ML20197A846
| ML20197A846 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 10/16/1986 |
| From: | Walker R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Kingsley O MISSISSIPPI POWER & LIGHT CO. |
| References | |
| NUDOCS 8610270406 | |
| Download: ML20197A846 (4) | |
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00T 161986 Mississippi Power and Light Company ATTN: Mr. O. D. Kingsley, Jr.
Vice President, Nuclear Operations P. O. Box 23054 Jackson, MS 39205 Gentlemen:
SUBJECT:
DOCKET N0. 50-416, CONFIRMATORY MEASUREMENTS RESULTS 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 received your analytical results as transmitted by your letter dated July 8, 1986.
Preliminary results were discussed with members of your staff by telephone on August 25, 1986. The final comparison of your results to the known values are presented in Enclosure 1 for your information and review.
The acceptance criteria for the comparisons are listed in Enclosure 2.
In our review of the data, comparative results were in agreement for Sr-89, Sr-90 and Fe-55 analyses and disagreement for tritium.
This disagreement may be
' indicative of a programatic weakness and therefore your attention is directed to determining the underlying cause for this disagreement.
Futhermore, 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 reviewed during future NRC inspections.
Sincerely, Original Signed by Luis A. Reyes /for Roger D. Walker, 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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cc w/encls:
T. H. Cloninger, Vice President, Nuclear Engineering and Support J. E. Cross, GGNS Site Director C. R. Hutchinson, GGNS General Manager L. F. Dale, Director, Nuclear Licensing and Safety R. T. Lally, Manager of Quality Assurance Middle South Services, Inc.
R. B. McGehee, Esquire Wise, Carter, Child, Steen and Caraway N. S. Reynolds, Esquire Bishop, Liberman, Cook, Purcell
& Reynolds R. W. Jackson, Project Engineer G. O. Smith, Plant Chemist J. Lassetter, Count Room Specialist bec w/encls:
NRC Resident Inspector Document Control Desk State of Mississippi i
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ENCLOSURE 1 CONFIRMATORY MEASUREMENT COMPARISONS OF H-3, FE-55, SR-89, AND SR-90 ANALYSIS FOR GRAND GULF NUCLEAR PLANT ON MAY 5, 1986 Iosotope Licensee NRC Resolution Ratio Comparison (uCi/ unit)
(uC1/ unit)
(Licensee /NRC)
H-3 1.16 E-4 1.69.03 E-5 56 6.86 Disagreement Fe-55 1.65 E-5 1.25.03 E-5 42 1.32 Agreement Sr-89 2.22 E-5 2.12.06 E-5 35 1.05 Agreement Sr-90 2.22 E-6 2.01.08 E-6 25 1.10 Agreement
c ENCLOSURE 2 CRITERIA FOR COMPARING ANALYTICAL MEASUREMENTS This attachment 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 are variable in relation to the comparison of the NRC's value to its associated uncertainty.
As that ratio, referred to in this program as " Resolution," increases, the acceptability of a licensee's measurement should be more selective.
Conversely, poorer agreement must be considered acceptable as the resolution decreases.
RATIO = LICENSEE VALUE NRC REFERENCE VALUE 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