

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the best evidence of the reliability of NDA quant tics will be

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and that

the conclusion of the FFTP program when the process will

forthcoming at

be subjected to a cotaplete cleanout.

Final material balances at that

time should dutcrmine whether inaccessib]c plutonium that has been

measured by NDA appears as product or whether there are significant MUF

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discrepancies.

NDA !!casurement Ouantitics

The UDA program has been an effort to measure all plutonium in the process

(glovebo::cs, pipes, operating equipment, and the process filtration system)

after routine cicanout procedure havs been completed prior to a bi-conthly

The total UDA quantitics measured haw tended to increcsc

inventory.

f rom the first trial ef fort in October 1974 through May 1975,. then

there was a decrease in July 1975. The increase :in totals in .the earlier

ef forts is considered to have resulted from increased- experience and

knowledge of the locations where plutonium was most likely to be foun'd.

The decrease in the most recent inventory probably resulted from the

fact that the overall plant inventory has been prcgressively decreasing

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and the inaccessibic holdup quantity has also fintily begun to decrease.

A summary table of plant and NDA totals appears below:

Plant Total (3),

NDa Total (e-)_

Inventory _Date

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October 1974

296,456

11,977

December 1974

281,064

11,771

January 1975

251,435

12,949

March 1975

243,641

20,045

May 1975

200,949

29,122

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July 1975

137,270

24,338

. The NDA totals in the tabic are not incluihd in the plant totals

Note:

for October, Deceuber and January since NDA was is its experimental

The UD.\\ totals for March, May, and July rc included in the

phasie.

Plant totals.

The plutoniun measured by NDA has beca distributni anoung all arcac .or

roonn of the plant.

No particular arca has been found to contain the

most material consistently, but the area which has averaged .the highest

for the six inventories is Roon 127. This is a s: rap processing area

a dozen gloveboxes in which sevcral operations such as

containing about

the burning of combustib]cs, calcination of ash, dissolution, solution

The manual handling

evaporation, and ion exchange separation take p1rce.

of ,the het.crogeneous ansortment of materialc protnbly leads to more

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spills and dust than in any other plant area.

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NDA measurements are inade after the process has been cleano

up for

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inventory.

Operations are not

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resumed in any area until the counting

has been coLpleted.

No movement of material in adjacent areas that

might affect the counting is permitted.

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At cach glovebox location where material .is rmonted, the general procedure

is to t3ade tuo 30-second counts.

The collimator is them covered by a

lead shield and tuo 30-second background counts are made.

Background

counts are subtracted from the gross counts to give two corrected counts,

which are converted to grams of plutonium (per square foot of area in

the case of a glovebox measurement or simply grams of plutomium in the

case of a pipe measurencnt).

The formula-is:

p

g , (gros _s counts - backnround counts)

'g

transmission constant

The transmission constant is a factor for the type of material through

which the neasurement is nade.

Sope of the constants used are 0.96

for Plexiglas, 0. 71 for stainless steel, 0.57 for Icad glass, and 0.97

for a leaded glove. The constants are obtained from tabics.

The

licensec has cyperinentally confirmed one or tuo of the more generally

used constants.

The calibration constant is the ratio of grams plutonium

to counts as determined from standard measurcreentq.

In determining the amount of plutonium in gloveboxes the following

technique is used.

The grams per square foot are determined at approx-

imately two fort intervals alonr, the length of the glovebox.

Thesc

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determinations crc averaged and ciultiplied by the total surface arca

involved.

Usually it is necessary to measure the plutonium on both

horir.ontal ind vertical surfaces of gloveboxes.

Horizontal surfaces are

' measured by pocittening the detcetor above or underneath the surfacc

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whichever is taore c6nvenient.

Vertical surfaces are measured by holding

the detcetor in a horizontgl position.

For convenience some measuraments

are made at an angle of 45 - Appropriate changes are made in the trans-

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mission constant in such instances.

In pipe mearurements counts are

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converted, using the proper calibrator factor, directly to grams of

plutonium.

In pipa measurements the grams of plutenium in a two foot

length of pipe are determined.

Sinilar detcrcsinations are made at other

positions a'onc, the pipe.

The vetchted average is then multiplied by

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the length of the particular pipe.

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It was noted t hat the atrount of counting that has been donc during the

six UDA inventerit: has tended to increase.

In the' July inventory counts

were made at 1131 bex Jocations and 416 pipe locaticas.

