IR 05000275/1981014
| ML16340C008 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 09/14/1981 |
| From: | Book H, Hamada G, Hankins G, Wenslawski F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML16340C007 | List: |
| References | |
| 50-275-81-14, NUDOCS 8109230664 | |
| Download: ML16340C008 (10) | |
Text
Report No. 50-275/81-14 U. S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION V
Docket No. 50"275 No CPPR-39 Safeguards Group Licensee:
Pacific Gas and Electric Company P. 0.
Box 7442 San Francisco, California 94120 Faci1ity Name:
Diablo Canyon Unit 1 Inspection at:
Avila Beach, California Inspection conducted:
July 20-23s 1981 Inspectors:
~
e ama as ate Signed G.
M. Hankins, Ra iation Instrumentation Technician ate Signed
'--=:"'"Approved by:
F. Mensl <sk, Chi f Reac ad tio otec n Section Approved by:
r H. E. Book, Chief, Radiological Safety Branch Summary:
Date Signed D te S gned Date Signed Ins ection of Jul 20-23 1981 Re ort No. 50-275 81-14)
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1 lg ptllttyt t measurements and-review of associated laboratory quality control programs.'ntercomparison test measurements were performed on secondary standards using the Region V Mobile Laboratory.
The inspection involved a total of 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> onsite by one inspector and one radiation instrumentation technician..
Results:
No
$ tems of noncompliance were identified in the areas inspected 8109230664 810914, PDR ADOCK 05000275 9 "'DR RV Form 219 (2)
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RETAILS Persons Contacted
- J. Boots, Supervisor, Chemistry and Radiation Protection
%. Ohara, Sr.
Chemistry and Radiation Protection Engineer
"J. Scott, quality Control Inspector
- R. Thor nberry, Plant Manager
- R. Twiddy, guality Assurance Supervisor D. Unger, Chem.
and Rad. Protection Engineer
- Indicates those present at the exit interview.
Measurement and Intercom arison of Standards ENERGY IN KEY NRC VALUE RATIO
~a" s sec
~NBS NRC During the inspection of April 27-30, 1981 (Report No. 50-275/81-09),
results of intercomparison measurements on secondary radioactivity standards indicated that agreement between the licensee and NRC was at best marginal to poor.
Although this did not constitute noncompliance with regulatory requirements, it was stipulated that better agreement for gamma measurements needed to be achieved.
As a first step towards this end, the licensee (PGSE) obtained new primary standards from the National Bureau of Standards (NBS) for fabricating secondary standards in the various geometric, configurations needed in the routine measurement program.
The current inspection was conducted to determine if the licensee's new, calibration parameters would permit better agreement than was achieved earlier.
I-Intercomparison measurements were per'formed using the Nuclear Data 6600 gamma spectrometry system in the Region V mobile laboratory.
The new NBS mixed nuclide standard solution consists of a mixture of antimony-125, tellurium-125m, europium-154 and europium-155.
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The results of the" measurements are tabulated below.
TABLE 1 PGBEiParticulate Flite'r Stanrfard'(
evNi NBS Standard)
(Measured on Surface of Detector)
NBS REFERENCE VALUE g's sec 86. 60 123. 10 176.40 248.00 427.90 600.60 635.90 723.30 996.40 1004.80 1274.40 215 635
108 333 198 127 313 163 282 542 140 330
51 230 138
167 119 178 357 1. 54 1. 92 1. 33 2. 12 1. 45 1.43 1.41 1. 87 1. 37 1. 58 1. 52
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ENERGY IN KEY TABLE 2 PGBE Particulate Filter Stanrfard (New NBS Standard)
(Measured on Shelf 3, 10 cm from Surface)
NBS REFERENCE VALUE NRC VALUE y's sec
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'274.40 215 189 1. 14 635 540 1. 18
73 1.05 108 103 1.05 333 285 1. 17 198 180 1.10 127 127 1.00 313 282 1. 11 163
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Tables 1 and 2 show the effect of source-to-detector solid angle on the count rates of two similar, b'ut.,n'ot identical particulate filter secon'dary standards; the NRC particulate,.filter standard, which was used to'calibrate.the NRC measurement sys'em, and the recently fabricated PG&E,'particulate filter standard.
