ML20044E273

Rev 5 of Fundamental Nuclear Matls Control Plan

ML20044E273
Person / Time
Site:	07001201
Issue date:	04/22/1993
From:	FRAMATOME COGEMA FUELS (FORMERLY B&W FUEL CO.)
To:
Shared Package
ML20044E259	List: ML20044E258 ML20044E273
References
PROC-930422, NUDOCS 9305240128
Download: ML20044E273 (9)

Text

.

I FUNDAMENTAL NUCLEAR MATERIALS CONTROL PLAN DATE:

4-22-93 PAGE: 3-1 REV.: 5 3.0 Material Control & Accountability Measurements 3.1 Affirmations A measurement system has been established and maintained for all SNM receipts, removals and inventory items, and all quantities of SNM in the material accounting records are based on measured values.

A measurement control program is followed by which all measurement biases associated with key measurement systems, are estimated i

and any significant biases are eliminated from ID values and shipper / receiver differences.

l 1

Measurement systems that are-the key contributors to the total measurement standard error have been identified.

The list is reviewed annually and updated as necessary.

These are considered as key measurement systems and their standard j

deviations are monitored and controlled by j

the measurement control-program.

~

The estimate of the measurement contributions to the SEID is traceable to the appropriate measurement error data and to the calibration standards used.

l The total measurement error is controlled so that twice its standard error for a material balance period _is less than the greater _of 9 kilograms of U-235 or O.25% of the active U-235 inventory in the inventory period.

The measurement systems have_ adequate calibration frequencies, sufficient control of biases, and sufficiently small standard deviations to achieve the requirements of i

74. 31(c) (4 ).

A measurement control t

program is used by the licensee and contractors to assure that the quality of

.the measurements is maintained on a level consistent with the regulatory requirements.

)

i 3

CURRENT REVISION:

SUPERSEDES:

PAGE: 3-1 DATE:

12-01-92 REV.:

4-USNRC APPROVAL

REFERENCE:

9505240228 930422

{DR ADDCK 07002201 PDR

1 FUNDAMENTAL NUCLEAR MATERIALS CONTROL PLAN DATE:

4-22-93 PAGE: 3-2 REV.: 5 i

3.2 General A measurement system will be established and

[

maintained for all SNM receipts, removals, and j

inventory items > 10 grams U-235.

Typically, j

those items that are i 10 grams U-235 are either i

samples and standards or small quantities of Uo2 scrap material.

These items will either have measured values associated with them or will utilize nominal values traceable to a parent lot or contract.

LSA waste is collected in plastic bags and is typically less than 10 grams U-235 per drum (i.e., item).

This LSA waste is gamma scanned for U-235 content but is not considered a key measurement system as noted in the annex

[

to Chapter 3.

The total U-235 quantity generated for all items 5 10 grams U-235 that are based on nominal values is less than 1.0 kg U-235/ year.

SNM that is received as an encapsulated source (i.e.,

sealed fuel rods or fuel assemblies) may be accepted based on shipper's values provided the material is kept encapsulated.

SNM that is received for storage purposes only, J

i and is properly maintained and tampersealed may be accepted based on shipper's values.

Subsequent shipment of this stored SNM will also be made based on the original shipper's values provided the material has been properly maintained.

For fuel rods or fuel assemblies that are received and downloaded i.e., the pellets are removed from the fuel rod, the shipper's element and isotopic values may be accepted provided all of the following conditions are met:

1)

The fuel originated from B&W Fuel l

Company's Commercial Nuclear Fuel Plant.

t 2)

Traceability has been maintained to ensure that each fuel rod and its i

contents can be traced back to the production process.

3)

Fuel rod serial numbers will be checked prior to the downloading i

process to ensure traceability.

4)

The integrity of the fuel rod will be inspected to ensure that the fuel CURRENT REVISION.

l SUPERSEDES:

PAGE: 3-2 DATE:

12-01-92 REV.: 4 USNRC APPROVAL REFERENCE-

?

i

FUNDAMENTAL NUCLEAR MATERIALS CONTROL PLAN DATE:

4-22-93 PAGE: 3-3 REV.: 5 rod has not been tampered with.

