ML20141N795
| ML20141N795 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 02/27/1986 |
| From: | Mineck D IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT |
| To: | Oestmann M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| DAEC-86-0153, DAEC-86-153, NUDOCS 8603180140 | |
| Download: ML20141N795 (9) | |
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lowa Electric Light and Ibwer Company.
February 27, 1986 DAEC-86-0153 p-Dr. M.J. Oestmann U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 Sbuject: Duane Arnold Energy Center Docket No: 50-331 Op. License No: DPR-49 Split Sample Audit
Dear Dr. Destmann:
The purpose of this-letter is to relay to your office information which will permit resolution of several open items from the routine in--
spection of August 5 thru 8, 1985.
Enclosed is an Inter-office memo from Alex Feldman, Radiological Engineer to Mr. Herb Giorgio, Radiation Protection Supervisor which ad-dresses each of the remaining open items.
If you have any questions regarding this material, please feel free to contact either myself. or Lou Kriege at extension 291.
Sincerely, H
L 24 Daniel L. Mineck Plant Superintendent - Nuclear DLM/AF/hc e603180140 86022/
PDR ADOCK 05000331
' Attachments o
PDR-cc:
A. Feldman R. McGaughy y
K. Young Q
H. Giorgio W. Miller i\\
File: NRC-4, A-103 MAR "3 1986
. General Ofce
- ID. Ikg 331
- Cedar llapids, Iowa 52406
- 319/398-4411
o
?.
., g February 7,1986 TO:
Herb Giorgio Radiation Protection Supervisor Lou Kriege Chemistry Coordinator Ralph Lewis Chemsitry Foreman FROM:
Alex Feldman Rad Engineer
SUBJECT:
Resolution of Open Items from the Routine Safety Inspection Conducted by Drs. M.J. Destmann and R.B. Holtzman on August 5 thru 8, 1985 FILE:
NRC-4 Several items remained opened after the inspection which are addressed be-low. They are:
Item No.
Subject 50-331/83013-02:
Laboratory Ventilation 50-331/85019-01:
Strontium and Tritium Analysis 50-331/85019-02:
Kr-85m Analysis 50-331/8b019-03:
Mn-56 Analysis 50-331/85019-04:
Technician discussion of Analysis 50-331/85019-05:
As-76 Analysis 50-331/85019-06:
Additional Analysis NRC EXCERPT:
(0 pen) Open Item (50-331/83013-02):
Inadequate ventilation in labor-atory and sample hoods - a third finding in a licensee internal audit (I-82-28). A Design Change Package has been received at the plant to modify the existing ventilation system. However it has been placed on a low priority since it was discovered that to modify the existing ventilation system, workers would have to cut through asbestos material.
Licensee representatives were unable to provide the inspectors any information as to when the work would be started or completed until
.o NRC Open Item -
the problem of the toxicity of the asbestos taaterials solved. This item remains open pending completion of the necessary modifications to provide adequate ventilation in the laboratory and fume hoods.
RESOLUTION:
DCP # 1286 is presently on hold because asbestos has been found in the work area.
Iowa Electric is pursuing the removal of the asbestos and hopes to have the problem resolved in June or July of 1986. DCP
- 1286 will require approximately three (3) months work after the asbestos removal. Consequently, it should be done by the end of October,1986.
NRC EXCERPT:
Samples collected for the confirmatory measurements program were off gas, a charcoal adsorber, reactor coolant liquid, an air particulate filter, and liquid radwaste, and analyzed by both the licensee in his laboratory and by the NRC inspectors using the Region III Mobile Lab-oratory. The results of the NRC-licensee comparisons are given in Table-1 with comparison criteria presented in Attachment 1.
The liquid radwaste sample was filtered through a 0.45 tm membrane filter to re-move solids (mainly spent resin fines) from the liquid prior to the split with the licensee. The licensee agreed to analyze the split filtered sample for gross bata, h-3, Sr-89, and Sr-90. The results will be compared with those from the NRC Reference Laboratory, the Radiological Environmental Sciences Laboratory (RESL), and will be included in an addendum to this report (0 pen Item 50-331/85019-01).
RESOLUTION:
The liquid radwaste sample referenced above was analyzed on-site for gross beta and tritium activity.
The Strontium 89 and 90 analysis were done by Teledyne Labs. The results of all the analysis was sent to the NRC under cover letter DAEC-85-0899, dated November 20, 1985.
Subsequent discussions with Dr. Holtzman over the phone indicate that the NRC and DAEC reported values are in agreement.
NRC EXCERPT:
The licensee had 27 agreements out of 30 comparisons. Two additional nuclides (I-131 in the primary reactor coolant and Cs-137 in the liquid waste) were detected, but because of poor counting statistics, no com-paritons were made. The comparison of Kr-85m in the off gas sample was in disagreement (67% of the NRC value). The ifcensee attributed this low value to the use of the 151-key peak for Kr-85m. This energy is on the knee of the detector efficiency curve where two curves meet, and hence, this region is very sensitive to calibration errors. At the request of the inspectors, the spectrum was reanalyzed using a
NRC Open Item secondary peak at 305 kev and an agreement was achieved. This peak was not listed in the licensee library normally used for this analysis and thus was not available for the analyst to use for confirmation.
Had it been, the discrepancy at 151 kev should have been noted.
In a telephone discussion on this matter on August 21, 1985, licensee representatives agreed to examine their calibration in the 151-kev region and to add the 305-kev line to the library (0 pen Item 50-331/
85-019-02).
RESOLUTION:
Two actions have been taken to address this item.
