ML20246P282

Forwards Confirmatory Measurement Comparisons of H-3,Fe-55, Sr-89 & Sr-90 Analyses for Plant on 890109

ML20246P282
Person / Time
Site:	Brunswick
Issue date:	05/01/1989
From:	Dan Collins NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	Eury L CAROLINA POWER & LIGHT CO.
References
NUDOCS 8905220138
Download: ML20246P282 (3)

Text

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MAY 011989-L F .

Carolina Power and. Light Company j

• l ATTN: Mr. Lynn W. Eury

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. Executive-Vice President ,

Power Supply J

.P. O. Box 1551 h.. Raleigh,- NC 27602 Gentlemen:. ]

1

SUBJECT:

DOCKET N0s. 50-325 AND 50-324, CONFIRMATORY MEASUREMENT RESULTS, d '

. SUPPLEMENT T0 NRC INSPECTION REPORT NO. 88-44

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

were sent on . January 9, .1989,. to your Brunswick facility for . selected radiochemical. analyses. We. are in receipt of your analytical results transmitted to us by your letter dated March 8, 1989, and . subsequent - to verification of your . values' as per our. conversation by telephone .on March 28, 1989, 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. these data all comparative 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

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will be discussed at future NRC inspections.

. Sincerely, 4;ifit. sci Qned IkJ IkilCdks Douglas M. Collins, Chief

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Emergency Preparedness and Radiological Protection Branch Division of Radiation Safety and Safeguards i

Enclosures:

1. Confirmatory Measurement j Comparisons

2. Criteria for Comparing Analytical Measurements p

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R. B. .Starkey, Jr. , Manager Brunswick Nuclear Project J. L. Harness, Plant General Manager State of North Carolina l 1

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e s 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 comparison ratio 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, referred to in this program as " Resolution"1 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 the Table below. Values outside of the agreement ratios for a selected nuclide are considered in disagreement.

1 Resolution = NRC Reference Value for a Particular Nuclide Associated Uncertainty for the Value 2 Comparison Ratio = Licensee Value NRC Reference Value TABLE Confirmatory Measurements Acceptance Criteria Resolutions vs. Comparison Ratio Comparison Ratio for Resolution Agreement j i

<4 0.4 - 2.5 1 4-7 0.5 - 0.2 8 - 15 0.6 - 1.66 16 - 50 0.75 - 1.33 .

51 - 200 0.80 - 1.25 1

>200 0.85 - 1.18

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