ML19338E403

Forwards Nationwide Confirmatory Measurements Program Re Radioactivity in Actual or Simulated Plant Effluent Samples for Evaluation of Facilities Performance

ML19338E403
Person / Time
Site:	Dresden, Quad Cities, Zion
Issue date:	09/01/1976
From:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	Brian Lee COMMONWEALTH EDISON CO.
References
760401, NUDOCS 8009260716
Download: ML19338E403 (8)

Text

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umreo smes NUCLEAR REGULATORY COMiWISSION REGION lit 799 ROOSEVELT RO AD GLEN ELLYN, ILLINOIS 60137 SEP' 1~

1976 Commonwealth Edison Company Dochet No. 50-10 ATEi:

Mr. Byron Lee. Jr.

Docket No. 50-237 Vice President Docket No. 50-249 P. O. Box 767 Docket No. 50-254 Chicago, T111ncis 60690 Docket No. 50-265 Docket No. 50-295 Docket No. 50-304 s

Gentlaman:

As you are aware, the NRC conducts a nationwide Confirmatory Heasurements Program at nuclear power facilities. This prograr consists of teat of 14 ranaam measuranants of radioactivity in actual or s4=n1= tad plant effluent samples, comparing the licensee's measurements to those of our NRC reference laboratory.

The measurements made by the NRC reference laboratory cre trace-able to the National Bureau of Sennelards' Radioactivity Measure-i nents System by laboratory intercomparisons.

The NRC's Office of Inspection and Enforcement has been conducting the confirmatory maamurements program with nuclear power facilities since 1973. In the past, inspectors have discussed changes in the program with your staff during the course of their confirn-atory measurements inspections. In order to update your informa-tion and assist you in evaluating your facility's performance, we have prepared the, enclosed review of our present Confirmatory Heasurements Program.

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Commonwealth Edison Company < E P' I'

'190 We consider neceptible results in this progra= to be of s1Gaificant importance, and raquest your continued cooperation. We will gindly discuss any questions concerning this matter.

Sincerely yours, James G. Keppler Regional Director

Enclosure:

Confirmatory Mecaurements Program ec w/ enc 1:

Mr. B. B. Stephenson Station Superintendent Mr. N. Kaliv4an=leia Station Superintendent Ilr. J. Bitel, Plant Superintendent bec w/ encl:

Central Files IE Files PDR Local PDR Anthony Roisman, Esq.,

Attorney i

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i CONFIRMATORY MEAS!!RDIT.NTS PROGRAM

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I.

Introduction The following information has been compiled for the information of licensees in NRC Region III to assist in developing a more uniform basis of laboratory comparisons in the conduct of the NRC Confirm-atory Measurements Program.

II.

NRC Reference Laboratory Analysis The following counting times and instrumentation are generally used by the NRC Reference Laboratory:

Media Analysis Instrumentation Count Time

• Liquid Gross Beta Proportional 20 minutes H-3 Liquic scintillation 10 minutes Sr-90, total Sr Proportional 20 minutes Gamma Spec GeLi 60 minutes Gas Gamma Spec GeLi 60 minutes Particulate Gamma Spec GeLi 60 minutes filter Charcoal Gamma Spec GeLi 60 minutes Adsorber

• or 20,000 counts.

III. ] Limits for Detectability The reported NRC reference laboratory results are reviewed to deter-mine if the results are above specific limits for detectability (LD).

Values below the LD are not used for comparison purposes.

These LD values are as follows:

1.

Licaid and Gac Specific radionuclide concentrations of 10% of their MPC in 10 CFR 20, Table 11, Column B, of more restrictive value of solubic or insoluble limit.

2.

Particulate Filter and Charcoal Adsorber Spccific radionuclide activity present on filter (pCi/ sample) at the following levels:

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LD Isotope Ly l

-0

-5 Cr-51 1

x 10 Mo-99 1.0

-5

~0 Hn-54 1.5 x 10 I-131 2 x 10

-5

-5 Co-57 2

x 10 Cs-134 2 x 10

-5

-5 Co-58 1.5 x 10 Cs-137 2 x 10

-5

-5 Co-60 3

x 10 Ba-14 0 2 x 10

-5

-5 Fe-59 3

x 10 La-140 4 x 10

-5

-5

'n-65 3

x 10 Ce-141 2 x 10

-5

-0 Sr-89 1

x 10 Cc-144 1 x 10

-6

-5 Sr-90 2

x 10 ZrNb-95 4 x 10 IV.

Decay Correction NRC reference labo; story samples are counted approximately ten (10) days from sample collection.

