IR 05000263/1975006
| ML20024G062 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 04/24/1975 |
| From: | Januska A, Jorgensen B, Pagliaro J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20024G058 | List: |
| References | |
| 50-263-75-06, 50-263-75-6, NUDOCS 9102070496 | |
| Download: ML20024G062 (6) | |
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l U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
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REGION III
Report of Independent Measurements Inspection IE Inspection Report No. 050-263/75-06
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Licensee:
Northern States Power Company 414 Nicollet Mall Minneapolis, Minnesota Monticello Nuclear Generating Plant License No. DPR-22 Monticello, Minnesota
. Category:
C Type of Licensee:
BWR (GE) 545 MWe Type of Inspec. tion:
Routine, Announced Dates of Inspection:
April 2-4, 1975 J
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Dates of Previous Inspection: March 11 -- 14,1975 (Operations)
b 4411t-f Principal Inspector:
B. L. 'J orgensen Ye
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p Q4u.Ls 12W Accompanying Inspector:
A. [J nuska
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Other Accompanying Person -1:
None.
Reviewed By:
J A. Pagliar O
7d Senior Environmental Scientist
'(Date'/
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Environmental and Special
Projects Section 9102070496 750428 PDR ADOCK 05000263 Q
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SU)etARY OF FINDINGS
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Enforcement Action: None.
Licensee Action on Previously Identified Enforcement Matters No previously identified enforcement items within the scope of this inspection Unusual Occurrences: None within the scope of this inspection.
Other Significant Findings A.
Current Findings This inspection consisted of an evaluation of the licensee's per-formance in analysis of radioactivity in effluent sampics. The licensee's results have yielded S3% Agreements or Possible Agreements and 17% Disagreements when compared to the rea: 1ts of the NRC reference laboratory.
B.
Status of Previously Reported Unresolved Items do previously reported unresolved items within the scope of this inspection.
Management In' erview
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t A management interview was held with Messrs. Larson, Anderson and Eliason. The following items were discussed with licensee representatives.
A.
The NR'C inspectors discussed the scope of this specific inspection and the results of compcrative measurements.
(Paragraphs 2 and 3, Report Details)
B.
The inspectors discussed the result yielding an " Unacceptable" comparison. No apparent cause for the discrepancy was identified.
(Paragraph 4, Report Details)
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REPORT DETAILS
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1.
Persons Contacted C. Larson, Plant Superintendent W. Anderson, Superintendent of Operations L. Eliason, Radiation Protection Engineer R. Jacobson, Plant Chemist E. Wright, Radiation Technician 2.
General The licensee is requircd 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 measurements of radioactivity in actual samples of his effluents.
The test consists of comparing the licensee's measurements with those of the NRC's reference laboratory.
The two laboratories make measurements on the same sampics, or on duplicates or splits of the same samples. The measutements made by the KRC's reference laboratory are referenced to the National Bureau of Standards radioactivity measurements system by Jaboratory intercomparisons.
3.
Analytical Results This inspection showed some of the licensee's measurements on these samples are acceptable under the test criteria used by the Office of Inspection and Enforcement for comparing measurements results (see the Attachment).
However, some of the licensee's measurements are not acceptable under the test criteria. The types of samples tested and the results of measurements were:
a.
Type of Sample:
Off-gas (10/74)
(Result in units of pCi/ml)
ACCEPTABLE Fadionuclide NRC Reference Measurement Licensee's Measurement Xe-133 2.88 1 0.08 E-01 2.98 1 0.01 Es01 NOT ACCEPTABLE:
None.
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b.
Type of Sample:
Particulate Filter (9/74)
(Result in units of uCi/ sample)
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ACCEPTABLE _
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Radionuclide NRC Reference Measurement Licene 3's Measurement
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Cs-137 3.00 + 0.07 E-03 2.37 + 0.05 E-03 Cs-134 1.31 1 0.05 E-03 1.45 _+ 0.04 E-03 Co-60 1.8 + 0.1 E-04 2.85 1 0,31 E-04 NOT ACCEPTABLE Radionuclide NRC Reference Measurement Licensec's Measurement
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Ba-140 5.2 10.5 E-03 1.31 1 0.08 E-02 c.
Type of Sample:
Charcoal Adsorber (9/74)
(Results in units of pCi/ sample)
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ACCEPTABLE Radionuclide NRC Reference Measurement Licensee's Measurement 1-131 2.18 + 0.05 3.49 + 0.02
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u NOT ACCEPTABLE: None.
4.
Samples Not Meeting Acceptance Criteria The licensee's reported result on analysis of a particulate filter for Ba-140 has yielded an " Unacceptable" comparison. Discussions with the licensee and with the refercuee laboratory did not provide information to indicate a probable cause for the discrepancy.
The licensee's results is a factor of about 2.5 times larger than that reported by the reference laboratory.
If this difference is real and representative of routine licensee analyses, the licensee may have over-reported releases of this nuclide near the time of this comparison. The licensee analysed a particulate filter with acceptable results for Ba-140, during a previous comparison. This analysis will be re-examined during a cubsequent inspection.
Attachment:
Attachment 1-4-
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ATTACEMENT 1 CRITERIA FOR COMPARING ANALYTICAL MEASUREMENTS This attachment provides criteria for comparing results of capability tests and verification measurements.
The criteria are based on an empirical relationship which combines prior experience and the a
REGION lit 199 AOOSEVELT RO AD CLEN ELLYN. ILLINOl5 60137
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IE Inspec ion Report No. 050-263/75-06 A ril 28, 1975
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P Transmittal Date
Distribution:
Distribution:
IE Chief, FS6EB IE Chief, FS&EB IE:llQ (5)
IE:HQ (4)
nn c#ntrni Fi lec:
L:D/D for Fuels & Materials Regulatory Standards (3)
DR Central Files Licensing (13)
IE Files IE Files IE Chief, M6FPB L:D/D for Reactor Project B.
IE Inquiry Report No.
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Transmittal Date
Distribution:
Distribution:
IE Chief, FS6EB IE Chief, FS&EB s
IE:llQ (5)
IE:llQ
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DR Central Files DR Central Files Regulatory Standards (3)
IE Files Licensing (13)
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IE Files
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Incident Notification From:
(Licensee 6 Docket No. (or License No.)
Transmittal Date
Distribution:
Distribution:
IE Chief, FS6EB IE Chief, FS6EB lt.:HQ (4)
IE:HQ (4)
Licensing (4)
L:D/D for Fuels 6 Materials DR Central Files DR Central Files IE Files IE Files otut g
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- 7/6 1916 F
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