ML20212N899

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Forwards Confirmatory Measurements Results & Acceptance Criteria from 860707 Submittal of Selected Radiochemical Analyses & 860715 Telcon Verification.All Results Re Analyses Will Be Discussed in Future Insps
ML20212N899
Person / Time
Site: Summer 
Issue date: 08/18/1986
From: Verrelli D
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To: Nauman D
SOUTH CAROLINA ELECTRIC & GAS CO.
References
NUDOCS 8609020030
Download: ML20212N899 (4)


Text

w~so AUG 181986 outh Carolina Electric and Gas Company ATTN: Mr. D. A. Nauman, Vice President Nuclear Operations P. O. Box 764 (167)

Columbia, SC 29218 Gentlemen:

SUBJECT:

DOCKET NO. 50-395, CONFIRMATORY MEASUREMENTS RESULTS s

As part of the NRC Confirmatory Measurements Program, spiked liquid samples were sent on May 8,1986, to your facility for selected radiochemical analyses. We are in receipt of your analytical results transmitted to us by your letter dated July 7, 1986, and subsequent to verification of your values as per our conversation by telephone on July 15, 1986, the following comparison of your results to the known values are presented in Enclosure 1 for your information.

The acceptance criteria for the comparisons are listed in Enclosure 2.

In our review of_the data comparative results wete in agreement for Sr-89, Sr-90 and Fe-55 analyses and initial disagreement for H-3.

Reanalysis for H-3 showed agreement but the initial disagreement may be indicative of a programmatic weakness and therefore your attention is directed to determining the underlying cause for this disagreement. Furthermore, all data should be reviewed in greater detail by cognizant staff members for 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, 1

David M. Verrelli, Chief Reactor Projects Branch 2 Division of Reactor Projects

Enclosures:

1.

Confirmatory Measurement Comparisons

)

2.

Criteria for Comparing Analytical Measurements cc w/encls:

(See page 2) 8609020030 86081s DR ADOCK 05000395 PDR 1 &

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South Carolina Electric and Gas Company 2

./ccw/encls:

0. S. Bradham, Director, Nuclear Plant Operations

./J.L.Skolds,DeputyDirector

Operations and Maintenance VJ. B. Knotts, Jr.

Debevoise and Liberman JW. A. Williams, Jr., Special Assistant, Nuclear Operations -

f Santee Cooper 4 A. M. Paglia, Jr., Manager Nuclear Licensing

'bec w/encis:

  • NRC Resident Inspector jJ.Hopkins,ProjectManager,NRR Document Control Desk State of South Carolina RII[

RII RII RII RII SAdamovitz PStoddartDCo)li#s LMo ros Huance 8/ti/86 8/d/86 8/g86 8/[ 86 8/s[/86

ENCLOSURE 1 CONFIRMATORY MEASUREMENT COMPARISONS OF H-3, SR-89, SR-90, AND FE-55 ANALYSES FOR SUMMER NUCLEAR PLANT, MAY 8, 1936 isotope Licetsee NRC Resolution Ratio Compa ri son (uCi/ unit)

(uCl/ unit)

( Licensee /NRC )

H-3 3.64 E-5 1.7410.03 E-5 58 2.09 D i sag reement

  • 1.83 E-5 1.05 Ag reement Fe-55 1.18 E-5 1.2910.03 E-5 43 0.91 Ag reement Sr-89 2.34 E-5 2.1910.06 E-5 36 1.07 Ag reement Sr-90 2.38 E-6 2.0710.08 E-6 26 1.15 Ag reemen t
  • Results of reana lysis for H-3

[

ENCLOSURE 2 CRITERIA FOR COMPARING ANALYTICAL MEASUREMENTS This enclosure.provides criteria 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 judgement limits denoting agreement or disagreement between licensee and NRC results are variable. This variability is a function of the NRC's value relative to its associated uncertainty. As the ratio of the NRC value to its associated uncertainty, referred to in this program as " Resolution"*

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 2 of the licensee value to the NRC value for each individual nuclide is computed. This ratio is then evaluated for agreement 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.

NRC Reference Value for a Particular Nuclide 2 Resolution =

Associated Uncertainty for the Value Licensee Value 2 Comparison Ratio = NRC Reference Value TABLE 1 - Confirmatory Measurements Acceptance Criteria Resolutions vs. Comparison Ratio Comparison Ratio for Resolution Agreement t

<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

.-