IR 05000155/1978011
| ML19281A216 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 01/03/1979 |
| From: | Essig T, Greer R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19281A213 | List: |
| References | |
| 50-155-78-11, NUDOCS 7903080457 | |
| Download: ML19281A216 (7) | |
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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
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Report No.
50-155/78-11 Docket 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 Site, Charlevoix, Michigan Inspection conducted: November 30 - December 1, 1978
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Inspector:
R. JY Greer
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T Approved by:
T.
. Essig, Chief I b 30 Environmental and Special Projects Section Summa ry :
Inspection on November 30, December 1, 1978 (Report No. 50-155/78-11)
Areas Inspected: Routine confirmatory measurements inspection including j
a discussion of the results from previous sample comparisons and collection of samples for future comparative analyses, including the submission of a spiked sample for analysis by the licensee. The inspection involved six inspector-hours onsite by one NRC inspector.
Results: No items of noncompliance or deviations were identified.
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7903080457
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DETAILS 1.
Persons Coatacted
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- T.
Brun, Chemistry and Radiation Protection Supervisor
- C.
Axtell, Plant Health Physicist
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D.
Rickertsen, Senior Chemistry Lab Technician
- C.
Hartmann, Plant Supervisor
- Denotes those present at exit interview.
2.
General This inspection consisted of a comparison of confirmatory measure-ment results of effluent samples analyzed by the NRC Reference Laboratory. Measurements made by the NRC Reference Laboratory are referenced to the National Bureau of Standards.
Effluent samples were also split with the licensee for future comparison under the Confirmatory Measurements Program.
The inspector also submitted a spiked particulate sample to the licensee for analvsis.
The inspector examined the sample holder for the particulate and charcoal filters to determine if sufficient leakage paths around the charcoal filter existed to explain the apparently low results.
The filter was observed to be against two rubber gaskets (one on each side of the filter), and no leakage path was obvious.
3.
Confirmatory Measurement Sample Results a.
Off Gas - For the gas sample collected in the second quarter of 1978, the licensee failed to detect Xe-133m.
This analysis was performed on the licensee's NaI system because the GeLi system was down for repair. The licensee's failure to detect Xe-133m is attributed to the fact that it was masked by short-lived radionuclides. The licensee has agreed to routinely hold gas samples and perform a second count at a later date.
b.
Liquid Waste - Analysis of the J iquid waste sample collected in the second quarter of 1978 was performed by the licensee on the GeLi system. All six analyses were in agreement with the NRC's Reference Laboratory.
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Particukite Filter - The licensee analyzed the particulate filter collected in the second quarter of 1978 on a NaI system. The licensee failed to detect Cr-51, Cs-134 and Zn-65.
Iodine-131 and Mn-54 were detected, but resulted in disagreements.
These problems were attributed to the fact that Cr-51 is masked by 1-131 on the NaI system, thus causing
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the peak identified as I-131 to contain the activity belonging to the chromium and causing the iodine results to be high, thus contributing to the disagreement for the iodine.
On the NaI system, Mn-54 masks Cs-134 and it therefore contains the activity attributable to both nuclides, causing the re-sult for manganese to be high and result in a disagreement.
Zinc-65 is masked on the sodium iodide system by Co-60; however, the 2n-65 was a no-comparison (resolution less than 3.0).
A particulate filter was also collected during the third quarter of 1978. However, all activity was below the lower limits of detectability, therefore, no comparisons could be made.
In response to an item noted in a previous inspection 1/
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inspector discussed the calibration standard used for the particulatgjfilter.
Based on sample results of the previous comparison-and of results of the licensee's in-house analysis of EPA standards, the licensee's analysis of particulate filters on the GeLi system appear to be high relative to the NRC's Reference Laboratory.
This problem was discussed with the licensee. During the period in question, the licensee was calibrating with a standard prepared by pipetting a known amount of activity into the bottom of a plastic Petri dish, drying the sample, and then wrapping it in plastic. The licensee prepared sources this way because problems had been experienced with corrosion in the previous standard which was prepared by depositing an acid solution onto a stainless steel planchet.
The licensee stated that the sources were flaking from the plastic Petri dish, and that the conservative correction factor used to account for the flaking was the most likely cause of the problem.
A different 1/ IE Inspection Report No. 50-155/78-03.
2/ Ibid.
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method of preparing the sources is presently being developed.
The efficiency calibration for the particulate filter does not support the high results since the same efficiency is used for the charcoal absorber and results for the com-parisons of the charcoal absorber tend to be low.
The inspector examined the licensee's procedure for efficiency
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calibration and noted no obvious problems.
At this time, the conservative correction factor used to account for flaking of the standard appears to be the reason the analyses on the particulate filter tend to be high.
d.
Charcoal Filter - On the charcoal filter collected during the second quarter of 1978, the licensee failed to detect Cs-137 and Hg-203, however, the former was a no-comparison.
On the cnarcoal filter collected during the third quarter of 1978, the licensee failed to detect Co-60, Cs-137, Mn-54, Hg-203 and Sn-113.
Of these five comparisons, the FM-54, Hg-203, Sn-ll3 were in the -disagreement category, and the other two were no-comparisons.
These analyses were performed on the licensee's GeLi system.
The failure to detect these ntelides was attributed to the fact that the licensee en-countered relatively high concentrations of Br-82, which would successfully mask Co-60, Cs-137, Mn-54, and Hg-203.
The licensee agreed to perform a second count on the charcoal filter at a later date to allow the Br-82 to decay. No ex-planation for the licensee's tailure to quantify Sn-113 was apparent after a review of the supporting data.
4.
Exit Interview The inspector met with licensee representatives denoted in Para-graph 1, at the conclusion of the inspection on December 1, 1978.