Gross beta analysis is performed by both licensee and NRC reference laboratory on liquid samples at a pre-specified date approximately three (3) weeks from sample collection.

Gas samples should be retained by licensees for recounting tuo (2) to six (6) days after sample collection.

Experience has shown that Xe-135 vill mask Xe-133m and Kr-85 identification and quantification.

La-140 is presently not decay corrected to time of sampling by the NRC reference laboratory.

Comparisons with La-140 are presently made for information purposes only.

1 V.

Acceptance Criteria

" Criteria for Comparing Analytical Measurements" is utilized to determine whether results are in the agreement, dis-agreement, possible agreement, or no comparison category.

For all NRC reference laboratory results above the LD, comparisons which are in ' agreement' or 'possible agreement' are considered accept-able, while 'disagrcement' or 'not reported by licensee' are cor -

sidered unacceptable.

VI.

Reporting of Results Results from the licensee's analytical measurements are te be received by NRC IE:1Il within 45 days of sample collection.

VII. Reports Information on the NRC reference labor'atory's and licensee's results are analyzed by the NRC Computer Data Analysis System. The com-pleted report, example in Table I, is submitted to the licensee by l

the inspector during the exit interview of the Confirmatory Measure-ments Inspection.

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A's seca in Table I, results arc provided for each sampic by isotope.

The respective parameters are:

1.

NRC reference laboratory result and error (uncertainty).

2.

Licensec' rcsult and error- (uncertainty).

3.

NRC and Licensee results and errors arc reported in units of:

pCi/cc for gas samples pCi/ml for liquid samples pCi/ sample for particulate filters and charcoal adsorbers 4.

Z Value This parameter was utilized in 1973 as part of the statistical comparison test criteria.

The Z value is included for those licensees desiring additional statistical information about the reported values.

'L Z value = (X) - X )/(c2+U )

2 l

where X = NRC value 7

X = Licensee value 2

0 = NRC error 7

c = Licensee error 2

5.

PCT The percentage parameter was utilized in 1973 as part of the statistical comparison test criteria.

Percentage (PCT) is included for those licensees desiring additional statistical information.

PCT = (100) (X

-X) 1 2

1 6.

RAT The ratio (RAT) is defined in Attachment 1 as:

RAT = X /

2 1

7.

RES The resolution (RE9 is defined in Attachment I ac:

RES = X /0 y

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T The test result (T) is defined in Tabic 1.as:

A = Agreement P = Possible Agreement N = No Comparison D = Disagreement Attachments:

1. Attachment 1, Criteria for Comparing Analytical Measurements

2. Table 1, Confirmatory Measurements Program o

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t ATTACllMENT 1 CRITERIA FOR CO:lpARING ANALYTICAL MCASUREMENTS i

This attachment provides cr.tteria for comparing results of capability

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tests and verification measurements. - The criteria are based on an empirical relationship which combines prior experience and the accuracy needs of this program.

In these criteria, the judgment limits are variable in relation to the comparison of the NRC Reference Laboratory's value to its associated one sigma uncertainty. As that ratio, referred to in this program as

" Resolution", increases, the acceptability of a licensce's measurement should be more selective.

Conversely, poorer agreement should be con-sidered acceptable as the resolution decreases.

The values in the ratio criteria may be rounded to fewer significant figures to maintain statistical consistency with the number of significant figures reported by the NRC Reference Laboratory, unless such rounding will result in a narrowed category of acceptance.

The acceptance caterory reported will be the narrowest into which the ratio fits for the resolution being used.

RESOLUTION RATIO = LICENSEE VALUE/NRC REFERENCE VALUE Possible Possible Agreement Agreement "A" Agreement "B"

<3 No Comparison No Comparison No Comparison

>3 and <4 0.4 2.5 0.3 -

3. 0 No Comparison 2,4 and <8 0.5 2.0 0.4 2.5 0.3

3. 0 2,8 and <16 0.6 -

1.67 0.5 -

2.0 0.4

- 2.5 2.16 and <50 0.75 -

1.33 0.6 -

1.67 0.5

. 2. 0

>50 and <200 0.80 - 1.25 0.75 -

1.33 0.6 -

1.67

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[200 0.85 -

1.18 0.80 -

1.25 0.75 -

1.33 "A" criteria are applied to the following analyses:

Gacma spectrometry, where principal gamma energy used for identift, cation is greater than 250 kev.

Tritium analyses of liquid samples.

"B" criteria are applied to the following analyses:

Gamma spectrometry, where principal gamma energy used for identifi-cation is less than 250 kev.

Sr-89 and Sr-90 determinations.

Gross beta, where samples are counted on the same date using the same reference nuclide.

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