Assuming

about three ninutes to get the data at each location, it is estimated

that box measm ement s required 57 hours6.597222e-4 days <br />0.0158 hours <br />9.424603e-5 weeks <br />2.16885e-5 months <br /> of work, pipe recasurements about

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20; hours.,

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The second highest UDA inventory arca is the solvent extracti

ca.

This arca consists of three tall gloveboxes containing solve ~nt extraction

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columns which extend f rom the base:r.cnt to the ceiling of the first floor,

approximately 25 feet. Most of the plutonium is within the equipocat.

Since March 1975 the columns have not been used.

The room has been

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closed, the piping scaled of f and tbc March plutonium inventory carried

as a covaricnt item in the two subsequent' inventories.

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Rooms 128 and 124 rank next in NDA plutonium.

Room 128 contains the ceramic

processing gloveboxes in which plutonium is converted from the nitrate

to the dry oxide powder. The upper portion of the tall glovebox containing

the nitrate blending and weigh tanks ,is also in this room and has been

found to contain significant amounts of plutoniun.

Room 124 is the pellet

fabrication area.

As much as several hundred grams of plutonium has

been found consistently in cach of.the several pieces of operating

- equipment in the glovebux train. The presses, blender, grinder'and

furnace, although all emptied to the extent that they could be without

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dismantling, all consistently more than 100 grams by NDA.

Rooms B01 and B02 have been found to contain relatively smaller quantitics

of plutonium.

These are arcas containing liquid processing equipmcat.

B02 contains the lower portions of the nitrate blend tanks and some

boxes housing pumps.

B01 contains boxes,in which scrap liquids

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ara

filtered.

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Process piping has been found to contain less plutonium than any of the

individual roons or areas. The totals for all piping have been about

1500 grams for each of the last three inventories.

Attachment A is a listing of average plutonium quantitics found in cach

area with sub-listings of amounts found in the major pieces of equipment

within those areas.

Measurement Progtyjurcs

Af ter. calibratien of the two measurement systems agninst standards (summarized

in a later scetien) to establish the relationship betg'ecn counts and grams

of plutonium, the proccos material is measured. .Tvo electronics systems

are used for MDA notk, a SAM II (Scintillation Amplitude Monitor) made

by Eberline, and a Ludlun system.

Each is coupled to a collimated

sodium iodine detcetor.

The Ludlum is an older instrument and does not

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appear to be a stabic as the SN! 11.

Becadse of the more modern

circuitry, the counting rate with the SAM II can bc higher than that

of the Ludlum uithout losses due to pulse pile-up and dead time.

Far

'these reasons the SAM II is used for counting of material in gloveboxes

which contain the larger quantitics while the Ludlum's use is restricted

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to p'iping.

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It was oJse observed tint quantities of plutonitra c casured hdvc increased

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generally an the amount of counting has increased. This is attributed

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to increaned experience.

As knowledge has been acquired on where

plutonium is nost likely to be found, more i-n:phasis and increased

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counting cffort has been expended in these arcas. The licensec stated

that there uns no likelihood that a saturation point had been reached

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in counting which would lead to overlapping counting and the measurement

of sorre plutonium twice.

lic estimated that even at the current level of

counting effort, only about 20% of the total surface area and pipin;; are

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being tieasured.

Attachment B is a completed data shee't which illustrates the calculation

of the grams of plutonium in a particular glovebox.

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Calibration Standa_rds

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Standards that have been used to establish the relationship of betzecn

counts and grams of plutonium are of two types, one for box measurc:lents

the other for pipes.

The standards for box weasurements, the more critical of the two, nre.

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flat plastic packets about one squarc' foot in area. They were made

by mixing n weinhed quantity (about two grams) of plutonium from current

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produ.tfon uith a natrix catcrial uithin a glovchex, then inserting the

mixturc into a heavy PVC-type plastic bag. The pscket standards used

on the first five inventories contained a mtrix af Kcculpe material

inpregnated u t th plutonf uta nitrate.

Because of ' tic possibility of

deterioration of these standards, they were replamd with similar size

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packets containing a liquid paint resin mixed uith plutonium oxide.

The neu standards were used in the July inventory

The stpudards for pipes consist of one foot sectims of pipe of appropriate

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diameters containing tuo crams of plutonium. The plutonium was depasited

on Kemwipe matrix raterial which was then rolled tp and inserted it:o

the pipe so that distribution would be unifom.