5)

The shipper's values are consistent with the original B&W shipper's values.

Discrepancies will not be authorized for any of the 5 conditions.

For SNM that is to be downloaded and the pellets are to be returned to the pellet vendor for reprocessing and does not meet the conditions noted above, sampling of pellets shall be selected in accordance with the table below.

Each batch must contain one enrichment.

If enrichment varies amongst fuel assemblies or within fuel rods, a drawing that identifies the location of the enrichment variations must be available to separate batches.

BATCH SIZE (kgs)

NUMBER oF PELLETS FREQUENCY oF PELLET UO2 FUEL ASSEMBLIES TO BE SELECTED SAMPLING 0 - 100 20 each fuel assembly 100 - 300 15 each fuel assembly 300 - 500 10 each fuel assembly 700 - 1000 8

each fuel assembly

__ 1000 6

each fuel assembly In either case, the pellet boxes must be weighed and uranium content quantified.

This may be determined by using shipper's element and isotopic values or receiver's sample analytical data.

only those measurement systems which are the key contributors to the total measurement standard error will be subject to the controls in Chapter 3.

Those key neasurement systems that are identified have accounted for at least 90% of the total measurement uncertainty including those measurement systems that are used to measure SNM quantities in excess of 25%

of the active inventory at the CNFP.

The total measurement error will be controlled so that twice its standard error for a material balance period will be less than the greater of 9 kilograms of U-235 or O.25% of the active U-235 inventory in the inventory period.

l CURRENT REVISION:

SUPERSEDES:

PAGE: 3-3 DATE:

12-01-92 REV.: 4 USNRC APPROVAL

REFERENCE:

~

FUNDAMENTAL NUCLEAR MATERIALS CONTROL PLAN 1

DATE:

4-22-93 PAGE: 3-4 REV.: 3 3.3 Kev Measurement Systems i

Key measurement systems are those measurement systems which meet the criteria established in Section 3.2.

A complete listing of all l

measurement systems (incin3ing the non-key systems) are included in the annex.

This listing will be reviewed once every calendar year for adequacy and updated as necessary.

Changes may be made in the listing without NRC notification as long as a current listing is maintained at the CNFP.

3.3.1 Kev Measurement Systems 3.3.1.1 Uranium Powder / Pellet Receiv-ina and Shinoina Scale (s) i This system is used to perform gross weight measurements on Uranium powder or pellet receipts.

This scale's capacity is at least 35 kg and 1 scale division is at most i

20 grams.

3.3.1.2 Rod Loadina Scale (s) j The scale is used to weigh

[

Uranium fuel pellets that are loaded into rods.

The scale's capacity is at least 3 kilograms and 1 scale division is at most 2 grams.

3.3.2 Kev Analytical Measurement Systems l

All %U and %U-235 measurements based on analytical chemistry techniques (i.e.,

mass spec, gravinetric or titration, etc.)

are presently contracted out to analytical laboratories.

Audits of contractor laboratories are performed as indicated in Chapter 7.

.i I

3.3.2.1

% Uranium Measurement The % Uranium measurements used at the CNFP are based on analytical vet chemistry CURRENT REVISION:

SUPERSEDES:

PAGE: 3-4 DATE:

12-01-92 REV.: 4 USNRC APPROVAL

REFERENCE:

I r

FUNDAMENTAL NUCLEAR MATERIALS CONTROL PLAN

~

• DATE:

4-22-93 PAGE: 3-5 REV.: 5 techniques (i.e.,-gravimetric methods for fuel pellets and either a titration or gravinetric method for scrap material,.etc.).

NBS or NBL traceable standards are used to calibrate'the %U analysis method.

i 3.3.2.2

% Uranium 235 Measurement The U-235 measurement method for fuel pellets and scrap is a i

mass spectrometric technique.

