IR 05000397/1985035
| ML17278A481 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 10/24/1985 |
| From: | Hamada G, Yuhas G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML17278A480 | List: |
| References | |
| 50-397-85-35, NUDOCS 8511210252 | |
| Download: ML17278A481 (10) | |
Text
U. S.
NUCLEAR REGULATORY COMMISSION
REGION V
Report No.
Docket No.
50-397/85-35 50-397 License No.
NPF-21 Licensee:
Facility Name:
Washington Public Power Supply System P.
O. Box 968 Richland, Washington 99352 H
'NP-2 Inspection at:
Hanford Site inspection conducted:
Inspector's:
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P G. H.
September 13-18, 1985 gl da," Radiation aboratory Specialist lo Da e igned Approved By:
I Summary:
G.'ha Facili,tie ief adiological Protection Section I
o 0 Date Signed Ins ection of Se tember 13-18 1985 (Re ort No. 50-397/85-35)
Areas Ins ected:
Confirmatory split sampl'e measurements of gamma emitting radionuclides in gas, liquid, charcoal and particulate samples.
I,aboratory capability to perform low level trace 'element analysis was also reviewed.
Inspection Procedures 84725 and 79501 were performed.
The inspection involved 26 onsite hours by one inspector.
Offsite inspection totaled 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
Results:
No items of noncompliance were identified in the areas examined.
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DETADS 1.
Persons Contacted
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~ L a J Graybeal, Manager, Health Physics and Chemistry Nielson., Chemistry and Rad Protection Technician Morrison, Chemistry Supervisor Powers, Plant Manager W. Shannon, Assistant Managing Director
- Indicates personnel present at exit interview.
2.
Discussion Confirmatory measurements for filter paper, charcoal cartridge, liquid and gas media were performed utilizing the Region V Mobile Laboratory.
The results are summarized below.
Table
Gas (Primar Containment)
Nuclide WNP-2 uCi/cc NRC uCi/cc Ratio WNP-2/NRC Agreement
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Xe-133 Xe-135 1.82 E-8 1.93 E-8 2.79 E-8 2.52 E-8 Oe65 0.77 0.50 - 2.00 0.5 - 2.00 Table 1 shows that acceptable agreement was achieved for the gas category.
The wide agreement range is indicative of the poor counting statistics obtained by the NRC for this measurement.
Because of the expected low levels of activity in containment air, WNP-2 uses a
procedure whereby the noble gases are concentrated onto activated charcoal at, -37 degrees centigra'de.
A nominal 40 liter sample is collected for measurement.
(Seq Inspection Report No. 50-397/84-30).
A one liter sample was obtained for the NRC because NRC's calibration for gases extends up to a maximum, of 'a,1 3.i.ter sample.
A two hour count was taken to,improve,'counting 's'tatistics., Despite the low activities measured, it was encouraging't'o ~see tha't agreement was achieved.
This attests to"the validity not", only of the measurement method but also of the sampling~procedure.
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Table
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Nuclide" Na-24 Co-58 Co-60 Zn-65 Tc"99M WNP-2 uCi/cc 1-.57 E""12 1.49 E-'12 2.20 E-13 3.78 E-12 2.32 E-13 NRC
~uCi cc 2'4 E-12
~ 58 E-12 2.49 E-13 4.01 E"12 2.38 E"13 Table
Charcoal Cartrid e
Ratio WNP-2/NRC 0.70 0.94 0.88 0.94 0.97 e
Agreement
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0.60 - 1.66 0.75 - 1.33 0.60 " 1.66 0.60 - 1.66 0.60 - 1.66 Nuclide WNP-2 uCi/cc NRC uCi/cc Ratio WNP-2/NRC Agreement
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I-131 I-133 Br-82 6.73 E-13 6.62 E-13 2.57 E-12 6.66 E-13 1.01 6.58 E-13 1.01 2.89 E-12 0.89 0.75 - 1.33, 0.60 - 1.66 0.75 - 1.33 Tables 2 and,3 summarize the results obtained for a filter and a charcoal cartridge medium.
Acceptable agreement was paper medium achieved for both categories't is interesting that Br-82 continues to in the charcoal cartridge.
(See Report No. 50-397/84-30)
Table
be observed Nuclide Na-24 Cr-51 Mn-54 Mn-56 Co-58 Co-60 CQ-64 Zn-65 Zn-69M As-76 Sr-91 Sr-92 I-132 I-133 I-134 WNP-,2 uCi/cc 1.62 E-3 4.75 E-4 2.88 E-5 7.51 E-3 4.33 E-4 7.90 E-5 1.21 E-1 7.78 E-4 4,34 E-4 7.28 E-5 7.25 E-5 4.06 E-4 2.82 E-4 1.37 'E-4 8.50 E-'4; NRC uCi/cc 1.53 E-3 4.98 E-4 2.75 E-5 8.19 E"3 4.34 E-4 7.54 E-5 1.11 E-1 8.12 E-4 4.24 E-4 8.26 E-5 9.99 E"5 3.72 E-4 2.30 E-4 1.16 E-4 7.97 E"4 Ratio WNP-2/NRC 1.06 0.95 1.06 0.92 1.00 1.05 1.09 0.96 1.02 0.88 0.73 1.09 1.23 1.18 1.07 Agreement
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0.80 - 1.25 0.60 - 1.66 0.60 - 1.66 0.50 - 2.00 0.80 - 1.25 0.75 - 1.33 0.75 " 1.33 0.80 - 1.25 0.75 " 1.33 0.60 - 1.66 0.60 - 1.66 0.75 - 1.33 0.75 - 1.33
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Table 4 lists the activity comparisons for a reactor coolant sample.
It is noteworthy that activation products constitute the major fraction of the total activity.
On the basis of the results obtained for the various test media, it can be concluded that the radioactivity measurement program at WNP-2 is in control and valid results are being obtained on required measurements.
During this inspection, an assessment of laboratory capability to measure low concentration trace elements in water systems'was performed. It was learned that a new water chemistry group had just been formed to address the issues related to water chemistry and water chemistry control.
Because WNP-2 is already generally meeting industry guidelines on water quality, it. is expected that this group would serve to formalize this function through the development of specific criteria and procedures for water quality.
,Currently operational measurement systems include the ion chromatograph and plasma spectroscopy units.
This effo'rt to more rigidly control anionic and cationic contaminants in water systems should enhance the longevity of plant hardware and also reduce occupational exposure in keeping with the AIARA principle.
3.
Exit Interview Inspection findings were discussed with licens'ee personnel indicated in paragraph l. ',Iic'ensee management was informed of the generally good agreement obtained Xor all,'ample media tested.
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Enclosure Criteria for Acce tin the Licensee's Measurements Resolution Ratio
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- 200 200 0.4 0.5 0.6 0.75 0.80 0.85 2.5 2.0 1.66 1.33 1.25 1.18 Com arison 1.
Divide each NRC result by its associated uncertainty to obtain the resolution.
(Note:
For purposes of this procedure, the uncertainty is defined as the relative standard deviation, one sigma, of the NRC result as calculated from counting statistics.)
2.
Divide each licensee result by the corresponding NRC result to obtain the ratio (licensee result/NRC).
3.
The licensee's measurement is in agreement if the value of the ratio falls within the limits shown in the preceding table for the corresponding resolutio S