IR 05000010/1976009
| ML19340A798 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 06/17/1976 |
| From: | Oestmann M, Pagliaro J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19340A797 | List: |
| References | |
| 50-010-76-09, 50-10-76-9, 50-237-76-11, 50-249-76-10, NUDOCS 8009040613 | |
| Download: ML19340A798 (8) | |
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U. S. NUCLEAR RE'GULATORY CO!CIISSION
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OFFICE OF INSPECTION AND ENFORCEMENT
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REGION III
Report of Confirmatory Measurements Inspection IE Inspection Report No. 050-010/76-09 IE Inspection Report No. U50-ta, fro-Al IE Inspection Report No. 050-249/76-10 Licensee:
Commonwealth Edison Company Post Office Box 767 Chicago, Illinois 60690 Dresden Nuclear Power Station License No. DPR-2 Units 1, 2, and 3 License No. DPR-19 Morris, Illinois License No. DPR-25 Category: C
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Type of Licensee:
BWR (GE) (Unit 1) - 700 MWt (Unit 2), 2527 MUt (Unit.' - 2527 Mh't
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Type of Inspection:
Routine, Announced Dates of Inspection:
May 26-27, 1976
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Principal Inspector :
M. J. Oestmann (Date)
Accompanying Inspectors: None Others Accompanying Personnel: None
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Reviewed By:
J A.PagMaro ie Environmental and Special (Date)
Projects Section 800904'O $
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SUMMARY OF FINDINGS
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Inspection Summary Routine, announced confirmatory measurements inspection conducted May 26 and 27, (Unit 1, 76-09); (Unit 2, 76-11); and (Unit 3, 76-10) :
reviewed and discussed results of comparative analyses of previous effluent radiological sample collection; and~ collected new effluent samples for subsequent comparative analysis.
Enforcement Items None.
Licensee Action on Previously Identified Enforcement Items No previously identified enforcement items within the scope of this inspection.
Other Significant Items A.
Systems and Components
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No significant items identified.
B.
Facility Items (Plans and Procedures)
The licensee agreed to determine the concentration of Xe-133m in off-gas samples.
(Paragraph 4, Report Details)
C.
hanagerial Items
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No significant items identified.
D.
Noncomp'iance Identified and Corrected by Licensee None.
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Deviations None
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Status of Previously Reported Unresolved Items No previously reported unresolved items within the scope of thir. inspection.
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Hpnagement Interview
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- A management interview was conduc'ted with Messrs. B. B. Stephenson, D. Adam, G. Eergan, and F. Willeford on May 27, 1976. The following items were discussed with the licensee representatives:
A.
The NRC inspector discussed the scope and intent of this specific inspection.
(Paragraph 2, Report Details)
B.
The results of the comparative analysis performed pursuant to this inspection were reviewed, with emphasis on the results not yielding an acceptable comparison.
(Paragraph 4, Report Details)
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i REPORT DETAILS _
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Persons Contacted I
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B. B. Stephenson, Station Superintendent, Dresden D. Adam, Radiation Chemistry Supervisor, Dresden G. Bergan, Plant Chemist, Dresden R. Colby, Chemical Engineer, CE Technical Center L. Shearer, Plant Chemist, Dresden T. Sasgen, Rad-man, Dresden 2.
General
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The licensee is required to measure the quantities and concentrations of radioactive material in effluents from his facility to assure that they are within the limits specified in his license and NRC regulations.
This inspection consisted of a test of the licensee's capabilities of l
measuring the radioactivity content in actual samples of his
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effluents. The test consists of comparing the licensee's measure-ments with those of the NRC reference laboratory. The two laboratories make measurements on the same samples, or on duplicates or splits of the same sample. The measurements made by the NRC l
laboratory are referenced to the National Bureau of Standards'
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l Radioactivity Measurements System by laboratory intercomparisons.
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A set of liquid, off-gas, particulate filter and charcoal adsorber I
samples was obtained by the inspector, the results of which will
be examined during a subsequent inspection.
3.
A.ialvtical Results
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This inspection showed some of the licensee's measurements on these samples obtained in January 1976 are acceptable under the test criteria used (see the Attachment) by the Office of Inspection
and Enforcement for comparing measurements results. Some of the licensee's ecasurements, however, are not acceptable under the
test criteria. The types of samples tested and the results of the
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measurements were as follows:
a.
' Type of Sample: Liquid Waste (1/76)
(Results. in units of uCi/ml)
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ACCEPTABLE
Radionuclide NRC Reference Measurement Licensee's Measurement
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Gross Beta 1.23 + 0.04 E-06 1.4 E-06
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Co-60 4.3[0.2 E-06 4.3 E-06
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NOT ACCEPTABLE
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None.
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Type of Sample: Off-gas (1/76)
(Results in units of uCi/ml)
ACCEPTABLE Radionuclide NRC Reference Measurement Licensee's Measurement Xe-133 2.39 + 0.02 E-03 2.9 E-03 Xe-135 5.7{0.5 E-02 6.9 E-02 NOT ACCEPTABLE Radionuclide NRC Reference Measurement Licensee's Ifeasurement Xe-133m 3.7 1 0.3 E-04 Not Identified c.
