IR 05000528/1987004
| ML20204C961 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 03/19/1987 |
| From: | Hamada G, Russell J, Tenbrook W, Yuhas G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20204C910 | List: |
| References | |
| 50-528-87-04, 50-528-87-4, 50-529-87-05, 50-529-87-5, 50-530-87-05, 50-530-87-5, NUDOCS 8703250405 | |
| Download: ML20204C961 (7) | |
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k U. S. NUCLEAR REGULATORY COMMISSION
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REGION V
Report Nos. '50-528/87-04, 50-529/87-05, 50-530/87-05 Docket Nos.
50-528, 50-529, 50-530
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License Nos.
NPF-41, NPF-51 Construction Permit No.
CPPR-143
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Licensee:
Arizona Nuclear Power Project P. O. Box 52034 Phoenix, Arizona 85072-2034 Facility Name:
Palo Verde. Units 1, 2, and 3 Inspection at: Wintersburg and Tempe, Arizona Inspection ~ Conducted:
February 3-12 and February 25-26, 1987 Inspectors:
Ant!AA b/It)f(7 G. Hamada, Radiation Laboratory Specialist Date Signed JhflD J. Russell, R'adiation Specialist D&te: Signed
// Uwb 3l/ 77'
W. Te Brook Radiation Specialist Date Signed Approved by:
7//h/7 G.' Yuhas, Chyef Ddte ' Signed Facilities Radiological Protection Section Summary:
Inspection of February 3-12'and February 25-26, 1987 (Report No. 50-528/87-04, 50-529/87-05, 50-530/87-05)
Areas Inspected: Assess the capability of Unit 3 to perform required radioactivity and chemical analyses and check the adequacy of selected ineasurements routinely performed by Units 1 and 2.
This inspection involved inspection procedures 84525, 84725 and 79501.
Results:
No items of noncompliance were identified in the areas examined.
8703250405 870320 gDR ADOCK 05000528 PDR
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DETAILS.
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PersonsContacthd.
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'*T. Bradish, Supervisor," Compliance'.
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1*L. Brown, Manager,. Radiation Protection 'and Chemistry
- B. Cederquist, Manager,. Chemical-Services
- K. Chavet, Corporate Chemist
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- R. Ferro, Unit'3: Chemistry Lead
- . D2 Goodwin,, Unit'1 Chemistry Lead
- C. Gray,s unit 3 Chemistry Lead _
- K. Hodges, Unit 1 Chemistry Lead H. Hurley, Unit 3 Radiological Engineer
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- L. Johnson, Senior Nuclear Safety Engineer
- R. Johnson, Unit 2 Chemistry Supervisor.
- J. Mann,. corporate HP/ Chemistry Supervisor J. Riehs, Unit 3 Chemistry Technician
- J. Scott, Unit 3 Chemistry Supervisor
- T. Shriver, Manager, Compliance
- J. Sills, Senior Compliance Engineer
- T. Warren, Unit 1 Chemistry Supervisor
- Indicates personnel present at exit interview.
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Discussion Thisinspectionconsistedofareviewoftheradiochemistkyandchemistry programs at all three Palo Verde units. Most of the effort, however,
. involved Unit 3 because a: request for an operating license is expected to be submitted in the near future.
The NRC mobile laboratory. was brought onsite to perform check measurements on a variety of sample categories.
The results of these measurements are summarized below:
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Table 1 Charcoal Cartridge s
Nuclide
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pCi/Samp.
Unit 3/NRC
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Unit 3 NRC Ratio
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Range
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Ba-133 7.66 E-2 7.30 E-2 1.05 0.80 - 1.25
- See enclosure for explanation.
As a further check on the charcoal cartridge geometry, the charcoal cartridge calibration standard used by Unit 3 to calibrate for efficiency was measured on the NRC spectroscopy system.
Results obtained by the NRC
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were well within 10 percent of the certificate values assigned to the nuclides present in the standard.
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Unit 3 #
Unit 2 NRC Ratio E
Nuclide pCi/ml pCi/ml pCi/ml Unit 3/NRC _
Agreement
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Mn-54 1.48 E-4 1.36 E-4 1.69 E-4.
0.88 0.'60 - 1.66 Co-58 3.00 E-3 3.04 E-3
~2.96 E-3 1.01 0.80 - 1.25 Co-60 4.65 E-4 4.35 E-4 5.04 E-4 0.92 0.75'- 1.33 Tc-99M 7.27 E-5 7.55 E-5 5.52 E-5 1.32 0.50 - 2.00 Ag-110M 1.00 E-3 9.02 E-4 9.30 E-4 1.08 0.75 - 1.33 7.38 E-4
'0.75 - 1.33 Sn-117M
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Sb-122 9.24 E-4 9.00 E-4 9.25 E-4 1.00 0.75 - 1.33~
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Sb-124 5.45 E-2 5.58 E-2 5.54 E-2 0.98 0.85 - 1.18 I-131 3.22 E-4 2.74'E-4 3.21 E-4 1.00 0.60~- 1.66 Cs-137 3.97 E-4 4.01 E-4 3.98 E-4 1.00 0.75 - 1.33 Although only the NRC measurement shows the presence of Sn-117M, it is listed in'the above table because it appears to be "real."
