IR 05000206/1981006
| ML19350D504 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 03/20/1981 |
| From: | Book H, Hamada G, Wenslawski F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML19350D503 | List: |
| References | |
| 50-206-81-06, 50-206-81-6, NUDOCS 8104160053 | |
| Download: ML19350D504 (7) | |
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S.' NUCLMR REGUMTORY CCIOiISSION O OFFICE OF I!!SPECTIO!! A!!D EliFORCEME!TI
REGION V
Raport No.
50-206/81-06 - Do'cket No.
50-206 License No.
DPR-13 Safeguards croup Licensee: Southern California Edison Company 2244 Walnut Grove Avenue Rosemead, California 91770 Facility Na=e: San Onofre Unit 1 Inspection at: Camo Pendleton, California Inspection conducted: February 9-12, 1981 3 l26lf) Inspectors: n., tv-ct . H. ' amada, Ra f ation aboratory Specialist D' ate Signed . 3bs/7/ ~ ' ' Approved By: totw o F. Wenslawski, Chief, Reactor Radiation Protection Section Da(e Signed . Date Signed k 3 2'D [c$l - Approved By: H. E. Book, Chief, Radiological Safety Branch Date Signed S uc=a ry : , _.
Inspection of February 9-12, 1981 Report No. 50-206/81-06 , ,, Areas Inspected: Routine announced inspection of laboratory quality control program including independent confirmatory measurements using the Region V . mobilelaboratory. The inspection involved a total of 48 hours onsite by . -i one inspector and one radiation laboratory technician.
. Results: No items of noncompliance or deviations were identified in the areas inspected.
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_ _ _ _ _ _ _ _ _ _ _ _ _ _ , . DETAILS 1.
Persons Contacted
- R. Brunet, Superintendent, Unit 1
- J. D. Dunn, Project QA Supervisor
- W. G. Frick, Compliance Engineer
- J. G. Haynes, Manager of Nuclear Operations
- J. Heflin, Chemical Foreman
- B. Katz, Supervising Engineer
- G. W. Mcdonald, QA/QC Supervisor G. D. Peckham, Assistant Chemical Radiation Protection Engineer
- R. W. Rutland, QA
- M. K. Sullivan, Supervisor, Plant Chemistry
- Indicates those present at the exit interview.
2.
Peasurerents and Intercomoarison of Data Intercomparison measurements for gama ray emitting radionuclides were made with the Region V Mobile Laboratory measurement system. This system consists of a ND-6600 computer based multichannel analyzer array (with associated Nuclear Data (ND) software) coupled to an intrinsic germanium detector setup.
Samples of gaseous and liquid effluents were obtained for measurement by both Southern California Edison (SCE) and NRC. The gaseous samples were obtained from the south CVI bank, a tank containing gaseous waste in series a 1 liter Marinelli container (ples were obtained by connecting from the cryogenic treatment system. SamNRC), a 190 ml glass cylinder (SCE), a 33 ml glass bulb (NRC), and a 32.6 al glass bulb (SCE). This train was flushed for approximately 5 minutes before collecting the samples.
Because of the relatively long decay time for this sample, the only significant activity detected was Kr-85. The results are given in Table 1.
Table 1 Gaseous Effluent - South CVI Bank NRC SCE Det.#1 SCE Det.#3 Samole Nuclide pCi/ml AC1/ml stCi/ml s 33 ml Bulb (NRC) Kr-85 2.06x10-2 , , 1.84x10-2 2.15x10-2 2.01x10-2 " 32.6 ml Bulb (SCE) 2.10x10-2 2.73x10-2 2.54x10-2 " 190 ml Cylinder (SCE) 2.33x10-2 -" 1 L Marinelli - - (NRC) -- - _ _ - - - - - _ _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
l . . -2-The above table shows that the agreement between NRC and Southern California Edison (SCE) is adequate. This conclusion is based on the fact that all ratios are within the acceptable range of 0.6-1.66, where the ratio is the licensee value divided by the !!RC value (see attachment, " Criteria for Comparing Analytical l'easurerents"). The resolution range of 8-15 (see attachrent) was used because Region V experience to date with the mobil reasurement system indicates a total estirated uncertainty of 10 percent. While the random counting error is relatively small, other errors, particularly those associated with systematic effects, can be much more significant. Until such tire as Region V is able to better quantify all of the error components, the 10 percent error esticate will be applied and thus also the 8-15 range for resolution.
