IR 05000155/1976020
| ML20002D516 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 11/11/1976 |
| From: | Conaughton K, Gibson G, Pagliaro J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20002D513 | List: |
| References | |
| 50-155-76-20, NUDOCS 8101210283 | |
| Download: ML20002D516 (10) | |
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'l UNITED STATES, NUCLEAR REGULATORY Com!ISSION-OFFICEOFINSPECTIONANDENFORCEMENT]
REGION III
T. Report of Confirma, ry Measurements Inspection :
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.b IE Inspection Report No. 050-155/76-20
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Licensee:
Consumers Power Company-212. West Michigan Avenue;
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Jackson, Michigan- :49201-Big Rock Point; Nuclear Plant'
.-License No. DPR-6
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' Charlevoix, Michigan -
. Category:: 'C
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Type of. Licensee:
CE 240 MWt-Type of Inspection:
'Special.1 Announced Dates of Inspection:
October'26 and 27 -1976'
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Principal Inspector:
G..T.-Gibson, If '. C w
Il. l O */ t-(Date)
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.I Accompanying Inspector:
None
'Other Accompanying Personnel:
K. Conaughton A-r{.1pg..s G
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Reviewed By:, 'J.. A. Pagliaro, Chief 3 8 [l f - 7 (.
- l Environmental and Special (Date)'
Projects Section i
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SUIMUtY OF FINDINGS
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Inspection Su==ary Announced, special confirnatory ceasure=ents inspection-conducted on October 2'a 'and 27,1976, (7 6-20) for: review of plant radiochemistry and chemical instrument procedures; examination of equipeent and instru=en-tation utilized in plant radiochemistry; review of records and docu=entation pertaining to radioanalytical laboratory quality control programs; discussions with licensee personnel regarding the coeparative analyses results of plant effluent sa:ples obtained during a previous inspection;77 collection of liquid vaste particulate filter, and charcoal adsorber saeples; and submission to the licensee-of a spiked liquid sa=ple, spi.ked particulate filter, spiked charcoal.adsorber, and spiked siuulated gaseous vaste sample for radiochemical analyses.
The licensee's analyti-
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cal results reported for the effluent sacple.s collected and the spiked sa=ples sub=1tted will be examined during r. subsequent inspection.
Enforcement Itens None.
Licensee Action on Previously Identified Enforcement Itees No previously identified enforcement itens within the scope of this
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inspection.
Other Significant Itens A.
Systems and Co=ponents the licensee stated extensive repairs on the laboratory CcLi
,arca spectroscopy system were required in 1976.
The licensee atated the Celi syster was operational approxinately 30%,of 1976.
(Paragraph 3.a. Report Details)
B.
Facility Itens (Plans and Procedures)
None.
C.
Managerial lte=s None.
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1/ IE Inspection Report No. 050-155/76-06.
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Nonco=pliance Identified and Corrected by Licensee None.
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E.
Deviations None.
F.
Status of Previously Reported Unresolved Items No previously reported unresolved ite=s within the scope of this inspection.
Management Interview A management interview was conducted on October 27, 1976, with Mr. C. J.11artman and ce=bers of his staf f.
The following items were discussed:
A.
The NRC inspector discussed the scope and intent of this specific inspection.
(Paragraph 2, Report Details)
B.
The inspector discussed the review of the plant radiochemistry
- procedures, equip:ent, instru=entation, and quality control programs.
(Paragraph 3, Report Details)
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C.
The inspector discussed the results of present and previous com-parative analyses of the plant efiluent saeples, with emphasis cn1 those results not yielding acceptable comparisons.
(Paragraph 4, Report Details)
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= REPORT DETAILS
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Personnel' Contacted
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C. Hartman, Plant Superintendent T. Brun,' Chemistry and, Radiation Protection Supervisor;
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1C.-~Axtell, Plant Health Physicist
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2.
General-The confirmatory measurements inspection consisted of a' review
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of the 'licensce's radiochemistry; and chemistry instrument-pro- ~
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cedures,^and an' examination of selected instrumentation and-equipment relating to radiochemistry. In addition,ia test of the-licensee's measurements of radioactivity in actual plant effluent 1
samples, comparing.the licensee's measurements to'those.of;the; j
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NRC's, reference laboratory, was. performed.
Theitwo 1aboratories
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performed measurements on the same sample,1or ' on duplicates of split' samples..A spiked liquid: sample, a spiked particulate filter, a spiked. charcoal'adsorber, and a. spiked simulated gaseous waste-i
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sample were-provided to the licensee.. A liquid waste sa=ple, particulate filter and charcoal adsorber. effluent samples were obtained by the inspector. 'The results reported by.the licensee will be examined during a subsequent inspection.
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3.
Licensee Radioanalytical Programs
The inspector reviewed selected licensee. procedures, records and documentation pertaining to.the ccaduct of~the radioanalytical program. In addition, the inspector examined selected equipment t
and instrumentation utilized for radiological analyses.
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a.
Equipment and Instrumentation.