The 158 Kev line associated with Sn-117M was observed with good statistics in the licensee's measurements but remained unidentified because'Sn-117M was not included in their respective libraries and also because this energy could not be matched against any of the other nuclides in either library.
Measurements are now being performed to determine the half-life of the 158 Kev line.
A 13-day half-life would confirm the presence of Sn-117M.
(Sn-117M'is now included in the licensee's library).
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Table 3 Suspended Solids in Reactor Coolant Unit 3 Unit 1 NRC Ratio Agreement Nuclide pCi/ml pCi/ml pCi/ml Unit 3/NRC Range Cr-51 5.66 E-5 5.87 E-5 7.20 E-5 0.79 0.75 - 1.33 Mn-54 8.47 E-6 1.12 E-5 1.09 E-5 0.78 0.75 - 1.33 Fe-59 1.69 E-5 1.68 E-5 2.10 E-5 0.80 0.75 - 1.33 Co-58 1.24 E-4 1.16 E-4 1.31 E-4 0.95 0.80 - 1.25 Co-60 5.16 E-5 5.30 E-5 5.53 E-5 0.93 0.80 - 1.25 3.34 E-6 1.23 0.75 - 1.33 Sn-117M 4.10 E-6
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Sb-122 8.41 E-6 8.10 E-6 8.76 E-6 0.96 0.75 - 1.33 Sb-124 2.04 E-4 1.82 E-4 2.16 E-4 0.94 0.80 - 1.25 Zr-95 1.24 E-5
~9.43 E-6 1.10 E-3 1.13 0.75 - 1.33 Nb-95 1.20 E-5
'1.13'E-5 1.36 E-3 0.88 0.75 - 1.33 The suspended solids sample was obtained by filtering 100 ml of reactor
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coolant (Unit 1) through a membrane filter.
This sample was obtained to test the adequacy of calibration for the particulate filter geometry.
In the above table (Table 3) the presence of Sn-117M is again indicated.
In this case,'however, it~was possible to manually calculate the Sn-117M activity for the licensee's measurement (Unit 3) based on information provided in the raw data sheets which was not available in the earlier
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measurement (Table 2).
It might be noted that all of the nuclides in Table 3 can be placed in the activation product category.
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Table 4 Waste Gas Unit 3 Unit 2 NRC Ratio Agreement Nuclide pCi/ml pCi/ml pCI7ml Unit 3/NRC Range Kr-85 5.00 E-3 3.13 E-3 4.15 E-3 1.60 0.60 - 1.66 Xe-131M 12.45 E-3 1.94 E-3 2.01 E-3 1.22 0.75 - 1.33 Xe-133 5.42 E-2 4.04 E-2 4.60 E-2 1.18 0.80 - 1.25 2.11 E-5 1.33 0.50 - 2.00 Xe-133M 2.80 E-5
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The above table summarizes the data obtained for fission gases.
The results indicate adequate agreement for the gas category.
Table 5 Steam Generator Wipe Unit 3 NRC Ratio Agreement Nuclide pCi/Samp.
pCi/Samp.
Unit 3/NRC Range
- Na-24 3.89 E-3 2.82 E-3 1.38 0.60 - 1.66 Cr-51 5.78 E-2 6.34 E-2 0.91 0.75 - 1.33 Mn-54 4.94 E-3 5.20 E-2 0.95 0.75 - 1.33 Fe-59 6.06 E-3 5.99 E-3 1.01 0.75 - 1.33 Co-57 1.81 E-4 2.06 E-4 0.88 0.40 - 2.50 Co-58 1.02 E-1 1.10 E-1 0.93 0.80 - 1.25 Co-60 3.65 E-2 3.91 E-2 0.93 0.80 - 1.25
- Sr-92 1.96 E-2 1.28 E-2 1.53 0.60 - 1.66 Zr-95 9.39 E-3 1.02 E-2 0.92 0.75 - 1.33
- Z r-97 1.31 E-3 1.46 E-3 0.90 0.60 - 1.66
- Nb-95 1.76 E-2 1.88 E-2 0.94 0.80 - 1.25
- Nb-97 3.07 E-2 3.00 E-2 1.02 0.80 - 1.25 Tc-99M 4.40 E-4 3.65 E-4 1.21 0.50 - 2.00 Ru-103 2.15 E-3 2.37 E-3 0.91 0.60 - 1.66.
- Ru-106, 7.14 E-3 Rh-106
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Ag-110M 2.79 E-2 2.96 E-2 0.94 0.80 - 1.25 Sn-113
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6.02 E-4
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2.09 E-4 Sn-117M
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Sb-122 2.32 E-3 3.18 E-3 0.73 0.60 - 1.66 Sb-124 1.01 E-1 1.05 E-1 0.96 0.80 - 1.25 Ce-141 1.06 E-3 1.34 E-3 0.79 0.60 - 1.66
- Ce-144 1.39 E-3
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The table above lists the nuclides identified in a wipe sample obtained from the Unit 1 steam generator which was undergoing eddy current tests.