'Ihc first standards

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made contained plutoniuia in the nitrate form but these have been replaced

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by the oxide f or because of the potential Icahage hazard.

Calibration verk is accoeplished in a laboratory urca that is as far

renoved as possible from background interferences.. Tho ' racasuremen t

equipment has t;ecn recalibrated to establish neu calibration constants

prior to cach inventory.

Packet standards are cotnted singly and also

grouped with twa or four packets laid one over aucther to establish a

The calibratien constatjt established in this vay for use in

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constant.

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the. July inventory was 3.S0 x 10

grams per count for a half minute

counting period.

Plpe standards are similarly cotuted to determine a

con,stant. The l'asic pipe constant for the July fincntory was 2.07 x'10

jounts per gram for a twelve second counting peritd.

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In counting packet standards and in actual plant measurements,

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detcetor is usually positioned about thirty inches from the source.

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Exact distance is not critical because the arca acasured increases as

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the square of the distance, so that the ratio of area to distance is

always constant.

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Limits of Error

The licensec has developed a statistical system for determining the

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limits of error associated with the plutonium measured by NDA.

Since

the !! arch inventory when NDA quantitics of ficially became part of the

inventory, the LE 'or NDA has been the major portion of the overall LE.

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The tabic below shot:s the LE's associated with NDA as well as the

overall LEMUF for the plant for the three inventories in which NDA has

been used.

Inventory

NDA Total (g)

LE (NDA),

' LEtWF

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March

20,045

2,719

2,779

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tiny

29,122

2,774

3,578

July

24',333

2,660

2,742

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The system presently used for calculating systematic and random errors

associated with I'DA is set; forth in a report prepared in Ifarch 1975.

The experinents performed and the equations used to convert the

experinental data to errors are described. The report is presented as

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Attacher.nt C.

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Sourecs of systenatic crror considered in the report are those associated

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with the various calibration curves, the g .in spectra erro g hich is

en allowance for the interfe'rence of the

U daughter of

Pu, and

the errors due to counting geometry.

The sua of all these systematic

errors, has been only a small portion of the total I.E for NDA measurements.

Attachment D uhich itemites the NDA crrors for the May-July inventory

period illustrates this point.

NDA random errors constitute a much larger portion of'tha total LE for

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NDA than do the systematic crrors. The random errors are calculated.

from the replicate neasurement data accumulated during the NDA invantory.

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This is poss!ble since cach measurement is made in duplicate. Attachment

D indicates that randem crrors, particularly those associated with the

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sampling method, ' constitute the major part of both the LE for NDA and the

LE for the July inventory.

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The licenace points

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calculated from cur-

(RSD) that are appl

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are current and not

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Bias _Correcti'ons

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The licenece began

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inventory in llarch

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NDA measured plutou

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amperomet.ric titrat

of magnitude than h

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below summarizec th

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Bias corrections at

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for cach type of in

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the bias ratios thr

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of 1.075 and 1.027

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taining a knoi.n ae.

of 1.121 for filtc'

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contuinfug a 1: cot:n

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sirailarly obtaincd.

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biases on there tyi

systematic crror q:

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detector as explai-

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ratios are taultip!

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Conclusicos

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The Jicense; han considered many of the theoretical causes of inacburacy

in determining tbc limits of crror and bias,

lloucver, all the me'dsure-

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ments and the calculated limits of error must be based on standards and

simulated conditions stated that the licensee can only hope are repre-

sentative of the plutonium that he is measurinC in the plant.

There

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could be vide differences between laboratory and plant conditions.

There is no assurance that standards consisting to weighed amounts of

plutonium in~ plastic packets and sections of pipe can represcat all the

material in the plant. The plutonium in the plant exists in many different

physical and chenical forms and geometries.

The Camma ray response will

vary extensively because of differences in self-absorption and georatry

among the varions forms.

In most instances it is not possible to know

just what form the plutonium being counted is in.

When measuring a pipe,

for example, there is no certainty as to whether the plutonium inside

the pipe is solid, liquid, in pockets, or in a continuous stream,

or uhat the depth of the stream might be.

Similarly it is not possible to

know much about the distribution or form of the plutonium in a,glovebre or

piece of equipment.

An attempt to make up standards to represent all~

the possible situations would not be feasibic.

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In addition to the foregoing r,cncral concents on the problems of

relating laloratory da.tc to plant conditions, there appear to be some

specific measures that could be taken by the licensec that might

improve his results.