The inspector examined the licensee's GeLi.and NaI gamma-spectroscopy systems. Licensee personnel stated the_GeLi
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system will be restored to service on October.29,1 1976, after j
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an extended maintenance outage. Licensee personnel. indicated-
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.the operational availability of the-CcLi system during 1976 was approximately 30%.
Licensee personnel stated-the poor
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operational performance of the GeLi system required backup-i reliance upon the NaI system which was acquired in 1963.
The licensee'is presently assessing the repairs and. modifications.
made to the GeLi system.
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The inspector examined results of ~a' March, ?1976, s calibration :
analysis of the gross beta counting instrumentation.. Licensee.
personnel stated the beta' counting. instrumentation was dis-covered to ha'e a counting efficiency factor of 60% insteadlof'
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v the pre-iiously. assumed: factor of 30%.. The inspector determined -
the licensee has not similarly recalibrated the beta counting, instrumentation since March,L1976. ' Licensee-personnel stated a yearly calibration:frequencyfis utilized for:all-radio--
chemistry instrumentation.
b.
Procedures Theinspectorreviewed' selected'procedureswhichhadf"The
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prepared and approved since the previous inspection.2
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following radiochemistry procedures (RCP) Land chemistry-instrument procedures (CIP) were examined by the' inspector:
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RCP-1 (Rev. 0,.5/11/76)
" Sampling" RCP-3 (Rev. 0, 5/14/76)
"Off-Gas Composition
' Analysis"
RCP-5 (Rev. 0,14/8/76)-
" Chang'ing Stack Gas Sampling Filters"
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RCP-6
.(Rev. O, 4/21/76)
" Analysis of Stack Cas-
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Filters" RCP-7 (Rev. O, 5/4/76)
" Analysis of Liquid Radioactive Batch" CIP-3 (Rev. O, 7/15/76)
" Operation ofLthe TASC-2 Radioisotope: Analyzer"
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.The inspector has no further, questions regarding the pro-cedures referenced above at this time.
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The inspector _ ' lso discussed with licensee personnel the a
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licensee's proposed RCP and CIP procedures relating to laboratory quality control programs, equipment and instrumentation operation, and sampling verifications.
The new RCP-and CIP procedures will be reviewed'during a future inspection.
2/ Ibid.
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Licensee Program For'Qualit'y Control of Analytical Measurements:
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The inspector reviewed the licensee's' program for' control-of quality.in radiological analytical measurements..The.
inspector. noted the licensee does not currently m intain7
' procedures delineating instrumentation calibration limits'or designated (actions to be initiated when-calibration limits _.
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are exceeded. _ Licensee personne1~ indicated proposed RCP and.-
CIP procedures would be' reviewed and appropriate modification of the proposed ' procedures to include = calibration specifi-cations would be performed. This. item will be examined during a subsequent inspection.
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As discussed during a previous in'spection,3/ the inspector
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.noted the licensee has acquired several_ National Bureau of
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Standards (NBS) sources for instrument calibration.
The inspector has no.further questions regarding the licensee's
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NBS ' sources at this time.
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The inspector reviewed the-January and February,-1976, resnits of an informal interlaboratory comparison of samples betw.cn
.the licensee and a subcontracted laboratory.
The results of the interlaboratory comparison indicated'the: licensee's composite results and subcontractor's results varied up.to a factor of 3 for radionuclides quantified.
The licensee has
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.not performed a subsequent interlaboratory comparison.
4.
Comparison of Analytical Results-
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t The confirmatory measurements program consists of a test of the licensee's measurements of radioactive. effluent samples,~ comparing the licensee's measurements with those of the'NRC's reference laboratory.
The results reported by the licensee and the NRC reference laboratory (Health Services Laboratory-(HSL), Idaho Falls,
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Idaho) are compared using the " Criteria for Comparing Analytical-Results" (Attachment 1).
A discussion of the NRC confirmatory
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measurements program is presented-in the-September 1,.1976,' letter from Mr. J. G. Keppler, Director, Region III, USNRC, to Consumers Power Company.
The inspector reviewed the licensee's results reported for~the Febraary,.1976, particulate filter, charcoal adsorber, and liquid
waste samples. A summary of the HSL and 1A... ee results by sample
type and isotope is presented in Table I.
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3/ Ibid.
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The inspector discussed with licensee personnel--the :results-pre-sented in. Table I.
.The inspector. emphasized the:following'analysesi which were in. disagreement:
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. Particulate Filter' EIodine 131, Cesium 134'
'The inspector discusse1 with: licensee personnelfthe gamma
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spectroscopy' analyses of' the -particulate -filter.
'As' discussed'
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in Section 3.a of this report, the. licensee has experienced several' malfunctions of,the GcLi? system-since.the4 previous
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The' inspector collected.a particulate' filter.
sample from the licensee,'and submitted to'the licensee a spiked particulate filter..<The results reported by the licensee will be examined during a subsequent-inspection.
b.