This measurement was made to verify the quantity and type of activity
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being observed in the steam generator.
The nuclides listed are those identified by the nuclide identification software of the respective gamma spectroscopy systems. Although this list is.not an accurate catalog of nuclides actually present, all activities identified by the software are included to show that the calibration parameters for the energies represented by these nuclides are adequate.
When the peak data were examined, it was determined that of the 49 peaks identified, 14 resulted from silver-110M (Ag-110M) and 16 from antimony-124 (Sb-124).
Some of these peaks are similar enough to the key energies of other nuclides to provide false positive identification of these nuclides.
The false positive nuclides are indicated with a single asterisk.
The double asterisk for Nb-95 indicates that a significant fraction (~25%) of its activity was due to contribution from Ag-110M.
Because of better counting statistics for the NRC measurement, certain nuclides not detected by the licensee were identified by the NRC. These nuclides are listed to show the variety of activation products in the sample.
Of particular interest at this time are the antimony nuclides Sb-122 and 58-124.
The antimony is obtained from wear and subsequent activation of antimony-carbon bearings in the reactor coolant pumps.
The antimony activity in Unit 1, however, is up to a 100 times greater than activities seen in other plants with similar pumps.
This enhanced antimony activity could be due to a leaky antimony-beryllium (Sb-Be) secondary neutron source which these plants use.
This latter possibility is being investigated by the licensee.
Table 6 Spiked Sample (RESL)
Unit 3 Certificate Unit 2 Certificate Unit 1 Certificate Nuclide pCi/ml Value pCi/ml Value pCi/ml Value H-3 1.13 E-4 1.29 E-4 1.02 E-4 9.46 E-5 6.41 E-5 6.46 E-5 Fe-55 6.76 E-5 7.83 E-5 4.89 E-5 5.78 E-5 4.45 E-5 3.94 E-5 Fe-59 2.64 E-5 2.55 E-5 2.42 E-5 1.87 E-5 1.84 E-5 1.28 E-5 Mr-54 1.08 E-4 1.06 E-4 8.38 E-5 7.83 E-5 5.98 E-5 5.34 E-5 Co-60 1.04 E-4 1. 02 E-4 8.50 E-5 7.53 E-5 5.26 E-5 5.14 E-5 Cs-137 1.54 E-4 1.50 E-4 1.13 E-4 1.10 E-4 7.60 E-5 7.54 E-5 Gross
' Beta 4.16 E-4 3.60 E-4 3.80 E-4 2.73 E-4 2.15 E-4 1.82 E-4 Table 6 represents the results obtained for spike samples provided by the NRC (through the Radiological and Environmental Sciences Laboratory) to each of.the units.
The spikes had been sent earlier and was intended to test labcratory capability to perform measurements requiring chemical separations and soft X ray and beta counting.
In addition to the nuclides listed, the spikes also contained Sr-89 and Sr-90.
The strontium results, however, are not included in the table because the in-house strontium analysis procedure is not sensitive enough to accurately measure the levels provided in the spikes.
This procedure was designed primarily to obtain strontium information for the purpose of calculating the average energy (E) of radioactivity in primary coolant
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and for which high sensitivity is not required. When more sensitive strontium measurements are required,.as for example in composite filter samples, a' vendor laboratory is used.
It was agreed that-NRC would provide another set of spikes.containing strontium activity and these in turn would be sent to-the vendor-laboratory for analysis.
Also, the licensee is expected to periodically submit additional spikes to the vendor laboratory as a part of the QA program to check the validity of vendor. laboratory measurements.
(Item No. 50-528/87-04-01)
The chemical analysis program at Unit 3 las reviewed from the standpoints of equipment, laboratory facility and personnel.
Unit 3 is structured and organized like its counterparts at Units 1 and 2.
It is equipped with state-of-the-art measurement systems which include the ion chromatograph and the atomic absorption analyzer.
It is well staffed and cognizant personnel have been trained in the operation of the various systems and are familiar with the pitfalls and limitations as well as the capabilities of these systems.
Based on this inspection, it can be concluded that the Unit 3 laboratory is capable of performing the required measurements and also that the
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routine radioactivity measurement programs at Units 1 and 2 are providing valid'results.
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Exit Interview Inspection findings were discussed with licensee personnel indicated in paragraph 1.
Licensee management was informed of the results of the spiked samples.
It was agreed that the question of Sr-89, Sr-90 analysis should be resolved by sending QA (spiked) samples to the vendor
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laboratory.
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Enclosure:
Criteria for Accepting the Licensee's Measurements
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Enclosure
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Criteria for Accepting the Licensee's Heasurements
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Resolution Ratio
<4 0.4
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0.6 1.66
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200 0.85 1.18
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Comparison 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.)
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Divide each licensee result by the corresponding NRC result to obtain the ratio (licensee result /NRC).
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The licensee's measurement is in agreement if the value of the ratio
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falls within the limits shown in the preceding table for the corresponding resolution.