Dis'similarities in the standard such'as lo'cal geometry, differences tend" to be magnified on the surface where the solid angle is large".
Also, large source-to-detector solid angles enhance correlated summing effects resulting from cascading gama t'ransitions, and,for active'ources can cause pulse-pileup effects because of higher'counting efficiencies on the surface.
Table 1 shows the results of measurements made on the surface of the detector.
Table 2 measurements were made approximately 10 cm (shelf 3) from the surface.
It can be seen that the agreement between PG&E and NRC is considerably better on shelf 3 than on the surface.
I These data show that the disparity in counting efficiencies between NRC and licensee calibration standards is most pronounced for measurements made on the surface.
This disparity will also be manifested when process samples are measured on the surface.
TABLE 3 PG&E Ll uld Sclntillatlcn VFaa -
10 NL -
New NBS Standard Sam le Position Surface Shelf
2.5 cm)
Shelf 2 5.0 cm)
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at o NBS'Re erence a ue NRC 1. 43 1. 26 1. 21 1. 15
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Table 3 shows a similar "shelf effect" for the 10 ml liquid scintillation vial geometry.
For homogeneous materials, such as solutions, however, better agreement even on the surface might have been expected.
Closer examination revealed that the liquid scintillation vial used by the licensee was not the same as that used by the NRC; the dimensions were not the same.
Therefore, differences in the measurement results should be expected.
TABLE 4 NRC 14 NL Serum~a%Pi uid Standard PGSE NRC REFERENCE VALUE RATIO NUCLIDE
's sec N's/seo
~PG&E NRC Am-241 Cd-109 Co-57 Sn-113 Cs-137 Y-88 Co-60 1060 1181 1342 2456 7788 21500 13900 873 1273 1467 2817 8267 20500 13033 1. 21 0.93 0.91 0.87 0.94 1. 05 1. 07 1. 02 1. 10 1. 07 Table 4 shows the results obtained by the licensee for the NRC serum vial standard.
These measurements were made at the
cm geometry.
The agreement is reasonably good despite the fact that the licensee's calibration for this configuration was made with a gas matrix.
The licensee's eq'uivalent results for liquid,would have yielded values about 15,percent higher on the average and would have given a higher ratio by about the same quantity.
TABLE '5 LI'id Sellout on from RESL" RESL
'PG&E REFERENCE VALUE RATIO NUCLIDE
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-4 In addition to the above intercomparisons, other PGSE secondary standards measured during the previous inspection were remeasured at the maximum shelf geometry (shelf 3). It is noted that even with the particulate filter standard which earlier showed evidence of significant physical deterioration, relatively good agreement was achieved on the third shelf.
Earliet measurements on the surface had indicated an average difference of about 76 percent between PGGE and NRC.
The difference averaged only 13 percent on the third shelf.
Concern'nitially expressed over the apparent discrepancy of 76 percent was based on the fact that the licensee's procedures called for making this type of measurement on the surface of the detector as a routine.
Conclusions The data indicated that both material and administrative changes were needed to correct the measurement discrepancies.
New calibration standards were needed to replace some of the older standards which had deteriorated physically; e.g.
the particulate filter and the liquid scintillation vial standards.
The licensee has done this, and recent data indicate that the current stock of calibration standards (which include some of the older standards)
are trustworthy and usuable.
However, because of differences in local geometry and other effects mentioned earlier, procedural changes are needed to preclude surface effects by calibrating and measuring samples some fixed distance away from the surface of the detector.
The licensee has agreed to to this.
Based on current findings, open item no. 81-09-01 is closed.
Open item no. 81-09-02 will remain open until such time as certain radiochemical measurements currently. underway have been completed.
Exit Interview Inspection findings were discussed with PG&E personnel referenced in Paragraph 1.
PGSE management was,informed of the resolution of the measuremerit problem an'd,that, generally good agreement has now been achieved'on 'all measurement categories reviewed under the confirmatory measurements progr'am, noting. that radiochemical measurements are currently underway and rema'in to be evaluated.
It was pointed out that measurement procedures need'o be changed"to require that measurements be performed away from the surface of the 'detector for reasons discussed earlier (paragra'ph 2),.-
The licensee agreed to implement this change.
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