These are:

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A self-absorption (or scif-attenuation) correction should be

developed.

For the packet-type specimens used for calibration,-

the measured count rate can be expressed as follows:

licasured count rate

l'N (1-CN)

a

where K = counts /g of Pu per unit time

11 a

number graes of Pu

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attenuation constant per Eram

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Using date that the liccusec recently established for two packet

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' type samples, valuco for K and C can be calculated.

The data:

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1365 counts / min for a 1.936 Cran standard

4089 counts / min for a 7.744 gran standard

From the data the following table can be prepared:

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Unsttenuated

Grams Pu

Heasured Counts /:lin

Counts / Min

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1.936

1365

1479

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3.872

2514

2956

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5.808

3416

44S7

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7.744

4082

5916

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The curve of measured counts vs unattenuated counts plotted from

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the above table,' could be used to correct cach plant measurement.

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TheoreticalJy it appears that such a correction should be made.

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The cffeet of the correction would be to increase the amount of

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plutonium racasured by NDA by 10-20%.

From a practical standpoint

this is in the urong direction because the quantity of plutonium

currently being found by NDA appears to be too high, although this

~

in only n guess.

,

.

2.

The use of two sets cf standards primary and secondary, both

prepared in the same way might be useful.

Use of the primary

standardc would be confined to the laboratory for the purpose

of instrument calibration.

The secondary standards would be for

in-plant use for instrument checking, background studies, and

.

measuring attenuation constants. .They would be useful, in other

words, in translating laboratory measurements into plant

measurements.

,

.

Attachments:

I

Attachment A through D

.

e

.

4

9

4

.

e

.

t

l

.

l.

-

,.

.

,

.

g

,

.

$

- 12 -

.

_

.

I

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. . - - -

-

. - , , _ _ . , . _ _

_

___

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

,

I

t

.

1

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'

.-

,

i

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i

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Room 127 Scrap,Arca

'

.

l

t

Box 2,3, 24 - Sc

.

k

Box 25 - Dissol

-

.

l

I

Eox 31 A - Icn E

l

~

.

Box 31B and C -

.

9

Box 32

>

6

Box 33

.

t

Filters and Duc

Hiscellanceus

Room 127 'l

'

.

'

.

Baserent - Scilvent I

.

Room 128 - Ceramic /

-

.

Box 10 - Poude

Box 10 - Calcir

, .

.

?

.

Box 5 - pl! Adjt

1

l

Box 5, 6 - Filt

!

'

.

Box 3 - Nitrat<

!

.

l

Box 4 (Top) - t

'

Powder Carte. (:

Niscellnneoun

i

~

'

.-

Room 178 '

>-

.

-

.

.s

6

,

e

$

.

- - - -

_ _ _ _ _ _ _

m

_

-2-

.

,.

.

Room 124 - Pellet:

.6 nos. Av

Fabrication ~

Range O

Box IIB - Prese and Dionder

.

\\

i

444

Ilox IIA - Calciner and Slugger

108

,,

Box 12 Coivreyor

3go

193 ,

Dox 14 rurnace Outices

57

15 -

568

Box 15 - Grfnder Inspection

60 -

Filters and I)ucts

'1934

136.-

llisec11ane.:oun

444

224 -

i

122

~50 -

Room 124 Total

.

3049

'

logy _ ,

Roem E01 - I.iquid Scrap Recovery

Fox 40 - A ncous Recovery

i

'

39

liox 39 - 1,ou l'u D1 solution

g,9

4

.

353

Box 1A - l' ump flood

45 - 7;

,

.

llisec31anecos

93

,

49'- 14

,

'

255

Room 001 Total

100 - 35i

.,

1079

387 - 23C

Room h02 - t:lt rat e !;1end and h'eigh

.

Box 4 - tiltrat c Diend (Lou Porti

on)

111e

Box 1 - Punp Dox

293 - 216:

,

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'

}!isec11anecos

270

g_m

286

Ro m E02 Total

100 - 350

.

,

167h.

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741 - 2776

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Range (Low and liigh)

-

$

.

Piping : All Areas

B01

155

115 - 184

'.

-

1284

762 - 1636

B02

B01 to B02

130

79 - 199

,

P,01 to B127

154

27 - 218

~

..

.

B01 to B128

276

61 - 378

B01 to 1:128

124

26 - 221

'

Itiscellaneous

56

25~ .75

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CA1.CUI.AT101:S FOP ERROR STATI'!!Ellt

k

.

