IR 05000155/1980008
| ML19344F167 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 08/01/1980 |
| From: | Essig T, Januska A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19344F166 | List: |
| References | |
| 50-155-80-08, 50-155-80-8, NUDOCS 8009120509 | |
| Download: ML19344F167 (4) | |
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U. S. NUCLEAR REGULATORY COMMISSION
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OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
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Report No. 50-155/80-08
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bocket No. 50-155 License No. DPR-6
%licensee: Consumers Power Company 212 West Michigan Avenue Jackson, MI 49201 Facility Name: Big Rock Point Nuclear Plant Inspection At: Big Rock Point, Charlevoix, MI Inspection Conducted:. June 11 and 26, 1980 Sft[60 Inspector:
A. G. Janusra Approved By:
T. H. Essig, Chief 6fs[80 Environmental and Special Projects Section Inspection Summary
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Inspection on June 11 and 26, 1980 (Report No. 50-155/80-08)
Areas Inspected: Confirmatory Measurements including:
telephone discussion and closeout of results of a previous sample collection. The inspection involved 0 inspector-hours onsite by one NRC inspector.
Results: No items of noncompliance or deviations were identified.
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.8009120 68 f
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DETAILS 1.
Persons Contacted (Telephonically)
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C. Axtell, Plant Health Physicist I
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G. Fox, Chemistry and Radiation Protection Supervisor
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- g Results of Comparative Analyses Results of comparative analyses performed on samples split onsite in December 1978 are shown in Table I.
The criteria for comparing measure-ment results are given in Attachment 1.
For 16 sample comparisons, the licensee's results yielded 14 agreements or partial agreements.
The licensee failed to identify Cs-134 and Zn-65 on a particulate filter.
In reviewing the data from the analysis, the licensee could not determine the reason for the failure to identify these nuclides.
If the licensee's results were representative of releases during this period, the semiannual reported values would have been nonconservative.
Using the NRC's contractors values for the nuclides mentioned above to adjust the licensee's reported values would increase the reported releases to approximately 1.1 E-02 percent of the licensee's Technical Specification limit.
Enclosures:
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Table I, Confirmatory
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Measurements Program 2.
Attachment 1, Criteria for Comparing Analytical Measurements
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TABLE !
US NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION A ND E NF O RC E M E N T h
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CONF IR M A TOR Y MF A SUREMENT S PR OGR A M
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FACILITY BIG ROCK P1 yt.
FOR THE 4 OUARTER Or 1978
NRC-------
---NRC t L IC E N S E E----
AMPLE ISOTOPE RESULT FFLOF F.F90LT ERROR RATIC RE S T
FILTFP 1 131 4 Q E -0 3 1.gr_oc 3.g. E _n 3 S e 5 E -0 5 6 9 E -01 2e6E+01 P
FIL1ER CR 51 9 5E-04 1.0E-04 7.? E -D 4 1 5E-04 7 7E-01 9 5E +00 A
I 131 3 5F-04 3 5F-05 2 3 E -0 4 2 6E -0 5 6 6E-01 1 0E +01
'A 8A 140 3 3 E -0 3 1 6E-04 2 e ? E -0 3 1.9 E -0 4 7 0E-01 2.1 E + 01 F
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8 7E+00 D
CS 137 3 6E-04 1 e 8E -0 5 4 2 E -04 2e6E-35 1 2E+00 2 0E +01 A
2N 65 1 0 E -0 4 2 2E -0 5 D e0
00 4 5E +00 D
CO 60 1 2 E -0 4 1 8E-05 1 1 L -0 4 2 1 E -0 6 9 2 E -01 6 7E +00 A
FF GAS XF 133 1 6E-33 S e0E -05 2 9 E -0 3 1 6E-05 1 3E+00 3 2E +01 P
WASTE BETA 1 1E-03 4 0E -05 1 3 E -0 3 2 5E-0 6 1 2E +00 2 8E +01 A
SR 89 2 0E-06 1 0E-07 1 1 E -0 6 1 0E -0 7 5 5E -01 2 0E +01'
P SR 90 8 0E-07 Se0E-08 1 1 E -06 1 0E -07 1 4E+00 1 6E +01 P
CS 134 1 0E-04 3 6E-06 1 0E-04 8 9 E -0 7 1 0E+00 2 8E +01 A
CS 137 1 1E-03 3 0E-05 1 0E -0 3
?. 2 E -0 6 9 1E-01 3 7E +01 A
MN 54 1 8E-05 1 2E-06 9 4 E -06 4 3E-0 7 S e 2E -01 1 5E +01 P
CO 60 6 6 E -0 5 2 6F-06 6 0 E -0 5 7 6E-07 1 0E +00 2 5E +01 A
TEST RESULTS t
= A G R E E ME N T l
=01 S AGRE E ME NT l
=POSSIBLE AGREE ME NT
=NO COMP AR IS0N
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ATTACHMENT 1
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CRITERIA FOR COMPARING ANALYTICAL MEASURI'MENTS 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 e.cperience and:the accuracy
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needs of this program.
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" 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
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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
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Possible Possible Agreement Agreement "A" Agreeable "B"
<3
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No Comparison No Comparison No Comparison 2.5 0.3
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>3 and <4 d.4
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3.0 2.0 0.4
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2.5 1.67 0.5
- 2.0 0.4 78 and <16 0.6
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2.0 1.67 0.5 716 and <51 0.75 - 1.33 0.6
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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 spectrometry, 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.
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Gross beta, where samples are counted on the same date using the same reference nuclide.
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