IR 05000344/1986040

Insp Rept 50-344/86-40 on 861027-30 & 1117-18.No Items of Noncompliance Noted.Major Areas Inspected:Confirmatory Measurements of Radioactivity in Various Sample Media Performed

ML20212E179
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	12/17/1986
From:	Hamada G, Russell J, Tenbrook W, Yuhas G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML20212E139	List: IR 05000344/1986040 ML20212E133
References
50-344-86-40, NUDOCS 8701050270
Download: ML20212E179 (7)

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U. S. NUCLEAR REGULATORY COMMISSION ,

REGION V .

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, Report N /86-40

Docket N '

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. License N NPF-1 ,

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Licensee: Portland General Electric Company 121 S. W. Salmon Stree Portland, Oregon 97204 . ,

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Facility Name: Trojan Nuclear Plant

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Inspection at: Rainier, Oregon I Inspection Conducted: October 27-30 and November 17-18, 1986-Inspectors: - />//7/84,

G. Hamada, Nadiation Laboratory Specialist ~ Date ' Signed E

J.. Russell', Nadiation Specialist

/2l/7lB4 Date S'igned MW W..T6nBrook, Rhdiation Specialist

/z/n/si D7te Signed Approved by: ~[Af

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/ 7 G. Yuhas, Chief Da Signed Facilities Radiological Protection Section  ;

Summary:

Inspection of October 27-30 and November 17-18, 1986 (Report-No. 50-344/86-40)

Areas Inspected: Confirmatory measurements of radioactivity in various  !

sample media were performe Laboratory capability to measure trace anionic l-and cationic species in secondary and primary systems was reviewed. This inspection involved inspection procedures 84725 and 7970 Results: No items of noncompliance were identified in the areas examine DjO 86121e O Dhyj05000344 PDR ,

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DETAILS Persons Contacted

• S. Bauer, Onsite Regulation Engineer

• G. Kernion, Laboratory Supervisor

• D. Keuter, Manager, Technical Services

• D. Leslie, NQAD QA Engineer

• G. Rich, Chemistry Supervisor

• C. Sprain, Steam Generator. Program Engineer ,

L. Timme, Chemistry Technician

• Indicates personnel present at exit intervie . Discussion The Region V mobile laboratory was brought on site to perform confirmatory measurements on a variety of sample categories. The results of these tests are summarized below:

Table 1 Waste Gas Trojan NRC Ratio * Agreement Nuclide pCi/ml pCi/ml Trojan /NRC ,

Range Kr-85 1.12 E-3 6.44 E-4 1.74 0.40-2.50 Xe-131m 2.76 E-4 3.19 E-4 0.87 0.75-1.33 Xe-133 3.48 E-3 3.69 E-3 0.94 0.85-1.18

• See enclosure for explanatio Table 2-Filter Paper A Trojan NRC Ratio Agreement Nuclide pCi/ml pCi/ml Trojan /NRC Range Rb-88 2.28 E-8 3.03 E-8 0.75 0.50-2.00 Cs-138 2.99 E-8 3.07 E-8 0.97 0.75-1.33 Table 3 Filter Paper B Trojan NRC Ratio Agreement Nuclide pCi/ml pCi/ml Trojan /NRC Range Rb-88 2.60 E-9 3.24 E-9 0.80 0.60-1.66 Cs-138 3.59 E-9 3.89 E-9 0.92 0.75-1.33 Ba-139 4.38 E-11 4.88 E-11 0.90 0.50-2.00

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Tables 1, 2, and 3 represent results obtained fo'r gas and fi1ter paper I

geometries. Because of low activity levels for the filter paper. matrix, a second cross-check sample was_obtained to confirm the result for the first sample. The data indicate adequate agreement for these categorie Table 4 Reactor Coolant-Trojan NRC Ratio Agreement-Nuclide pCi/ml pCi/ml Trojan /NRC Range Co-58 4.72 E-3 8.28 E-3 0.57 0.50-2.00 Ag-110m 7.01 E-3 6.40 E-3 1.10 0.50-2.00 I-131 2.16 E-2 2.45 E-2 0.88 0.75-1.33 I-132 2.57 E-1 3.12 E-1 0.82 0.80-1.25 I-133 1.60 E-1 1.i4 E-1 0.92 0.80-1.25 I-134 4.34 E-1 5.28 E-1 0.82 '0.80-1.25