Type of Sample: Particulate Filter (1/76)
(Results in units of uCi/ sample)
ACCEPTABLE
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Radionuclide NRC Reference Measurement Licensee's !!easurement Co-60 2.2 1 0.2 E-04 1.8 E-04 I-131 6.3 1 0.3 E-04 6.2 E-04 Ba-140 5.1 1 0.2 E-03 3.5 E-03 NOT ACCEPTABLE Radionuclide NRC Reference Measurement Licensee's l!easurement Cs-137 1.0 1 0.1 E-04 4.1 E-05 Ce-141 3.0 1 1 E-05 Not Identified Hn-54 3.0 1 1 E-05 Not Identified d.
Type of Sample: Charcoal Adsorber (1/76)
(Results in units of uCi/ sample)
ACCEPTABLE Radionuclide NRC Reference Measurement Licensee's Measurement I-131 2.17 1 0.1 E-03 3.4 1 0.9 E-03 NOT ACCEPTABLE None.
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4.
Samples Not Meeting Acceptance Criteria a.
Particulate Filter The licensee's reported results on analyses of the particulate filter sample for Cs-137 yielded a comparison in the unacceptable category when compared with the reported results of the NRC reference laboratory. Both laboratories re-examined original records, methods and reported results, finding no likely bases for the reported difference in the results. The inspec tor also examined the original gamma spectra and discussed this analysis with licensee personnel.
The licensee on this occasion reported the radioactivity level of Cs-137 on a particulate filter which was 40% lower than the value reported by the NRC reference laboratory. If this difference is real and representative of routine analysis, the licensee could have underreported releases of this nuclide near the time of this comparison. On three previous particulate filter comparisons made in 1974 and 1975, the licensee reported values for Cs-137 yielding acceptable comparisons.
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In addition, the licensee did not observe any Mn-54 or Ce-141 radioactivity present in the particulate filter although the NRC reference laboratory reported results slightly above the lower limit of detection with an error of 33%. At the previous inspection the licensee found un-54 at the lower level of detection; but the NRC reference laboratory did not report any Mn-54 present. At this inspection the total amount of Cs-137, Mn-54, and Ce-141 found, however, represented enly 2.6% of the total radioactivity present on the particulate filter. This media and analyses for Cs-137, Mn-54, and Cc-141 will be re-examined during a subsequent inspection.
The NRC reference laboratory also reported the activity level of La-140 found on the particulate filter and the licensee noted the presence of this nuclide but no comparison is aade because of the decay correction problems.
The inspector noted the licensee successfully analyzed for three other nuclides and in particular Co-60 on the particulate The previous inspection / had yielded an unacceptable l
filter.
comparison for Co-60 in this media.
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IE Inspection Reports Jo. 050-010/76-03; No. 050-237/76-02 and No. 050-249/76-02.
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b.
Charcoal Cartridge Samples The licensee reported an acceptable result for the I-131 present on the charcoal cartridge in comparison with the NRC reference laboratory results. The previous inspection /
yielded an unacceptable comparison for this nuclide and media, c.
Off-Cas Sampics The licensee's results on analysis of off-gas sample for Xc-133 and Xe-135 were found to be acceptable in comparison with the NRC reference laboratory results. The licensee, however, did not report the presence of Xe-133m as did the NRC reference laboratory. The inspector examined the original gamma spectra showing the presence of Xe-133 and Xe-135, but no Xe-133m could be identified. The licensee stated that he would count subsequent off-gas samples again a week later after the 9.14 hour1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> Xe-135 has decayed away to avoid interference from detecting Xe-133n. The results of analysis for this nuclide and media will be re-examined during a subsequent inspection.
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d.
Liquid Waste
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Tr'. tium samples are not being compared at this time since the licensee has not completed his analysis of the liquid waste sample. Comparison of the results of the analysis for tritium in liquid waste will be reported in a sub-sequent inspection report.
- Attachment:
Attachment 1, Criteria for Comparing Analytical Measurements 2/
Ibid.
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ATTA.C_11.' ll.t.l.T _1
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CRITERI A TOR Cn!!!'ARING A lA1.YTICA1. !1 EAST:RI'.!!!:UTS
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Thi:. a L t achment 'provi der. cr i t eria for comparinn renn]Ln of capability
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tents aiul verification meanurementr..
The criteria are ba:,ed on an empirical relationship which combinen prior experience and the accuracy needs of thin program.
In thene crite.i:.c"the judgement Jimits are variabic in re]ation to the comparinon of the !!RC Heference I.abora tory's value to i t:, ar.nociated uncertainty.
As that ratio, referred to in t hif, program an " Rentation" increases the acceptability of a licennec', measurement should be more
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selective.
Converncly, poorer agreement must be connidered acceptable as the resolution decreanes.
RES01.UT10!!
RATIO = LICE:!SEE VALUE/::RC REFERE: CE VALUE Posuihle Possihic
r, Agreement Acreencut A
',,reement B
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3.0 No Compari con -
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2.0 0.4
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1.66 0.5
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1.33 0.6
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2.0 51 - 200 0.80.-
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1.33 0.6 - 1,66 200 0.85 -
,1,18 0.80 - 1.25 0.75 - 1.33
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"A" criteria are applied to the following analyses.
Camna Spectreretry where principal canna energy used for identifi-cation is greater than 250 Kev.
Tritium analysen of liquid samples.
"B" criteria are applied to the following analyses:
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Gamna spectrometry where principal gamma energy used for identification it. Ics. than 250 Kev.
89Sr and 90Sr Determinations.
Cronn Beta where samples are counted on the same dat'c using the
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same reference nuclide.
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