IR 05000324/1986027
| ML20210D371 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 01/29/1987 |
| From: | Reyes L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Utley E CAROLINA POWER & LIGHT CO. |
| References | |
| NUDOCS 8702100072 | |
| Download: ML20210D371 (4) | |
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JAN 2 91987
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Cprolina Power and Light Company MTTN: Mr. E. E. Utley Senior Executive Vice President Power Supply and Engineering and Construction P. O. Box 1551
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Raleigh, NC 27602 Gentlemen:
SUBJECT: DOCKET NOS. 50-325 AND 50-324, CONFIRMATORY MEASUREMENT RESULTS SUPPLEMENT TO INSPECTION REPORT NOS. 50-325/86-26 AND 50-324/86-27 As part of the NRC Confirmatory Measurements Program, spiked liquid samples were sent on September 22, 1986, to your Brunswick facility for selected radiochemical analyses. We are in receipt of your analytical results transmitted to us by your letter dated November 20, 1986.
Results were verified based on a telephone conversation on January 5, 1987.
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 were in agreement for H-3, Sr-90, and Fe-55 analyses and disagreement for the Sr-89 analysis.
This 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 analyses.
These results and any results from previous years pertaining to these analyses will be discussed at future NRC inspections.
Sincerely, Original Signed by Luis A. Reyes Luis A. Reyes, Acting Director Division of Reactor Projects
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Enclosures:
1.
Confirmatory Measurement Comparisons 2.
Criteria for Comparing Analytical Measurements cc w/encls:
(See page 2)
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8702100072 870129 PDR ADOCK 05000324 Q
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Carolina Power'and Light Company
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LP. W. Howe, Vice President Brunswick Nuclear. Project 9 '. R. Dietz, P.lant General Manager
NT G. Cheatham, Manager, E&RC
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gNRC Resident Inspector Document Control Desk State of North Carolina
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e ENCLOSURE 1 CONFIRMATORY MEASUREMENT COMPARISONS OF H-3, FE-55, SR-8, AND SR-90 ANALYSES FOR BRUNSWICK NUCLEAR PLANT ON NOVEMBER 20 1986 Licensee NRC Ratio factane fuci/ml)
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Resolution f licertsee/NRC )
Compa ri son D-3 3.41 E-5 3.50 1 0.07 E-5
0.97 Ag reement FA-55 2.59 E-5 2.60 1 0.05 E-5
1.00 Ag reement tr-19 8.42 E-5 4.41 1 0.13 E-5
1.91 Di sag reement S r-90 3.32 E-6 4.17 1 0.17 E-6
0.80 Ag reement
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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, referred to in tnis program as " Resolution"2 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 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.
2 Resolution = NRC Reference Value for a Particular Nuclide Associated Uncertainty for the Value 2 Comparison Ratio =
Licensee Value NRC Reference Value TABLE 1
Confirmatory Measurements Acceptance Criteria Resolutions vs. Comparison Ratio Comparison Ratio for 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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