IR 05000346/1980020
| ML19331C101 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse |
| Issue date: | 06/27/1980 |
| From: | Essig T, Januska A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19331C100 | List: |
| References | |
| 50-346-80-20, NUDOCS 8008140167 | |
| Download: ML19331C101 (4) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-346/ 80-20 Docket No. 50-346 License No. NPF-3 Licensee: Toledo Edison Company Edison Plaza 300 Madison Avenue Toledo, OH 43652 Facility Name: Davis-Besse Nuclear Power Station, Ur.it 1 Inspection At: Davis-Besse Site, Oak Harbor, Ohio h.
. [iuska WA A. G. J b
8" Inspector:
Approved By:
T. H. Essig, Chief G
Environmental and Special Projects Section Inspection Summary Inspection on June 5, 1980 (Report No. 50-346/80-20)
Areas Inspected: Confirmatory Measurements including:
telephone dis-cussion and closeout of results of a previous sample collection. The
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inspection involved 0 inspector-hours on site by one NRC inspector.
Results: No items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted D. Briden, Chemist and Health Physicist 2.
Results of Comparative Analyses Results of comparative analyses performed on samples split onsite in August, 1978, are shown in Table I.
The criteria for comparing measurement results are given in Attachment 1.
For seven sample com-parisons, the licensee's results yielded six agreements or partial agreements.
The licensee failed to accurately quantify gross beta in a liquid waste split sample.
In a discussion with the licensee, no reason for the disagreement wac apparent other than acknowledged differences in equipment and operating plateaus used by the Radiation Environmen-tal Sciences Laboratory (RESL), NRC's reference laboratory, and the licensee. Beta counting is not required by his effluent Technical Specifications and is used mainly as a quality assurance check to determine trends and identify problems.
Attachments:
1.
Table I, Confirmatory Measurements Program, Davis-Besse.
2.
Attachment 1, Criteria for Comparing Analytical Measurements.
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TABLE I U S NUCLEAR REGULA TORY COMMISSION OFFICE OF INSPEC TION A ND E NF O RCE ME N T C ONF I P.M A T OR Y ME ASUREMENTS PROGR AM FACILITY: C1VIS BESSE FOR THE 3 QUARTER OF 1978
NRC--
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---NRC : L ICE N S E E ----
S A MP LE ISOTOPE RESULT ERROR RESULT ERROR RATIO RES T
LeWASTE H 3 2.4E-02 2 0E-04 2 4 E -0 2 5 3E-05 1 0E+00 1 2E+02 A
GETA 8 5E-06 3 0E-07 1 7E -0 4 4 5E-06 2 0E +01 2 8E +01
CO 58 4 3E-04 1 2E -0 5 5 1E-04'
3 2E-06 1 2E+00 3 6E +01 A
MN 54 6 6 E -0 5 2 i O E -0 6 7 7E-05 1 4 E -0 6 1 2E+00 3 3E+01 A
FE So
'.1 E -0 5 7 8E-07 1 3E-05 1.6E -0 6 1 2E+00 1 4E+01 A
CO 60 2 6E-05 8 9E-07 3 6E-05 1 1E-06 1 4E+00 2 9 E + 01 P
UFF GAS XE 133 1 1E-03 4 0E-05 1 1 E-03 1.8E-05 1 0E +0 0 2 8 E + 01 A
T TEST RESULTS:
A= AG REEME N T D wD I S A G REE ME N T PwPOSSIBLE AGREEMENT MmHO. C OMP A R I SDN
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ATTACHMENT 1 l
CRITERIA FOR COMPARING ANALYTICAL MEASUREMENTS This attachment provides criteria for comparing results of capability tests and verification measurements.
The criteria are based on an
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empirical relationship which combines prior experience and the accuracy
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needs of this program.
In these criteria, the judgment limits are variable in relation to the comparison of the NRC Reference Laboratory's value to its associated one sigma uncertainty. As that ratio, referred to in this program as
" Resolution", increases, the acceptability of a licensee's measurement should be more selective. Conversely, poorer agreement should be con-sidered acceptable as the resolution decreases. The values in the ratio criteria may be rounded to fewer significant figures to maintain statistical consistency with the number of significant figures reported by the NRC Reference Laboratory, unless such rounding will result in a narrowed category of acceptance. The acceptance category reported will be the narrowest into which the ratio fits for the resolution being used.
RESOLUTION RATIO = LICENSEE VALUE/NRC REFERENCE VALUE Possible Possible Agreement Agreement "A" Agreeable "B"
<3 No Comparison No Comparison No Comparison 3.0 No Comparison
>3 and <4 d.4 - 2.5 0.3
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3.0
>4 and <8 0.5 - 2.0 0.4
- 2.5 0.3
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2.5 1.67 0.5
- 2.0 0.4
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T8 and <16 0.6
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2.0 T16 and <51 0.75 - 1.33 0.6
- 1.67 0.5
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1.67 551 and <200 0.80 - 1.25 0.75 - 1.33 0.6
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1.33
][200 0.85 - 1.18 0.80 - 1.25 0.75
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"A" criteria are applied to the following analyses:
Gamma spectronetry, where principal gamma energy used for identifi-cation is greater than 250 kev.
Tritium analyses of liquid samples.
"B" criteria are applied to the following analyses:
Gamma spectrometry, where principal gamma energy used for identifi-cation'is less than 250 kev.
Sr,-89 and Sr-90 determinations.
Gross beta, where samples are counted on the same date using the saae reference nuclide.
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