This measurement system is calibrated using NBS or NBL traceable standards.

3.3.3 Uranium Pellet Samplina (%U and %U-235) j The frequency for sampling fuel pellets l

which are fabricated or received at the CNFP shall be dependent on the UO2 pellet lot size.

The table below outlines as a guide the sampling to be followed in choosing pellets from each lot selected.

Samples for %U and %U-235 ale-then analyzed as described in Section 3.3.2.

6 LOT SIZE (kgs) UO2 NUMBER OF PELLETS

' FREQUENCY oF PELLET EELLETS To BE SELECTED SAMPLING

> 2800 10 Every 6th box 2333 - 2800 12 Every 6th box 2000 - 2333 14 Every 6th bon 1750 - 2000 16 Every 6th box 1555 - 1750 28 Every 6th box 1400 - 1555 20 Every 6th box 1166 - 1400 24 Every 6th box 933 - 1166 30 Every 6th box 700 - 933 40 Every 6th box i

560 - 700 50 Every 6th box 350 - 560 80 Every 6th box i

CURRENT REVISION:

SUPERSEDES:

PAGE: 3-5 DATE:

12-01-92 REV.

-4 USNRC APPROVAL

REFERENCE:

i

1 FUNDAMENTAL NUCLEAR MATERIALS CONTROL PLAN DATE:

4-22-93 PAGE: 3-6 REV.:.5 A designated agent, operating in behalf of~

B&W, may select such samples, for B&W use, from the lot master sample at the uranium fuel vendor site.

Samples are then analyzed for %U and %U-235 as described in Section 3.3.2, with results reported to B&W.

B&W's. designated agent shall be accountable to B&W, shall have access to the lot master, and shall be permitted direct observation of the means by which the lot master sample is generated.

The designated agent shall not be in the employ of the uranium fuel vendor.

3.4 Measurement controls and Calibrations (Kev Measure-ment Systems 1 3.4.1 Mass Measurement Systems (Scales)

Only these scales identified in Section 3.3.1 are required to be calibrated and controlled by the systems described below (3.4.1.1 and 3.4.1.2).

3.4.1.1 Calibration Scale calibrations will be performed in accord with an approved written procedure.

Calibrations will be performed prior to initial use and thereafter on a quarterly basis or more frequently if necessary.

Scales will be calibrated to 1 scale division utilizing NBS or NBL traceable standards that cover the range of operation.

Calibration checks performed in 3.4.1.2 indicating deviations 1 1 scale division will result in scale recalibration.

Bias calculations for scales are as described in 3.5.1.1.

3.4.1.2 Calibration Checks Calibration checks are performed on each key scale utilized at the CNFP.

These checks are performed using NBS or NBL traceable standards at a frequency of not less than 2 times per plant operating shift.

Calibration check data is used to verify scale calibration while in use.

CURRENT REVISION:

SUPERSEDES:

PAGE: 3-6 DATE:

12-01-92 REV.: 4 USNRC APPROVAL REFERENCE.

1

FUNDAMENTAL NUCLEAR MATERIALS CONTROL PLAN j

1 DATE:

.4-22-93 PAGE: 3-7 REV.: 5 A calibration check log is used to.

record the difference in actual standard weight from the scale indicated weight.

Scale performance is monitored by using absolute control limits based on scale divisions.

If a calibration check indicates a difference of 1 or more scale divisions the scale is recalibrated and items measured on the scale during the out-of-control situation are remeasured as necessary.

4 3.4.2 Analytical Measurement System Both the %U and %U-235 measurements described in Section 3.4.2 are controlled as follows:

At least ane NBS or NBL certified standard will be analyzed on each measurement system each week that process items are analyzed.

Measurement control for these systems is maintained by the analytical laboratory.

3.5 Measurement Bias and Statistics 3.5.1 Measurement Bias 3.5.1.1 Scales Bias calculations for scales are based on calibration check data.

