IR 05000155/1976020

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IE Insp Rept 50-155/76-20 on 761026 & 27.No Noncompliance Noted.Major Areas Inspected:Radiochemistry & Chemical Instrument Procedures,Records & Documentation Re QA Program, Effluent Sample Analyses, & Radwaste Sys
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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D.

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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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

inspection.

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.

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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

~ RATIO = LICENSEE VALUE/NRC REFERENCE VALUE

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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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- 0. 5 ' - 2.0 T16 and <51-0.75 - ~1.33-0.6

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- 1.67 T51 and <200 0.80 - 1.25 0.75

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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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