IR 05000361/1982005
| ML20052H980 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 04/27/1982 |
| From: | Book H, Hamada G, Temple G, Wenslawski F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20052H973 | List: |
| References | |
| 50-361-82-05, 50-361-82-5, NUDOCS 8205240271 | |
| Download: ML20052H980 (8) | |
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i U. S. flVCLEAR REGULATORY COMMISSION
0FFICE OF INSPECTION AND ENFORCEf1ENT REGI0f! V
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Report No. 361/82-05 i
Docket No. 50-361 License it f1PF-10 Safeguards Group i
Licensee: Southern California Edison Company
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2244 Walnut Grove Avenue
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Rosemead, California 91770 Facility Name: San Onofre Unit 2 Inspection at:
Camp Pendleton, California
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Inspection conducted: January 25 - February 26, 1982 Inspectors:
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G. H. Hamada, Radiation Laboratory Specialist Date Signed t T N a m BO.0 ;
Odb-82 G.'ti. Tempre, Radidtion Technician (Instrumentation)
Date Signed
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Approved by:
b h Qtd p 4-28-82.
F. Hensl6]s i, Chief, Rea t' r Radiation Protection Date Signed l
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Approved by: /
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Mi. E. Book, Chief, Radiological Safety Branch
/Daff Signed.
Summary:
Inspection of January 25 - February 26, 1982, P.eport No. 50-361/82-05 Areas Inspected: Routine announced inspection of laboratory quality control program and capability test for performi_ng radioactivity measurements. The second phase involved the Region V Mobile Laboratory. The inspection effort consisted of a total of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> onsite by one inspector and one radiation technician.
Results: No items of noncompliance or deviations were identified in the areas inspected.
8205240271 820427 PDR ADOCK 05000361
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DETAILS 1.
Persons Contacted
- F. Briggs, Compliance Engineer
- S. Check, Chemistry
- W. Frick, Supervisor, Plant Chemistry
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- E. Gault, Compliance Engineer
- B. Katz, Station Technical Manager
- T. Mackey Jr., Licensing
- M. Speer, Compliance Engineer
- J. Young, Engineer II
- Indicates those present at exit interview.
2.
Introduction This report covers two closely related inspection efforts. A short inspection was conducted on January 25-26, 1982 to assess the status of chemistry and radiochemistry laboratory operations at Unit 2.
This was followed by an inspection involvino the Region 5 mobile laboratory during which direct measurement e mparisons were made using check soruces, test solutions and calibretion standards. This latter effort was conducted on February 22-26, 1982.
3.
Discussion of Inspection'Results a.
Inspection of January 25-26, 1982 The objective here was to evaluate the relative readiness of the laboratories to perform required measurements from the standpoints of adequacy of facility, equipment, procedures and personnel.
It was found that while substantial progress had been made since the previous inspection, the laboratory was not yet fully prepared to fulfill all of the anticipated analytical requirements. For example, the gamma spectroscopy system had not yet been calibrated for all of the geometries it was expected to measure, nor were all of the required procedures fully developed and approved for use. The system for measuring tritium in containment air and the procedure for operating this system had not been completed.
Calibrations for the liquid scintillation counter as well as the proportional counter were incomplete.
Also, a clear plan for the' implementation of the lower limit
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of detection (LLD) criteria had not yet been developed. On the other hand systems and procedures for doing nonradiological assays appeared to be in a. fully operational mode.
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-2-This' inspection was concluded with the understanding that when the Unit 2 radiochemistry laboratory arrived at a point where
'the necessary measurement comparisons could be performed with the NRC, the Regicn 5 mobile laboratory would be brought on site
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i to directly test for the adequacy of the various calibration parameters obtained by So'uthern California Edison (SCE).
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Inspection of February 22-26, 1932
.The Region 5 mobile laboratory was brought to the San Onofre site to perform tests and measurement comparisons with the Unit 2 laboratory during the week'of February 22-26, 1982.
Earlier,
arrangements = had been made with NRC's contractor laboratory (RESL - Radiological and Environmental Sciences Laboratory of
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the Department of Energy Idaho Falls) to provide the Unit 2 laboratory with a test solution for analysis. A portion of this test solution containing those nuclides normally contracted out for analysis was shipped.to Evironmental Analysis Laboratory (EAL - a contractor laboratory) for measurement.
The remaining fraction was analyzed by SCE. The results are tabulated below.
l TABLE 1 Nuclide uCi/ml
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SCE (Unit 2)
Ratio Agreement Standard (RESL)
uCi/ml SCE/STD Range Co-57 2.03 + 0.05 E-4 2.~02 E-4 1.00 0.75 - 1.33
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Cs-137 2.60 T 0.07 E-4 2.67 E-4 1.03 0.75 - 1.33
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Zr-95 2.49 T 0.07 E-5 2.32 E-5 0.93 0.75 - 1.33 Nb-95 5.41 T 0.15 E-5 5.49 E-5 1.01 0.75 - 1.33 Mn-54 2.81 T 0.07 E-3 2.81 E-3 1.00'
O.75 - 1.33 Zm-65 4.89 I 0.15 E-4 4.81 E-4 0.98 0.75 - 1.33 i
Co-60 4.09 T 0.10 E-4 4.30 E-4 1.05 0.75 - 1.33 H-3 6.80 T 0.06 E-3 6.22 E-3 0. 91 0.80 - 1.25
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Am-243.