HDA II: vel *CORY 3/75

j\\

-

...

' A. ' Systema t ic Er ro r

1.

Calibration Curves

Calibration curves represcuting various measurenents were pec-

.

pared by counting standards. The systematic crror (variance)

.

for 'cach curve 9as calculated as follows:

'

,

.

i

(ga_(ExvF)

2

I

.

s yx=

y

1

n- 1

ExTi c-

7. x'-

t

Where: s yx e Variance of y about x

,

tiumber of dif ferent calibration points

n =

cpu or gPu/ unit for cach standard

y =

Counts / unit time

~

x =

This equation represents that variance of y alicut x for the

cquation:

y = bx.

If the uncertainty of the content of tbc stanfords is known

to be significant relative to Sy.x and if more than one cali-

bration curve is prepared for a given type of measurement',

then the contributing errors are pooled and t.be systematic

,

variance calcuinted using:

2c5~0Y

+ So

2

Sc

m%

h)

,

Uhcrc:

ScP= Systenatic . variance

, for all curves.

,-

En : .tetal nunber of calibration potrts

k

= tiember of calibration curves.

.

S y . x =: Relatin standard deviation for a calibration corve.

acLative standard devia tion for standa rds.

So e

llunb e r o f co tin ts taken per calibration point

m

e

Systematic errers for calibration curves used for the 3/75 NDA

Inventnry are L Lsted en page

6.

.

.,

'

2. ' Gamma Spectra

.

f'the 1:anma interfetence of concern is that of I" which has a

~

'

,'*

significant peak at 330 Kev.

A series of prol'uc tion sampics

asr.umed to represent materials inventoried wesc scanned with

,

~

a Ge-Li detcetor and the peak areas representdog the 330, 3f 5,

',

6

375, 393 and blfi Mcv peaks, determined. The entio of total

peak area to is t's peak arca was calculated for the standards.

.

9

.m

-

kmww. v c'

~

'

r-

.

- ~ - -

r.

.

,

'

.

'

.

\\ _\\

.-

.

From this rar.lo, a ' heore ti c a l total peak area was calculated

,

for cach sarvic. The ratio of actual total peak arca to thco'Q

,

retical tot .il peak a rea represents a gasc.ino counting error

'

37

caused by U

interference.

For cach campic type, a standard

deviation was calculated on the ratios as follows:

'-

.

_

)

si = .\\

n(n-1)

-

.

'

s t'a n d a r d deviation f o r a s a tap l e type

Uhcrc:

s1

=

n umb.e r o f sa mpic s of a given typc

n

=

,

total gamma ratio as explained in the test.

x

=

2

A relative standard deviation, Si

was calculated for-

'

cach sampic type and combined with a coun ting s ta tis tics

error as follows:

.

Sni =

i' + So'

4

-

\\

u

Where:

Ssi = sys tema tic relative s tanda rd deviation

for material. type a

SJ

relative standard deviation for material

=

type i from gamma peak areas

So

relative s tandard devia tion representing

='

.

s tandard source countin g erro r.

.

,

The'Pu 'found' by HDA Inventory uns divided into the

"

materini catagories represented by cli c gamma s canne :'

sampics.

See page 6 for the systematic crror calculated

g

for cach material type from gamma counts.

,

.

3.

Co un t i n g Cc o nc t r *,-

.

'

Counting genuetry errors were calculated for both

'

measuring techniques.

The two techniques are discussed

s e p ara te ly .

,

.

e

n.

Summin g Technique

~

,

An experiment was conducted in glorebox 21 wherein

known quan ti ties o f pu 'wc rc syme t rically dispersed

>

,.

a l o n t,

the Icnnth of the glovel.ox floo r.

The

matcriil was

'

cicasured using the sunning technique

-

.'

by counting the box at six locations.

Variation

.'

'

,-

in the anount of pu ' f o un d ' fron 1ccation to

.'

location was ascribed to a counting geonctry error.

A rela tive s tandard devia tion uns calculated using

equation 3.

.

Amwrn er c Ger

-

.

e.

!.

-

.

-

.

,

.

"

(

.

The relative s tandard deviation was determined

at two different loadings of Pu in llox 21 and

'

,-

equation 2

used to pool the RS D' s obtained.

-

, . ,

P a'ge 6 lists the RSD for the counting geonetry

sumning technique as well as the amoun t of Pu

measured via this te chniq ue and its' respe ctive

error.

