IR 05000321/1986004

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Addendum to Insp Repts 50-321/86-04 & 50-366/86-04 Adding Comparison of NRC & Util Analytical Results of Tritium Analysis of Split Groundwater Samples
ML20211H191
Person / Time
Site: Hatch  Southern Nuclear icon.png
Issue date: 06/05/1986
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20211H189 List:
References
50-321-86-04, 50-321-86-4, 50-366-86-04, 50-366-86-4, NUDOCS 8606230232
Download: ML20211H191 (4)


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ADDENDUM TO INSPECTION REPORT NOS. 50-321/86-04 AND 50-366/86-04 1 Licensee Action on Previously Identified Inspector Followup Items (92701)

(Closed) IFI 50/321/86-04-06, 50-366/86-04-06, Review of Groundwater Tritium

- Analyses: As part of the NRC Confirmatory Measurements Program, 11 water samples were collected on February 12, 1986, from wells established for monitoring the potential for tritium contamination of groundwater at the licensee's Hatch facilit A comparison of results for samples split between the licensee's facility and NRC Region II was conducted for the purpose of verifying licensee measurements and as an independent measurement of tritium concentrations in the sampling wells. A comparison of licensee results and NRC results is presented in Table The acceptance criteria for the comparisons are listed in Attachment 1. The inspectors reviewed these data and determined that all comparative results were in agreement; however, in all cases, licensee results were biased low. These biases may be indicative of a programmatic weakness and attention should be given to determine the reasons for such biases. The concentrations reported were similar to data obtained previousl It should be noted that since April 1981, only one sample from well P-16 was split; therefore, no comparisons to data obtained previously could be made. Results- from the Region II laboratory analyses since 1983 confirm previous observations that the potential for exposure of the general public from releases to unrestricted areas is negligibl For tracking purposes this item is considered close PDR ADOCK 05000321 G PDR A .. . _ _ _ _

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ATTACHMENT 1 CRITERIA FOR COMPARING ANALYTICAL MEASURE:4ENTS

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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 progra In these criteria, the judgement limits denoting agreement or disagreement between licensee and NRC results are variabl " 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"2, increases, the range of acceptable differences between the NRC and licensee values is more restrictive. Converseli, poorer agreement between NRC and licensee values is considered acceptable as the resolution decrease For comparison purposes, a " Comparison Ratio"2 of the licensee value to the NRC value is computed for each individual nuclide. The comparison ratio is then evaluated for agreement based on the calculated resolution. The corresponding resolution and comparison ratios which denote agreement are listed in Table Values outside of the agreement comparison ratios for a selected nuclide are considered to be in disagreemen " Resolution = NRC Reference Value Associated Uncertainty for the Value 2 Comparison Ratio = Licensee Value NRC Reference Value

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TABLE 1 - Confirmatory Measurements Acceptance Criteria Resolutions vs. Comparison Ratio a

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Comparison Ratio for

, Resolution Agreement

<4 0.4 - .5 - .6 - 1.66 16 - 50 0.75 - 1.33 51 - 200 0.80 - 1.25

>200 0.85 - 1.18 i

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TABLE 3 RESULTS OF GROUNDWATER TRITlUM MEASUREMENTS AT $

E. 1. HATCH NUCLEAR PLANT COLLECTED ON FEBRUARY 12, 1986 Concentration (pCi/ Liter) Ratio Samole Location Licensee f(RC Resolution Licensee /NRC Compa ri son T-2 3.77 E+2 5.0011.80 E+2 3 0.75 Not compa red (1)

T-3 1.02 E+4 1.1610.02 E+4 58 0.88 Ag reement T-4 2.38 E+2 3.9511.80 E+2 2 0.21 Not compa red (1)

- T-8 1.13 E+3 1.8310.18 E+3 10 0.62 Ag reement T-12 8.34 Et3 9.0310.23 E+3 39 0.92 Ag reement T-13 3.44 E+3 4.2310.21 E+3 20 0.81 Ag reement T-16 3.75 E+2 7.2011.80 E+2 4 0.52 Ag reement-1.17 E+1 5.5011.80 E+2 3 Not compared (1)

P-15A Ag reement P-15B 1.58 E+4 1.6610.03 E+4 55 0.95 P-16 5.32 E+4 5.3510.04 E+4 134 0.99 Ag reement P-17A 4.30 E+1 6.4011.80 E+2 4 0.07 Not compa red (1)

NOTE: The associated uncertainty assigned to each NRC value represents +/- one standard deviatio . NRC/ Licensee results not compared since NRC result was less than the '

analytical lower limit of detection (LLD), tyoical NRC analytical LLD = 600 ,

pCi/ liter; Hatch Technical Specification required LLD for H-3 in water is 2000 pCi/IIte .

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