A liquid effluent sample was obtained while a release was in progress.
This sarole represented low level reactor coolant letdown plus a mixture of miscellaneous drain waters. The ganna measurement results are tabulated in Table 2.
An aliquot of this sample was obtained for shipment to the Radiological and Environmental Sciences Laboratory (RESL) of the Department of Energy for tritium, gross beta, and SR-89, SR-90 analyses.
Results of these corparisons will be reported in a subsequent inspection report (81-06-01).
Table 2 Liquid Effluent - Holdup Tank C SCE NRC NRC Nuclide 100 ml-@ci/ml) 150 ml- @Ci/ml) 50 ml,(FCi/ml) Co-57 2.64 x 10-6 2.52 x 10-6 1.97 x 10-6
2.74 x 10-5 Ce-144 3.08 x 10-5 3.00 x 10 5 2.05 x 10-5 Cs-134 2.23 x 10-5 1.94 x 10-Ag-110M 2.94 x 10-5 2.65 x 10-5 2.36 x 10-5 Cs-137 1.94 x 10 5 2.87 x 10-5 2.85 x 10-5
- 2.59 x 10 4 Co-58 1.03 x 10 5 1.02 x 10-4 1.00 x 10-4
5 Mn-54 4.36 x 10 4 4.65 x 10 4 4.36 x 10 4 Co-60 7.49 x 10-7.20 x 10-6.99 x 10-
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. . -3-It can be seen that the measurements for the liquid effluent samples agree well within the acceptable range of ratios, where r = 0.6-1.66.
Three other samples were obtained for comparative measurements; but unlike the gaseous and liquid effluent samples, which were split for analysis, the same sample from each of the three types were measured by both SCE and NRC. Two of these samples, a particulate filter and charcoal cartridge, were obtained from the plant stack. Neither NRC nor SCE was able to detect any significant activity for either sample.
The third sample was a particulate filter obtained from steam generator B channel head. The results are presented in Table 3.
Table 3 Particulate Filter - Steam Generator B Channel Head SCE NRC Nuclide_ jfCi/ml ACi/ml Mn-54 1.20 x 10-9 1.05 x 10-9
Co-57 1.74 x 10-11 1.28 x 10 10
Co-58 5.69 x 10 9 5.03 x 10 9 Co-60 6.49 x 10-5.75 x 10- , All of the comparative measurements again fall.in the acceptable ratio ' range for agreement.
Because the charcoal cartridge sample contained no measurable activity which could be compared, SCE was asked to analyze NRC's charcoal cartridge calibration standard using SCE's current calibration parameters.
In Table 4, SCE's results are compared against the reference values provided by RESL for this calibration standard.
l Table 4 l l NRC Charcoal Cartridge (Homoaeneous) Calibration Standard , RESL SCE-Det. #3 SCE-Det. #1 l Nuclide JtCi ACi /ICi , Am-241 3.28 x 10-2 2.36 x 10-2 2.76 x 10-2 Co-57 2.33 x 10-2 2.10 x 10 2 2.02 x 10-2 Sn-113 5.91 x 10 2 5.09 x 10-2 4.83 x 10-2 Sr-85 7.91 x 10-2 6.29 x 10-2 5.40 x 10-2 Cs-137 1.31 x 10-1 1.18 x 10-1 1.11 x 10-1 Y-88 3.00 x 10-1 2.52 x 10-1 2.47 x 10-1 Co-60 1.77 x 10-1 1.55 x 10-I 1.54 x 10-1 , , e .- - -- ,. - ., - , - - - - - - -
. . -4-The data in Table 4 were decay corrected to March 19, 1980, the reference date for this working standard. The interval between the reference date and measurement date was long enough to cause a significant reduction in the activities of some of the shorter lived nuclides.
For Sr-85 this interval came to more than 5 half lives, resulting in a 32 fold decrease in its activity.
Despite relatively poor counting statistics for the shorter lived nuclides, all of the results in Table 4 are within the acceptability criterion for agreement.
3.
