IR 05000344/1985031
| ML20138M493 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 10/17/1985 |
| From: | Hamada G, Nelson G, Yuhas G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20138M492 | List: |
| References | |
| 50-344-85-31, NUDOCS 8511040015 | |
| Download: ML20138M493 (6) | |
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U. S. NUCLEAR REGULATORY COMMISSION
REGION V
Report No.
50-344/85-31 Docket No.
50-344 License No.
NPF-1 Licensee:
Portland General Electric Company 121 S. W. Salmon Street Portland, Oregon 97204 Facility Name:
Trojan Nuclear Plant Inspection at:
Rainier, Oregon Inspection conducted:
September 9-27, 1985
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Inspector:
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G. H. llamada, Radiation Laboratory Specialist Date Signed k f.
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. Ne so Chemist Date Signed g
/0 /7 ff Approved By:
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i,. 9. Yuhas, Chief Ea e S gned Facilities Radiological Protection Section Summary:
Inspection of September 9-27, 1985 (Report No. 50-344/85-31)
Areas Inspected:
Confirmatory split sample measurements of gamma emitting radionuclides in gas, liquid, charcoal and particulate samples.
Laboratory capability for performing trace element analysis (in the parts per trillion range) was also reviewed.
The inspection involved 54 onsite hours by two inspectors. Offsite inspection totaled six hours.
Results: No items of noncompliance were identified in the areas examined, gy1O40015g510tg Q
ADOCM c500o344 PDR
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DETAILS 1.
Persons Contacted
- S. Bauer, Onstte Regulation Engineer
- G.
C. Kernion, Plant Chemist
- D. Keuter, Manager, Technical Service R. Roth, Chemistry and Radiation Protection Technician L. Timme, Chemistry Technician W. Van Dusen, Chemistry Technician
- Indicates personnel present at exit interview.
2.
Discussion Split sample comparisons of gamma radioactivity measurements for various -
sample categories were performed utilizing the Region V Mobile Labo rato ry.
The results are summarized below.
Tabic 1 Charcoal Cartridge Trojan NRC Patio
- Agreement Nuclide uCi/cc uCi/cc Trojan /NRC Range I-131 1.57 E-11 1.49 E-11 1.05 0.60 - 1.66 I-132 2.00 E-11 2.01 E-11 1.00 0.60 - 1.66 I-133 7.88 E-11 8.14 E-11 0.97 0.75 - 1.33 I-134 8.68 E-12 8.71 E-12 1.00 0.50 - 2.00 1-135 7.56 E-11 7.43 E-11 1.02 0.60 - 1.66 Cs-138 2.11 E-11 2.46 E-11 0.86 0.40 - 2.50
- See enclosure for explanation.
Table 2 Filter Paper Trojan NRC Ratio Agreement Nuclide uCi/cc uCi/cc Trojan /NRC Range Cs-138 8.07 E-10 1.01 E-9 0.80 0.75 - 1.33 Ba-139 3.27 E-11 3.60 E-11 0.91 0.60 - 1,66
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The data in Tables 1 and 2 are for the charcoal cartridge and filter paper samples obtained from the secondary side at the air ejector discharge.
It can be seen that the agreement is adequate.
Table 3 Liquid Waste Treated Radwaste Monitor Tank Trojan NRC Ratio Agreement Nuclide uCi/ml uCi/ml Trojan /NRC Range co-58 3.08 E-7 3.25 E-7 0.95 0.60 - 1.66 Co-60 2.21 E-6 2.40 E-6 0.92 0.75 - 1.33 I-131 1.22 E-7 1.25 E-7 0.98 0.60 - 1.66 Cs-134 4.88 E-7 4.81 E-7 1.01 0.75 - 1.33 Cs-137 5.40 E-7 6.47 E-7 0.83 0.75 - 1.33 Table 4 Gaseous Waste Waste Gas Decay Tank Trojan NRC Ratio Agreement Nuclide uCi/cc uCi/cc.
Trojan /NRC Range Xe-131M i 1.21,E-3 9.92 E-4 1.22 0.60 - 1.66 Xe-133 9.92 E-2 1.02 E-1 0.97 0.85 - 1.18
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Xe-133M 4.36 E-4~
4.59 E-4 0.95 0.75 - 1.33 Tables 3 and 4 summarize the data obtained for a large liquid matrix and a gas matrix. Good agreement was obtained for both categories.