-

.

-

b.

Sar;pling Technique

Since the saupling technique in vo lve s counting

glovebox surfaces at a va ric ty of dis tances ,

an experiment was conducted to determine the

(

'

cffect o f dis tance on the s a mp lin g,

technique

calibration.

The rela ti ve standard deviation on

the calibration data was calculated via equation

3.

The syntenatic rela tive s tandard deviation

.

was then en J culated using equa tion 4

-

Page 6 lis ts the sampling technique geometric

,

crror.

B.

Randon Error

'

1.

Clovchouce

a.

Sumnin g !!c thod

.

The summing method involves c o un ti n g the entire

'

arca of interest.

If the surface is counted in

sections, the gPu f ound pe r sec tion are summed

together.

-

.

Equa ti on 3 is used to. calcula te ta c standard

.

deviation associated with a glovcSox.

Fo r these

glo v e b o ::e s wherein i nsuf ficient da t a e xi s t,s to

'

calculate an RSD, a pooled RSD is used to

estimate cuch boxes RSD.

The pooEcd RSD is

calculated as follows:

.

,, , n ,3 - 1_) S i +(ni-1)S2 8+

* * ( n .- 1) S

5

'

(

-

2

g

3p

.

~

(n +na...

n g)

k

-

'

pooled RSD

'

,~

Where:

Sp

=

-

.,'

n1 = numbe r o f dif f e ren t me asuremen ts

.

,.

taken on ith item

Si= RSD on Ith item

k

numbe r o f dif f e rcu t btems.

a

.

e

'

.

/Mwutnr a r C Gwm

-

.

g.

. _ . . _. _

,

r

-

.

'

e

.

,

.

a

s

The error as cpu from all gloveboxes inc a s u re d

by the summin g me thud is calcula ted as follows

'

assuminC measurement from box to box as

.

'

independent o f e a ch o the r.:

,,

-

.

hEi * S i

+ 'Er*+Es'+...Ez'

n"

6

Sc'

=

,

.

ny

.

m

-

.

Where:

Sc= random error for all boxes measured

.

by the summing te chniq ue

'

gPu in ith glovebox

Ei

=

Si a RSD for ith glovebox

m

= n u mb e r replicate counto p e r d i,f f e r e r. t

meas urin g site.

Sp = pooled RSD

.

Er..Ez = gpu in gloveboxes without suffi-

.

cient data for Si calculation for

cach box.

,

.

The random cr,ror for glovebox summing technique

is listed on page 6

b.

Sanplin g !!c thod

-

.

The c ampling me thod involves me asurin g represen-

.

tative sites in a gl o ve b o x , calculatin g a gPu/

g u/ unit area

unit arca, and multiplying average

p

timec box crea to.dctermine Pu holdup.

Equation 3 is used to calculate the RSD fo r cach

,

.

C ovebox from the sampling method measurements.

l

.When insufficient measurements have been made to

.

calculate on RSD, a pooled RSD is applied as

'

cal cula ted f rom Equa tion 5.

Equotfon 7 is then used to cal c ula te the error

associated with all gloveboxes measured via the

~

'

sampjing mtthod:

...E[ SP*

7

Ei Si+

Sc'

'Er +Es

2

1

"

,

_

nim

m

-

.

.,

Where.:

all symbols re tain the same meaning as in

equation 6 but

ni n numbe r o f different

,

.

measurements taken.on

,

-"

./

the ith glovebox.

,

.-

,

-

,.

Sec page 6 for the randon e rror. fo r gloveboxes

.

measured via the sampling technique.

.

'

9

'

kerna

in c

aer

M

'

-

__ _ _ .

.

'

.

. . "

.

c.

Ductwo rk and Pipes

-

.

Errors asso cia te d wi th Pu measuremen t in du c two rk

.

an.d pipes were calculated usirg the sampling

method equations'of the prior section (b).

See

page 6 for these errors expressed as gPu.

.

-

..

-

.

R.S. ilorshall '

'

4/9/75

~

.

,

.

-

.

9

.

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, , - . - _ - . -

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.-

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-

-,

-.

- - - . - - , - - - - , , -

-

<

, - - - - - - -

-

.oy. _ggyzpyw..ggm------

-- -

-

).

SYS'ill!NTiC 1.Iti;0!!S

'

N

..

CllANGli g Pu

11 ilk)il g Pu

"

'

CATI!GoltY

3/75-7/75

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ML20209D355

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