. Bias estimates are updated every material balance period (at inventory).

If-the calculated bias is greater than twice the error associated with the standards, the bias will be used to correct the inventory values.

3.5.1.2 %U and %U-235 Measurement Bias calculations will be performed for

%U and %U-235 measurement systems based on standards data.

Bias estimates will be updated every material balance period (at inventory).

If the %U and %U-235 calculated bias is greater than twice the error associated with the standards, the bias will be used to correct the inventory values.

l 3.5.2 Statistics CURRENT REVISION:

SUPERSEDES:

PAGE: 3-7 DATE:

12-01-D,;

REV.: 4 l

USNRC APPROVAL

REFERENCE:

FUNDAMENTAL NUCLEAR MATERIALS CONTROL PLAN j

DATE:

4-22-93 PAGE: 3-8 REV.: 5 3.5.2.1 General The SEID will be calculated for.each material balance period at time of 1

inventory.

The SEID will be based on measurement uncertainties determined from inventory quantities and~ random and systematic error estimates.

Propagation of measurement errors are based primarily on the methodologies outlined in Statistical Methods in Nuclear Material Control by John L. Jaech.

SEID is further defined as:

[

SEID =

(A)

+ (B) where A = nonmeasurement variance B = measurement variance A=B, therefore

[

(B)2 SEID =

2

• s 3.5.2.2 Systematic Error Typical systematic error estimates for key measurement systems are as shown in the annex.

These systematic errors will be evaluated at the time of the annual SNM inventory or whenever otherwise l

needed.

These systematic errors will be used in the annual SEID calculation.

Calibration check data will be used as the primary data base for calculating systematic error.

Methods for determining systematic errors are primarily taken from:

Statistical Methods in Nuclear Material Control by l

John L. Jaech.

Calculation of systematic error variances may include use of data from the previous material balance period.

[

3.5.2.3 Random Errgrs Typical random error estimates for key CURRENT REVISION:

SUPERSEDES:

PAGE: 3-8 DATE:

12-01-92 REV.: 4

[

USNRC APPROVAL

REFERENCE:

k

)

. s '.

FUNDAMENTAL NUC7. EAR MATERIALS CONTROL PLAN

~

DATE:

4-22-93 PAGE: 3-9 REV.: 5

^

measurement systems are as shown in the annex.

The random errors will be evaluated at the time of the annual SNM inventory or.whenever otherwise needed.

Random errors for the %U and %U-235 analytical method (Section 3.3.2) is included in the random error calculated pellet sampling.

The random for the UO,d analytical errors for %U.

sampling an and %U-235 measurements are based on the UO sampling routinely performed for SNM 7

receipts.

If necessary, standards data may be used in determining random errors for NDA or weighing operations.

The random sampling and analytical error may be separated provided-duplicate analyses are performed on the samples.

3.6 Control Procrams For key scales and balances, a calibration check log is used to record the difference in actual s*2ptard weight from the scale indicated weight.

Th caeck on t made on scale calibration, when a scale is in use, a daily basis.

Control limits will be determined for each key measurement system used at the CNFP.

The key measurement systems at the CNFP (scales) utilize control limits (or absolute limits) set at i 1 scale division.

If these absolute limits are exceeded, the measurement system is recalibrated and items measured on the system during the time that the absolute limit was exceeded will be remeasured as necessary.

3.7 Records and Reports Required data, information, and documents generated by the Measurement Control Program shall be retained as indicated in -Chapter 8.

Examples of these are as follows:

1.

Calibration data 2.

Source data for SEID calculations 4

3.

Measurement data 4.

Standard certification data 5.

Management reviews 6.

Calibration check logs 7.

Engineering analyses and evaluation reports

}

8.

Measurement control data supplied by contractor laboratories CURRENT REVISION:

SUPERSEDES:

PAGE: 3-9 DATE:

12-01-92 REV.: 4 USNRC APPROVAL

REFERENCE:

-