Table 5 RCS Liquid Trojan NRC Ratio Agreement Nuclide uCi/ml uCi/ml Trojan /NRC Range Ar-41 6.60 E-2 4.90 l'-2 1.35 0.60 - 1.66
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Rb-89 2.45 E-1 2.66 E-1 0.92 0.75 - 1.33 I-131 2.38 E-2 2.59 E-2 0.92 0.75 - 1.33 I-132 3.89 E-1 3.68 E-1 1.06 0.80 - 1.25 I-133 2.36 E-1 2.39 E-1 0.99 0.80 - 1.25 I-134 6.62 E-1 6.82 E-1 0.97 0.75 - 1.25 I-135 4.69 E-1 4.85 E-1 0.97 0.75 - 1.33 Cs-138 7.42 E-1 7.52 E-1 0.99 0.80 - 1.25 l
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Table 6 I
Stripped RCS Gas I.
I Trojan NRC Ratio Agreement l
Nuclide uCi/cc uCi/cc Trojan /NRC Range
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j Kr-85M 6.68 E-2 7.04 E-2 0.95 0.80 - 1.25
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Kr-87 1.62 E-1 1.58 E-1 1.03 0.80 - 1.25 i
kr-88 1.78 E-1 1.86 E-1 0.96 0.80 - 1.25 I
i Xe-133 2.18 E-1 2.72 E-1 0.80 0.80 - 1.25 I
Xe-133M 1.69 E-2 1.10 E-2 1.54 0.50 - 2.00 j
i Xc-135 4.85 E-1 5.01 E-1 0.97 0.85 - 1.18
Xe-135M 1.34 E-1 1.68 E-1 0.80 0.75 - 1.33
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Xe-138 6.64 E-1 7.35 E-1 0.90 0.80 - 1.25
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j Tables 5 and 6 show the results obtained for activity in reactor coolant j
and fission gas activity stripped from the coolant, respectively. To determine total reactor coolant gaseous activity, Trojan uses a procedure
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l whereby a reactor coolant sample is collected into a sample bomb under i
l pressure, with subsequent depressurization and stripping of the gases i
from the liquid phase into an evacuated vessel.
A sample of the stripped r
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j gas is obtained for analysis. To obtain non gaseous activity, a separate
l sample of reactor coolant liquid is obtained for analysis and only
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non gaseous activities are quantified. Af ter applying an appropriate
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I factor to correct for volume, the gas activities derived f rom gas analysis are added to the activities obtained for the liquid.
In
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general, the liquid analyzed is not the liquid fraction from which the j
gases were stripped for analysis.
Because the procedure as currently
applied assumes a high gas stripping efficiency, a test was conducted to
determine the actual stripping efficiency by analyzing for total gas l
,l activity in both the stripped liquid and gas fractions. The results
j indicated that as much as 10 percent or more could remain in the liquid
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fraction.
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(NOTE: When quantifying the gaseous activity in the stripped liquid, buildup of additional gas activity from the iodine parent must be accounted for. Also, 1-135 interferes with Xe-135M analysis.)
Based on the above finding, Trojan is changing its procedure to require i
j that the stripped liquid fraction be analyzed and that the gas activity i
j remaining in the liquid be included in the total.
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A new laboratory facility for performing trace element analysis has been completed and is currently operational.
It is equipped with state-of-the-art measurement systems (ion chromotograph and high sensitivity atomic absorption units) and staffed with qualified I
individuals. Procedures have been developed to preclude interference j
from potential contaminants that could bias the results.
For example, i
plastic sample bottles constructed of chlorine free material are used.
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Additionally, these bottles are pre-soaked with high purity water prior
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to use to remove surface contaminants and any other leachable material i
that. could be present. During analysis, the sample is fed into the ion i
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chromatograph through a plastic tube which exits the sample bottle through a close fitting hole in the bottle cap. This procedure minimizes sample contact with ambient air.
Laboratory air is filtered air and flow is balanced such that significant pressure differentials are not created in any given location. - This laboratory appears to be well suited to perform trace analyses. The ability of the plant to measure and control trace contaminants in its water systems to industry recommended levels will not only enhance the durability of plant systems, but could also significantly decrease occupational exposure in keeping with the ALARA principle.
3.
Exit Interview Inspection findings were discussed with Trojan personnel indicated in paragraph 1.
Management was informed of the generally good agreement.
achieved in the split sample tests for all sample categories.
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l Enclosure Criteria for Accepting the Licensee's Measurements
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Resolution Ratio
<4 0.4
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2.5
7 0.5 2.0
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50 0.75 1.33
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51 - 200 0.80 1.25
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1.18 200 0.85
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Comparison l
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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.)
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2.
Divide each licensee result by the corresponding NRC result to obtain the ratio (licensee result /NRC).
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3.
The licensee's measurement is in agreement if the value of the ratio i
falls within the limits shown in the preceding table for the
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corresponding resolution.
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