The purpose, scope and findings of the inspection w e discussed.
In response to certain remarks made by the inspector, the licensee agreed to:
a.
Routinely count both the off-gas and charcoal filter samples twice, the second count at a later date to allow short-livcd interfering nuclides to decay.
b.
Develop a new method for the preparation of the standard for calibration for the particulate filter.
Attachments:
1.
Table I, Confirmatory Measurements Program for second quarter of 1978.
2.
Table I, Confirmatory Measurements Program for third quarter of 1978.
3.
Attachment 1, Criteria for Comparing Analytical Measurements.
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TAELE I US NUCLEAR PEGULATORY CGMM I S S I O N OFFICE Cr INSPECTION AND E hF O R CE ME NT CONFIRMATORY NE A SUF E ME NT S PRCGP A M FACILITY: BIG POCK PT FeR T HE 2 OUA PTE R OF 1*7f
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--NRC--
--- NR C : L IC F h S E E - --
SAMPLE ISOTOPE RESULT ERROP RESULT FRROP PATIC P.ES T
GFF GAS
'X E 133 2 4E-0 3 7 0E-05 3 5E-03 3 7E-04 1 5E+00 3 4F+01 P
XE 133M 1.0E -0 3 2 0E-04
O.0
5 0E +00
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L WASTE BETA 2 3E-04 8 0E-06 2.SE-04 3 0E-06 1 2E +00 2 9 E + 01 A
SR E*
5 0E-07 1 0E-07 4 6E-07 1.0E-07 9 2E-01 5 0E+00 A
SP *0 2 0E-06 8 0E-0F 2 0 E -0 6 2 0E-07 1 0E+0C 2 2E+01 A
CS 137 2 2E-04 4 30-04 2 0 E -0 4 1 0E -0 6 9 1 E -01 3 5E +01 A
CC 60 2 3E-05 8 0E-07 3 1E-05 7 0E-07 1 3E +00 2.? E +01 P
P FILTEF. CR 51 4 5E-04 7 6E-05
00
5.t E +00 D
I 131 1 0 E -0 4
?.5E-05 4 6E-04 1 4E-05 4 6E+00 4 0E +00
CS 134 5.7E-05 7.?E-06
0.0
7 2E+00
CS 137 3 4E-04 1 7E-05 2 7E-04 1.1E-05 7. ? E -01 2 0 E + 01 A
MN 54 3 5E-05 7 0E-06 3 0F-04 1 2E-0 5 8 6E+00 5 0E +00
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2 5E +00 h
CO 60 1 1 E -0 4 1 4E-05 2 2E-04 1 0E-05 2 0E+00 7.5E +00 A
C FILTER CS 137 3 6E-05 1 4E-05
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2 6E +00 N
I 131 4.7E-03 1.*E-04 3 2E-03 4 0 E -0 5 6 8 E -01 2 5E + 01 F
H4103 6.4E-05 1 1E-05
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5 6E+00
- T TEST RESULTS:
A= AGREEMENT 0=0!S AGREE ME NT P = P O S S I BL E AGRE E MENT N=NO C O MP A R I SON
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TABLE T U S NUCLE AR REGUL ATORY COMMISSION
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OFFICE OF INSPECTIOh A ND E NC OR CE ME NT
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CONFIRM ATORY ME ASURE MENTS PROGR AM
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FACILITY: BIG ROCK PT
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FOR THE 3 DUARTER OF 1978
NRC-------
--L I C E N SE E -----
--NRC: LICENSEE----
SkKPLE ISOTOPE RESULT ERROR RESULT ERROR RATIO RES
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C HF ILTER HG 203 7.3E-05 1 3E-05
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5 6E+00
I 131 8 6E-03 3 0E-04 7 0 E -03 1.1E-04 8 1 E -01 2 9E+01 A
CO 60 3 2E-05 1 1 E -0 5
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2 9E+00 N
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2.iE +00 N
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0.0
4.1E+00
s:1 113 6. "2 E -0 5 1 3E-05
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4 8E+00
1eTEST RE S UL T S :
A= AGREEMENT D ual S AG RE E ME NT P wPO SS I BL E AGREEMENT
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N;ND COMPARISON
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ATTACICir.NT 1
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CRITERIA FOR COMPARING ANALYTICAL ME\\SilRDirNTS
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This attachment provides criteria for comparing results of capability tests and verificati9n measurements.
The criteria are based on an
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empirical relationship whi-h combines prior experience and the accuracy needs of this program.
'In these criteria, the judgment limits are variable in relation to the
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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 licensce'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 Laboratorf, 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.
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RESOLUTION RATIO = LICENSEE VALUE/NRC REFERENCE V!.LUE Possible Possible A rcement "A" Agreeable "B" AEreement J
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<3 No Comparison No Comparison No Comparison
>3 and <4 6.4 - 2.5 0. 3
- 3.0 No Comparison T4 and <8 0.5
- 2.0
- 0. 4
- 2.5 0.3
- 3.0 58 and <16 O.6 -
1.67 0.5
- 2.0 0.4
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2.5
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][16and<51 0.75 - 1.33 0.6
- 1.67 0.5
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2.0
>51 and <200 0.80 1.25 0.75 - 1.33 0.6
- 1.67
.][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:
Gamma spectrometry, here principal gamma energy used for identifi-cation is greater than 250 kev.
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Tritium analyses of liquid samples.
"B" criteria are applied to the following analyses:
Camma spectrometry, where principc1 gamma energy used for identifi-cation is less than 250 kev.
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Sr,-89 and Sr-90 determinations.
Gross beta, where samples are counted on the sam: date using the same reference nuclide.
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