ML20154M511

Forwards Confirmatory Measurement Comparisons of Spiked Liquid Samples & Criteria for Comparing Analytical Measurements as Suppl to Insp Repts 50-327/88-38 & 50-328/88-38.Comparative Results in Agreement

ML20154M511
Person / Time
Site:	Sequoyah
Issue date:	09/16/1988
From:	Mccoy F NRC OFFICE OF SPECIAL PROJECTS
To:	White S TENNESSEE VALLEY AUTHORITY
References
NUDOCS 8809290011
Download: ML20154M511 (4)

See also: IR 05000327/1988038

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SEP 161988

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Mr. S. A. White

Senior Vice President, Nuclear Power

Tennessee Valley Authority

6N 38A Lookout Place

1101 Market Street

Chattanooga, TN 37402-2801

Dear Mr. White:

SUBJECT: DOCKET NOS. 50-327 AND 50-328, CONFIRMATORY MEASUREMENT RESULTS

SUPPLEMENT TO INSPECTION REPORT NOS. 50-327/88-38 AND 50-328/88-38

As part of the NRC Confirmatory Measurements Program, spiked liquid samples

were sent on June 2, F88 to your Sequoyah facility for selected radiochemical

analyses. We are in receipt of your analytical results transmitted to us by

your letter dated August 18, 1988, and subsequent to verification of your

values as per our conversation by telephone on August 24, 1988, the following

comparison of your results to the knowr, val 's are presented in Enclosure 1 for

your information. The acceptance criteria for the comparisons are listed in

Enclosure 2.

In our review of these data all ccmparative results were in agreement. These

data should be reviewed in greater detail by cognizant staff members for any

significant trends in the data among successive years in which samples have

been analyzed by your facility.

These results and any results from previous years pertaining to these analyses

will be discussed at future NRC inspections.

Sincerely,

Frank R. McCoy, Assistant Director

for TVA Inspection Programs

TVA Projects Division

Office of Special Projects

Enclosures:

1. Confirmatory Measurement

Comparisons

2. Criteria for Comparing

Analytical Measurements

cc w/ encl: (See page 2)

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cc w/encis:

J. L. LaPoint, Acting Site Director

Sequoyah Nuclear Plant

J. A. Kirkebo, Vice President,

Nuclear Engineering

R. L. Gridley, Director

Nuclear Safety and Licensing

M. Ray, Acting Site Licensing

Manager

TVA Representative, Rockville Office

General Counsel, TVA

- State of Tennessee

G. Fisher, Chemistry Manager

D. Nix, Court Room Supervisor

bec w/encis:

J. N. Grace, RIJ

J. G. Partlow, OSP

S. D. Richardson, OSP

S. C. Black, OSP

B. D. Liaw, OSP

K. P. Barr, OSP/RII

J. B. Brady, OSP/RII

J. Rutberg, OGC

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NRC Resident Inspector

DRS Technical Assistant

- NRC Document Control Desk

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ENCLOSURE 2

CRITERIA FOR COMPARING ANALfTICAL MEASUREMENTS

This enclosure provides criter't- for comparing results of capability 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 denoting agreements of disagreement

between licensee and NRC results are variable. This variability is a function

of the NRC's value relative to its associated uncertainty, referred to in this

program as "Resolution"8 increases, the range of acceptable differences between

the NRC and licensee values should be more restrictive. Conversely, poorer

agreement between NRC and licensee values must be considered acceptable as the

resolution decreases.

For comparison purposes, a ratio * of the licensee value to the NRC value for

each individual nuclide is computed. This ratio is then evaluated for

agreemer.t based on the calculated resolution. The corresponding resolution and

calculated ratios which denote agreement are listed in Table 1 below. Values

outside of the agreement ratios for a selected nuclide are considered in

, disagreement.

2 Resolution = NRC Reference Value for a Particular Nuclide

Associated Uncerta'nty for the Value

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Comparison Ratio = Licensee Value

i NkC Reference Value

TABLE 1

Confirmatory Measurements Acceptance Criteria

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Resolutions vs. Comparison Ratio

Comparison Ratio

for

j Resolution Agreement __

<4 0.4 - 2. 5

4-7 0.5 - 2. 0

8 - 15 0.6 - 1. 66

16 - 50 0.75 - 1. 33

51 - 200 0.80 - 1. 25

>200 0.85 - 1. 18

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