IR 05000309/1979001
| ML19305A281 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 01/23/1979 |
| From: | Kottan J, Stohr J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19305A282 | List: |
| References | |
| 50-309-79-01, 50-309-79-1, NUDOCS 7903120528 | |
| Download: ML19305A281 (4) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No. 50-309/79-01 Docket No. 50-309 Li ense No. DPR-36 Priority
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Category C
Licensee:
Maine Yankee Atomic Power Company 20 Turnpike Road Westborough, Massachusetts 01581 Facility Name: Maine Yankee Nuclear Power Station Inspection at: Wiscasset, Maine Inspection conducted: Ja uary 12, 1979 Inspectors: Z dE (r &
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J. J. Kottan, Radiation Specialist
/date/ signed date signed date signed
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~7 9 Approved by:
e J.
./StohF, ' Chief, Environmental and (date signed S cial Projects Section, FF&MS Branch Inspection Summary:
Inspection on January 12, 1979 (Report No. 50-309/79-01)
Areas Inspected: This report contains the results of an effluent sample split between the licensee and NRC:I during a previous inspection on August 8-10, 1978.
The comparison of these results involved no onsite time.
Results: Within the area inspected, no items of noncompliance were observed.
790312052E Region I Form 12 (Rev. April 77)
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DETAILS 1.
Persons Contacted D. Sturniolo, Chemistry and Health Physics Supervisor J. Stevens, Technical Assistant 2.
Confirmatory Measuremer.ts In a pre';icus inspection conducted on August 8-10, 1978, Inspection Report 50-309/78-12 a liquid effluent sample was split with the licensee and NRC:I. Analyses were performed by the licensee using his nornal methods and procedures, and the NRC:I analyses were performed by the Department of Energy's Radiological and Environ-mental Services Laboratory (RESL). The comparison of the analyses results indicated that all of the measurements were in agreement or possible agreement under the criteria used for comparing results (see Attachment 1) with the exception of the gross beta measurement.
The inspector discussed the disagreement with the licensee. The disagreement may be due to the fact that the NRC sample was analyzed for gross beta approximately four months after the licensee's analysis, permitting the decay of short lived isotopes.
I-131, which has an eight day half life was present in the initial sample.
(See Inspection Report 50-309/78-12, Table I).
In addition, the inspector noted that the disagreement was in a conservative direction and would not have resulted in the licensee possibly exceeding any effluent release limits. The results of the comparisons are presented in Table I.
No items of noncompliance were identified.
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Exit Interview The inspector discussed the results of this inspection in a tele-phone conversation on January 12, 1979 with the licensee representa-tive denoted in Paragraph 1.
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TABLE I MAINE YANKEE VERIFICATION TEST RESULTS
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SAMPLE IS0 TOPE NRC VALUE LICENSEE VALUE COMPARISON RESULTS IN MICR0 CURIES PER MILLILITER Test Tank gross beta (4.2+0.3)E-7 (3.72+0.06)E-6 Disagreement 8/8/78
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2045 hrs.
H-3 (8.2110.02)E-3 (8.0610.05)E-3 Agreement Co-58 (1.8610.13)E-6 (1.4110.42)E-6 Agreement Note: The sample was also analyzed for gross alpha, Sr-89 and Sr-90, but these isotopes were not detected in the sample by RESL.
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Attachment 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 accuracy needs of this program.
In these criteria, the judgement limits are variable in relation to the comparison of the NRC Reference Laboratory's value to its associated uncertainty. As'tnat ratio, referred to in this program as " Resolution",
increases the acceptability of a licensee's measurement should be more selective.
Conversely, poorer agreement must be considered acceptable as the resolution decreases.
LICENSEE VALUE RATIO = NRC' REFERENCE VALUE Passible Possible Resolution.
Agreement Agreement A Agreement B
<3 0.4 - 2.5 0.3 - 3.0 No Comparison
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4-7 0.5 - 2.0 0.4 - 2.5 0.3 - 3.0 8 - 15 0.6 - 1.66 0.5 - 2.0 0.4 - 2.5 16 - 50 0.75 - 1.33 0.6 - 1.66 0.5 - 2.0 51 - 200 0.80 - 1.25 0.75 - 1.33 0.6 - 1.66
>200 0.85 - 1.18 0.80 - 1.25 0.75 - 1.33
"A" criteria are applied to the following analyses:
Gamma Spectrometry where principal gamma energy used for identification is greater than 250 Kev.
Tritium analyses of liquid samples.
Iodine on absorbers
B" criteria are applied to the following analyses:
Gamma Spectrometry where principal gamma energy used for identification is less than 250 Kev.
39Sr and 90Sr Determinations.
Gross Beta where samples are counted on the same date using the same reference nuclide.
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