~I-135 2.94 E-1 3.10 E-1 0.95 0.80-1.25 Cs-138 4.96 E-1 5.39 E-1 0.92 0.80-1.25 Ba-139 5.28 E-2 5.22 E-2 1.01 0.60-1.66 Table 5 Stripped Gas Trojan NRC Ratio Agreement Nuclide pCi/ml pCi/ml Trojan /NRC Range Kr-85m 3.51 E-2 4.38 E-2 0.80 0.80-1.25 Kr-87 7.15 E-2 7.52 E-2 0.95 0.80-1.25 Kr-88 8.19 E-2 9.83 E-2 0.83 0.80-1.25 Xe-133m 9.92 E-3 1.38 E-2 0.72 0.60-1.66 Xe-133 3.95 E-1 4.23 E-1 0.93 0.80-1.25 Xe-135m 6.41 E-2 8.50 E-2 0.75 0.75-1.33 Xe-135 2.63 E-1 2.99 E-1 0.88 0.85-1.18 Xe-138 2.74 E-1 3.06 E-1 0.90 0.80-1.25 Table 6 Stripped Liquid Trojan NRC Ratio Agreement Nuclide pCi/ml pCiZEl Trojan /NRC Range Na-24 3.77 E-3 5.64 E-3 0.67 0.50-2.00 Co-58 6.02 E-2 6.36 E-2 0.95 0.75-1.33 Rb-88 1.52 E-1 1.79 E-1 0.85 0.40-2.50 Rb-89 1.42 E-1 1.14 E-1 1.25 0.40-2.50 I-131 1.94 E-2 1.99 E-2 0.97 0.75-1.33 I-132 2.24 E-1 2.62 E-1 0.85 0.80-1.25 I-133 1.45 E-1 1.59 E-1 0.91 0.80-1.25 1 1-134 3.85 E-1 4.52 E-1 0.85 0.80-1.25 I-135 2.70 E-1 2.84 E-1 0.95 0.80-1.25 1

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Cs-138 4.02 E-1 4.48 E-1 0.90 0.80-1.25 Ba-139 4.22 E-2 5.72 E-2 0.74 0.60-1.66 Kr-85m -

2.07 E-3 - -

Xe-133 -

2.29 E-2 - -

Tables 4, 5, and 6 are the data for reactor coolant, gases stripped from the coolant and the stripped coolant respectively. The analysis of the stripped . liquid was performed to provide a basis for assessing the efficiency of the method used for stripping gases from reactor coolan Also, because these measurements are for two different samples of the coolant, the degree to which results in Table 4 agree with those in Table 6 (for comparable nuclides) would be an indication of the adequacy of the sampling procedure to provide a sample which is representative of the activity in the coolant. The noble gas activities (Kr-85m and Xe-133)

listed in Table 6 have been normalized for volume so that they may be compared-directly with activities of these nuclides given in Table The approximately 5 percent of gaseous activity remaining in the liquid fraction indicated by the data include the Kr-85m and Xe-133 activity ingrowth (from Br-85 and I-133) subsequent to gas stripping. The 5 percent or so of activity remaining is therefore biased slightly hig The data indicate that stripping efficiency is acceptable and that adequate agreement between the NRC and Trojan was achieved for gases and liquid Table 7 Charcoal Cartridge A Trojan NRC Ratio Agreement Nuclide pCi/ml pCi/ml Trojan /NRC Range I-131 1.04 E-12 1.29 E-12 0.81 0.50-2.00 I-133 2.40 E-12 2.02 E-12 1.19 0.50-2.00 Table 8 Charcoal Cartridge B Trojan NRC Ratio Agreement Nuclide pCi/ml pCi/ml Trojan /NRC Range I-131 4.48 E-10 3.68 E-10 1.22 0.75-1.33 I-132 9.78 E-11 7.89 E-11 1.24 0.50-2.00 I-133 6.95 E-10 5.72 E-10 1.22 0.75-1.33 Tables 7 and 8 list the results obtained for the charcoal cartridge geometry. Because of' low activity levels in the first sample, a second sample was obtained for confirmation. The results indicate adequate agreement for this categor , .. . .

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Treated Liquid Waste Monitor Tank I 10/27/86' Sample 10/28/86 Sample' ~ >

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Trojan _

NRC Trojan ,- .