Charcoal Adsorber - Barium'140, Cobalt 60, Lanthanium 140
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As discussed in the September 1,1976, letter from Mr.- J. G.. Keppler, Director, n Region III, USNRC, to - Consumers -
Power Company, radionuclides other.than Iodine 131 on charcoal-adsorbers are not presently beingEconsidered for comparative analyses. However,-.the results are significant in that--the
-- preceding particulate filter is not ef fective in ' trapping. the-particulate activity. Licensee personnel indicated the particulate filters. art now being instriled with a.more (_
positive seal to assure that " blow-by is eliminated.'
'Dii s item will be examined during a subsequent; inspection.
The inspector collected a charcoal adsorber sample.
The.
inspector also submitted to the licensee a spiked charcoal ~
adsorber. The results reported'by the-licensee will be examined during a' subsequent inspection.
c.
Liquid Waste - Beta, Strontium 90 The-inspector discussed'with licensee ~ personnel.th/ results of the gross beta analysis and strontium 90 analysis.of the--
previously collected liquid waste sample.
As_ discussed in Sectionj3.a of this' report, the licensce's beta. counting.
instrumentation was being utilized with an improper counting efficiency factor during the period prior to March,1976.
~The.
analysis of strontium 90 is routinely performed by a licensee
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subcontractor, however, the' licensee' attempted'to' identify.
the strontium'90 activity for.the. liquid waste sample collected..
Licensee personnel' stated all future struntfum' analyses,
. including confirta*ory measurements samples, would be per-
. formed by the licensee's' subcontractor..
The inspector collected a liquid-waste sampic, and submitted-
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to the licensee a spiked liquid waste sample; The results reported-by the licensee will be examined during.a subsequent inspection.
.11ua inspector 'noted, based on.the results ;repotied by-the : licensee in this. confirmatory measurements comp'rison, that for the a
particulate activity released'in-gaseous effluents during thel period of this inspection the licensee would have underreported the radionuclide concentrations of particulate; activity..Hcvever, the inspector. noted the nonconservative reporting would not have
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resulted in the violation.of-the licensee's annual operating release limits. With respect to the gross. beta.activityLin-liquid waste, the licensee may hove overrepcrted the gross beta. activity -
in liquid waste.
The inspector reviewed and discussed with licensee personnel the
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licensee's g73fgymance in the confirmatory measurements program 7 since~1974.
The inspector noted the licensee has performed-33 acceptable comparisons-(54%) and 28 unacceptable comparisons
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(46%).
The inspector noted for the present inspection, the.
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licensce's comparative analyses results yielded 7 : acceptable comparisons (64%) and 4 unacceptable comparisons (30%). Licensee.
personnel believe this poor performance has been.primari19 attributed to the problems encountered in the GeLi system and operational-limitations of the Na1 system. The inspector re-emphasized the importance of the confirmatcry acasurements program and will examine corrective actions implemented by. tlic licensee to assure acceptable comparisons'uring a subsequent inspection.
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Attachments:
1.
Attachment 1, Criteria For Comparing Analytical Measurements.
2.
Table 1, Confirmatory Measurements Program.
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R.O. Inspection Report No. 050-155/74-07.
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IE Inspection Report No. 050-155/75-01.
IE Inspection Report No. 050-155/76-06.
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ATTACIC4DIT 1
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i CRITERIA FOR COMPARIEC ANALYTICAL MEASURDIENTS;
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This attachment provides criteria for comparing results of capability'
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tests and verification ncaserements.: 1The critcria:are based on an
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. empirical relatienship whichtcombines prior 'experienen and the accuracy 1
needs of this program.
In.these criteria, the' judgment. limits are variable is relation to the -
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comparison of.the NRC Reference I.aboratory's value to its associated.
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one signa uncertainty; As that; ratio referred to: in-this program as :
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" Resolution", increas,x, th'e' acceptability-of.a licensec's measurement; should be more selective.- Conversely,lpoorcr; agreement shouldfbe: con--
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sidered acceptableJas. the resolution * decreases.
The values _in the ratio.
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criteria ray be rounded to fever significant. figures to' maintain statistical consistency-with the number of significant: figures ~ reported.
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by the NRC Reference Laboratory, unless such rounding vill ~resul't ins
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. narrowed category of acceptance. The-cceeptance category reported'will
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be the narrouest into which the ratio'fitsifor the resolution being used.'
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RESOLU' ION
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Possibic:
Possible'
AgreementL Agreement "A"-
' Agreeable "B"
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<3 No-Comparison'
No Comparison :No1 Comparison
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>3 and <4 0.4
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3.0
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-- 1.67
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- 0. 5 ' - 2.0 T16 and <51-0.75 - ~1.33-0.6
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3200 0.85 - 1.18 0.80 - ~1.25 0.75 - 1.33
- "A" criteria are applied to the following analyses:
Gamma.;--tiometry, where principal. gamma cnergy used for,identifi-
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cation is greater than,250 kcV.
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Tritium analyses of liquid samples.
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"B" criteria are applied to.the following analyses:
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Gamma spectronetry, where principal gamma energy used for identifi-'
cation is less than 250 kev.
Sr,-89 and Sr-90 determinations.-
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Cross beta, where sampics are. counted en the same date using the same reference'nuclide.
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