Review of Quality Control Procedures and Practices Procedures involving quality control in sampling and measurement were reviewed. Although SCE does have written procedures which address these operations, it was pointed out that these procedures might be upgraded to better conform with the provisions described in Regulatory Guide 4.15, " Quality Assurance for Radiological Monitoring Programs (Normal Operations) - Effluent streams and the Environment." In particular, it was mentioned that the procedures should include an internal audit function for assessing the adequacy of actual practice as measured against stated policy.
Another area reviewed concerned SCE's method for calculating lower limits of detection for various radionuclides and the ability of the Unit I laboratory to conform with guidelines established for lower limits of detection for key radionuclides. While Unit 1 is not required specifically to conform with criteria for lower limits of detection specified in standard technical specification guidelines (flUREG-0472, " Radiological Effluent Technical Specifications for PWR's), it would be desirable to establish procedures for complying with these, guidelines.
In some cases, this is already being accomplished; e.g., particulate samples.
In most cases where these criteria are not now being met, relatively minor changes in counting procedures will bring the measurements into conformance with the guidelines. This will make lower limit of detection criteria for Unit 1 compatible with those for Unit 2 when Unit 2 becomes operational. This matter was brought to the licensee's attention during the exit interview.
No items of noncompliance were identified in the areas examined.
4.
Exit Interview Inspection findings were discussed with SCE personnel referenced in Paragraph 1.
The licensee was informed of the agreement between SCE and NRC on measurements performed on various intercomparison samples.
It was also mentioned that certain procedures needed to be upgraded, particularly those involving sampling; and that it would be desirable to include an internal audit requirement in the procedures. The desirability to have Unit I conform with lower limit of detection criteria specified in NUREG-0472 was also discussed.
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ATTACF2'E'.T , - CRITERIA FOR COMPARI'iG A' ALYTICAL YJ.ASU?ll'I'.TS . '( t. ICE';SEE VALUE ) ~~ RATIO (ARC EEFFJr:cE VALUE) . _. .g g . Pcssible Possible ' " " ' , Resolution Agree =ent Agree ent A Agree e-: 3 <- 3 0.4 - 2.5 0.3 - 3.0 No Cc :parisen 4-7 0.5 - 2.0 0,4 - 2.5 0.3 - 3.0 8.- 15 0.6 - 1.66 0.5 - 2.0 0.4 - 2.5 16 - 50 0.75 - 1.33 0.6 - 1.66 0.5 - 2.0 51 - 200 0.80 - 1.25 0.75 - 1.33 0.6 - 1.66 >200 . 0.85 - 1.18 0.80 - 1.25 0.75 - 1.33 . "A" criteria are applied to the folleving analyses: Ca==a Spectrc etry where principal g=-a energy used for identificatica is greater than 250 Kev.
$N$ Tririu= analyses of liquid sa=ples.
Iodine en adscrbers.
"B" criteria are applied to the folicving analyses: Ca==a spectrc=etry where principal gn-' energy used for . identificatica is less than 250 Kev.
'Sr and 9 Sr deter =icaticas.
Gross Beta where sa=ples are counted en the sa=e date using the sa=e reference nuclide.
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The NRC Reference Laboratory value should be divided by its e r:; associated uncertainty (10) to obtain the resolution.
b.
The ratio of the two measure =ents to be compared should be
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- determined by dividing the result to be compared by the AEC ' N= s$ Reference Laboratory result.
- c.
Agreement is considered obtained if the ratio falls within the range given in the " Agreement" colu=n for the agociated resolution. For exa=ple, consider a co=parison of Sr-5 deter =inations. A licensee obtains a value of 1.97 +.08 x 10 uCi/ml and the NRC Reference Laboratory reports a result of ' 2.53 +.06 x 10~ uCi/ml. The resolution would be 42 (2.53/.06) and the ratio is 0.78 (1.97/2.53). This pair of measurements would be considered to be in " agree =ent" because for this resolution, the " agreement" range is 0.75 - 1.33.
d.
If " agreement" is not achieved, the ratio should be evaluated for "possible agreement." In this case, consideration is cade for the type of z.nalyses conducted by selecting a range in the appropriate column; i.e., "A" analyses or "B" analyses, e.
If the ratio falls outside the appropriate "possible agree =ent" colunn, the two measure =ents will be considered to be in " disagreement."
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