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2L Sample 500 ml Sample 2L Sample,530 ml Sample" '500 ml Sample

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Nuclide .pei/ml pei/ml .pei/al' pei/ml -

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pei/ml

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Co-58 6.46 E-7 -1.21 E-6 4.61 E-7 e8.34,E-7 6.96'E-7 Co-60~ -3.10 E 6JI '7.89'E-6 ~ 1.50'E-6 '4'95 E-6 , ,\ 3.60 E-6

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' Nb-95 .4.24 E-7 7.67 E-7' 2.72 E;7 6.71 E-7 4.38'E-7

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Ag-110m 4.41 E-7 4.48 E-7 3.41 E-7 3.58 E-7 3.27 E-7 I7.02E-7

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Sb-125 8.47 E-7 8.52 E-7 6".51 E ,7 ~ 8.12 E-7 Cs-137 2.74 E-7 7.90 E-7 2.01 E-7 3.01 E-7 5.68 E-7 Mn-54 - -

'6.50 E-8 1.78 E-7 1.27 E- Zr-95 - -

1.12 E-7 3.40 E-7 1.76 E-7 Ru-103 '- -

4.02 E-8 8.51 E-8 7.30 E-8 Cs-134 - --

7.87 E-8 1.46 E-7 5.93 E-7-

- Ce-144 - -

2.01 E-7 3.86 E-7 2.60 E-7 NOTE: Because the samples taken on October 28, 1986 were counted for significantly longer intervals-than the first set, nuclides not observed in the October 27,.1986 samples were detected in the

' October 28,-1986 samples. For most of these nuclides, the agreement range for the Trojan /NRC ratio is 0.75-1.3 Table 9 summarizes the data obtained for samples of liquid waste.-

Additional samples were taken on October 28, 1986, when significant i

differences were observed for the splits obtained on October 27, 198 The splits taken for the October 28,=1986, sample consisted of a 530 ml

geometry'in addition to the 2 liter and 500 ml geometries of the previous day. . This was done to test for potential discrepancies in the calibration of Trojan's 2 liter geometry. Earlier, it was determined that Trojans 530 ml geometry was comparable to NRC's 500 ml geometry when NRC's analysis of Trojan's 530 al_ calibration standard gave results within about 5 percent of the certificate value for the various nuclides in the mix. As the results show, discrepancies were also evident for-the second' set. It appears that reproducible splits were not obtained for this sample possibly because of varying amounts of suspended solids in the fraction It should be noted that in both instances, the tank was recirculated for about an hour prior to sampling. Based on these results, Trojan agreed to conduct tests to assess the adequacy of the sampling procedure. Samples would be taken as a function of mixing time and also at different times to determine if consistent results can be

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obtained. _ If these' differences persist, it may be necessary to take the

.r average of several measurements to minimize the effects of sampling-error (0 pen Item No. 86-40-01).

In a continuing' effort to upgrade laboratory systems, Trojan acquired a new liquid scintillation system earlier this yea It is expected that the_ gamma spectroscopy system will be upgraded-in the near future. As a

_ part of the quality assurance program, the laboratory now participates 11n three separate analytical cross-check programs. The annual EPA cross-check and the semi-annual NWT Company cross-check are for nonradiological chemical analysis. The quarterly to semi-annual Analytics, Inc.,_ cross-check involve both radiological and nonradiological measurement . Exit Interview Inspection findings'were discussed with licensee personnel indicated in paragraph 1. . Licensee management was informed of the results of the

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confirmatory measurements and the necessity to conduct"further tests to determine the magnitude of the~ apparent sampling' error in sampling liquid *

wast It was also agreed that Trojan would analyze's spiked sample supplied by the NRC to check laboratory capability to measure, beta emitters and soft x-ray emitters (Open Item No. 86-40-02).

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Enclosure Criteria for Accepting the Licensee's Measurements Resolution Ratio

<4 .5 4 -

7 .0 8 - 15 .66 16 -

50 0.75 - 1.33 51 - 200 0.80 -

1.25 200 0.85 - 1.18 Comparison Divide each NRC result by its associated uncertainty to obtain the resolutio (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.) Divide each licensee result by the corresponding NRC result to obtain the ratio (licensee result /NRC). 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 .

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