2.34 T 0.05 E-6 2.20 E-6 0.94 0.75 - 1.33 Fe-55 1.08 -- 0.03 E-4 9.70 E-5*
0.90 0.75 - 1.33 S R-89 4.72 7 0.19 E-3 4.60 E-3*
0.97 0.75 - 1.33 S R-90 5.92 T 0.24 E-4 5.60 E-4*
0.95 0.75 - 1.33
- Analyzed by EAL The agreement, especially for those nuclides analyzed by gamma spectrometry (Co-57 through~ Co-60 in the table) is very good.
Agreement for the other nuclides is also quite good when credit is given for the considerable wet chemistry in'volved in the analysis of Sr-89, Sr-90 'and Fe-55, the distillation procedures required for.H-3 analysis, and the sample preparation procedures required for Am-243 analysis by alpha counting.
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The results of the other comparisons are t'abulated below.
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TABLE 2
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10 ML Liquid Scintillation Vial Geometry
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Reference (RESL)
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'SCE1-Value Ratio
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IAgreement f m.,e NuclIde-
_uCi /ml uCi/ml SCE/Ref Range
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Co-60 f*3 -8.79 E-3 9.13 E-3 0. %
0.80 - 1.25
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O.80 - 1.25 Y-88 1.84~E-2 1.84 E-2 1.00
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C3-139/,
2.10 E-3 2.35 E-3 O.89 0.80 - 1.25
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Co;57, 1.81 E-3 1.87 E-3
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0.97 0.80 - 1.25
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Cs-13/
7.74 E-3 7.84 E-3 0.99 0.80 - 1.25
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C<i-109 4.26 E-2 4.82 E-2 0.88 O.80 - 1.25
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TABLE 3-e
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d 1 LiIer Marinelli Beaker Geoinetry
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Reference
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Value Ratio'
Agreement
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Muelide.
.uCi" uCi SCE/Ref Range Cd-109 1.08 E-0 1.16 E-0 0.93'
O.80 - 1.25 i
0 M - 1.25 Co-57 6.12 E-2 5.89 E-2 1.04 Ce-139 7.76 E-2 7.27 E-2 1.07 J 0 - 1.25-l Hg-203 3.77 E-1 3.44 E-1 1.10
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0.80 - 1.25 Sn-lT3'
3.43 E-1.
2.77 E-1 1.24 0.80 - 1.25
i Sr-85
.4.48 E-1 4.36 E-1 1.03, 0.80 - 1.25 Cs-137 1.89 E-1 1.79 E-1 1.06 0.80 - 1.25 Co-60 2.07 E-1 2.06 E-1 1.00 0.80 - 1.25 Y-88 5.56 E-1 5.45 E-1 1.02 0.80
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It can be seen that-the agreement is good for the two liquid geometries listed above.
In general, comparisons betweea,liiuids tend to agree better than comparisons between l
charcoal or filter paper. The homegeneity of activity distribution usually fo'und for liquids, however, is not necessar;ily to be expected for other matrices.
Differences in the deposition of activities on filter paper or charcoal cartridgkcalibration standards, which is not uncommon, will cause differences in calibration parameters between these standards
and other similar standards.
These apparent differences are most severe near the surface of the detector and becomes less so with
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distance from the detector.
The results below illustrate these
effects.
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-4-TABLE 4A SCE Particulate Filter Standard (On Surface)
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NRC Reference Value Ratio Agreement
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Nuclide Becq.
Becq.
NRC/Ref Range Cd-109 3.67E4 4.90 E4 0.75 0.85 - 1.18 Co-57 7.39 E2 9.97 E2 0.74 0.80 - 1.25 i
Ce-139 9.73 E2 1.44 F3 0.68 0.80 - 1.25 Sm-ll3 2.26 E3 3.18 E3 0.71 0.80 - 1.25 Co-60 2.71 E3 3.58 E3 0.76 0.85 - 1.18 Y-88 3.59 E3 4.73 E3 0.76 0.80 - l.25 Cs-137 1.45 E3 1.93 E3 0.75 0.85 - 1.18
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TABLE 4B
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SCE Particulate Filter Standard (* Shelf - 3)
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NRC Reference Value Ratio Agreement Nuclide Becq.
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NRC/Ref.
Range Cd-109 4.34 E4 4.90 E4 0.89 0.85 - 1.18 Co-57 8.53 E2 9.97 E2 0.86 0.80 - 1.25 Ce-139 1.32 E3 1.44 E3 0.92 0.80 - 1.25
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i Sn-113 2.66 E3 3.18 E3 0.84 0.75 - 1.33
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Co-60 3.09 E3 3.58 E3 0.86 0.80 - 1.25 Y-88 4.14 E3 4.73 E3 0.88 0.75 - 1.33 Cs-137 1.68 E3 1.93 E3 0.87 0.80 - 1.25
- Shelf-3 is 10 cm from surface of detector.