First the Ortec system was recalibrated. This was done from December 1985 to Jan-uary 1986. Calibration curves were produced from sorption corrected mixed gama liquid sources which used a linear data fit from o to 130 Key and a quadratic data fit from 130 Kev to 2000 Kev. Secondly, the Kr-85m peaks have been reversed in the PARTIODI and 0FFGAS1 libraries.
They now list the Kr-85m data as follows:
4.48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> Kr-85m Half-Life
=
Kev Gama/D 304.470 14.0000 151.000 75.5000 NRC EXCERPT:
In the primary sample the short-lived (2.59 h) Mn-56 comparison agreed only efter the criterion was relaxed to the next higher acceptance range (Attachment 1). This adjustment was made to allow for the add-itional uncertainty introduced by correcting for the I-134 contribu-tion to the 847 kev peak used to quantify Mn-56. This adjusted value was consistent with the value obtained using a secondary peak at 1810 kev. This correction was not made by the licensee because the inter-fering 847 kev line for I-134 is not in the licensee's library and the discrepancy with the 1810-kev peak was not noted.
In the August 21 telephone discussion of this problem, licensee representatives agreed to review and detennine the need for change in their analysis for Mn-56.
(0 pen Item No. 50-331/85019-03).
RESOLUTION:
This open item has been resolved by modification of the RADWASTE1 and EFFLUENT 1 libraries.
Because the 847 Kev which is observed has a total area produced by both I-134 and Mn-56, the libraries have been modified
q.
NRC Open Item -
to read:
2.57 hours6.597222e-4 days <br />0.0158 hours <br />9.424603e-5 weeks <br />2.16885e-5 months <br /> Mn-56 Half-Life
=
Kev Gamma /D 1811.200 27.2000 846.600 99.0000 The modifications which have been made will ensure greater accuracy for the Kr-85m and Mn-56 activities which are reported. The cost of this increased accuracy is an increase in the MDA (LLD) levels. This is because the new primary peaks have a lower gamma /D value. Neither of these isotopes are listed as principle gamma emitters in the DAEC Technical Specifications and there is no specified LLD value.
NRC EXCERPT:
They also agreed to discuss the Kr-85m and Mn-56 problems and the im-portance of analyst intervention in such cases in a regular Friday training session with the chemistry technicians.
(0 pen Item No. 50-331/85019-04).
RESOLUTION:
The entire subject of operator interpertation of Ortec data was add-ressed at a Friday afternoon group meeting shortly after the NRC Exit interview.
In addition, a second Friday meeting was devoted to a re-view of the Ortec system analysis algorithym. This was documented with the training group.
F NRC EXCERPT:
The As-76 comparison was in disagreement because this nuclide was not in the licensee's library used in this analysis.
(It was in other licensee libraries). The licensee has agreed to include As-76 in his library for reactor coolant.
(0 pen Item No. 50-331/85019-05).
RESOLUTION:
As-76 has been inserted into the EFFLUENT 1, RADWASTEl, and PARIODI li-braries. They read as follows:
1.097 days As-76 Half-Life
=
y.
NRC Open Item -
Kev Ganna/D 559.100 44.7000 657.040 6.0800 NRC EXCERPT:
The filtered waste sample gave disagreement for Mn-54 when counted by the licensee in a two-liter Marinelli and again when recounted in a one-liter plastic bottle. Agreement for Co-60 was achieved both times. The cause for disagreement was not discovered; it may owe to differing effects of the settling of suspended particles on the dif-ferent licensee and NRC counting geometries. The licensee has agreed to analyze a spiked liquid sample from Ge NRC Reference Laboratory in an attempt to resolve this matter.
(0penItem 50-331/85019-06).
RESOLUTION:
A 10 mi vial of spike liquid was received from the Idaho Laboratory and analyzed. The results of the analysis were transmitted to the Region III Office in the letter of November 20th. Subsequent con-versations with Dr. Holtzman indicated that we were in agreement with Cs-137, but in disagreement with Co-60. Upon investigation the cause of the disagreement became apparent.
The RADWASTE1 library was used during this analysis. The library con-tains the isotopic data and the peaked background activity for each isotope (inBq.). The RADWASTE1 library normally uses the 2 liter Marinelli calibration file to compute the Baquerel activity of the background spectra. After the RADWASTE1 library was modified to use the 10 ml vial efficiency to compute the background activity, the pro-per Cobalt-60 activity was computed. The difference in the observed Co-60 activity was due to the different efficiencies for the 10 ml vial and the 2 liter Marinelli.
(See Attached Data) h Alex Feldman Rad Engineer AF/hc Attachment
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CFN1ROID ENERGY BAf h0F:00ND NET AREA INTENSITY UNCEPT FUHM Cl! Al>FE t I:l' V COUt:TS C O L'NT S CTE/SEC KEV 102;.02 511.00 23.
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7.467E-03 43.3 2.28 1022.02 511.00 23.
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7.447E-03 43.3 2.28 0.00 657.04 263.
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SUMMARY
OF NUCLIDEE IN SAMPLE ****************
TIME Or COUNT UNCEPTAINTY TIME CORRECTED UNCERTAINTY NUCLIDE A.CTIVITY COUNTING AC1IVITY COUNTING UC/ML t-2 SIGMA U C / M'.
+/- 2 SIGMA CD-60 1.861E-05 4/- 2.9E-06 2.141E-05
+/- 3.4E-06 CS-137 2.214E-05
+/- 3.1E-06 2.269E-05
+/- 3.2E-06 s * *
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