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l TABLE SA
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NRC Measurement of SCE Charcoal Cartridge (Homogeneous)
(Eu-152 Standard)
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(On Surface)
r NRC Value*
NRC Value*
NRC Value Reference Ratio (Side 1)
(Side 2)
(Average)
Value NRC/Ref.
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(9.30 + 0.66)E4 (9.42 + 0.67)E4 (9.36 + 0.47)E4 1.18 E4 0.79 i
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- These values are the average activities for each face of the cartridge calculated from 6 different photon energies.
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-5-TABLE 5B SCE Charcoal Cartridge Homogeneous (Eu-152 Standard)
(Shelf 3)
Ratio NRC Value*
Reference Val.
NRC/Ref.
(1.08 + 0.04)E4 1.18 E4 0.92
- This value is the average activity calculated from 6 different photon energies.
TABLE 6
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NRC Charcoal Cartridge ~ (Homogeneous)
SCE Reference Value.
Ratio Agreement Nuclide uCi uCi
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Range -
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Co-57 2.99 E-2 2.33 E-2 1.28 0.75 - 1~.33
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Co-60 2.07 E-1 1.77 E-1 1.17 0.75 - 1.33 Y-88 3.46 E-l 3.00 E-1 1.15 0.75 - 1.33 Cs-137 1.53 E-1 1.31 E-1 1.17'
.0.75 - 1.33 TABLE 7
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i NRC Charcoal Cartridge (Face loaded)
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Reference Value Ratio Agreement Nuclide uCi uCi SCE/Ref.
Range j
Co-57 4.25 E-2 4.42 E-2 0.96 0.75 - 1.33 Co-60 5.54 E-3 5.79 E-3 0.96 0.75 - 1.33 (
Cs-137 3.13 E-2 3.27 E-2 0.96 0.75 - 1.33
- The SCE results were obtained by averaging the counts from both faces of the cartridge and correcting for efficiency using the efficiency i
j parameters obtained with the face loaded charcoal cartridge standard.
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. ' l Tables 4A, 4B, 5A and SB illustrate how calibration standards which are seemingly identical can differ (because they are actually not identical), Land how these differences can be minimized by measuring away from the surface of the detector.
Table 7 shows how data can be made to agree by manipulating measurement procedures. This particular procedure happened to
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provide the best results for this comparison but this will not be the case, generally, for other situations.
The data tabulated in Tables 8 and 9 provide comparisons for the 33 ml. gas bulb geometry.
TABLE 8 33 ML Bulb Geometry (Liquid)
SCE Reference Value Ratio Agreement Nuclide uCi uCi SCE/Re.
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Co-60 5.37 E-3 4.55 E-3 1.18 0.75 - 1.33 Y-88 9.43 E-3 7.68 E-3 1.23 0.75 - 1.33 Co-57 7.34 E-4 5.96 E-4 1.23 0.75 - 1.33 Cs-137 3.91 E-3 3.36 E-3 1.16 0.75 - 1.33 TABLE 9 NBS Kr-85 Standard (30 ML Glass Bulb Geometry)
SCE Reference Value Ratio Agreement Nuclide uCi uCi SCE/Ref.
Range Kr-85 1.77 E6*
1.49 E-6 1.19 0.75 - 1.33
- Corrected activity - Initial result obtained using calibration parameters for liquid was corrected for a gas matrix.
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Although in actual practice, this geometry is for measuring gases,
Table 8 results are for a liquid matrix. Both SCE and NRC calibrations for this gsametry were performed initially with a liquid standard.
Calibration.'arameters for a gas matrix were calculated by estimating
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the "mean path length" (radius) through the liquid volume and applying the appropriate attenuation coefficients for the photon energies measured.
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-7-Table 9 gives the result obtained by SCE for an NBS Kr-85 gas standard.
Consistent with the data for the liquid matrix, SCE is high by about 20 percent also for the Kr-85. This could be due to differences in the wall thickness of the bulbs, volume diffu " aces, an actual systematic difference in standards, or a combination of all of these.
Despite these differences, however, the results all fall in the agreement category.
In general, it can be concluded that SCE has demonstrated the adequacy of its calibrations.
It would be desirable, nevertheless, to periodically continue to confirm and upgrade as required, the various calibration parameters with different or new standards and especially to recalibrate the gas counting geometries with actual gas standards when they become available.
This inspection has determined that all prior commitments and unresolved items relative to radiochemical measurements and procedures have been adequately addressed and resolved. On the basis of these findings, license condition 21, " Laboratory Instrumentation" is considered to have been fulfilled.
4.
Exit Interview Inspection findings were discussed with members of licensee management and staff indicated in paragraph 1.
The inspector agreed-that the inspection report would address the issue of adequacy of laboratory operations in conforming with license condition 21.
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