IR 05000155/1987029

Insp Rept 50-155/87-29 on 871214-18.No Violations or Deviations Noted.Major Areas Inspected:Qa & Confirmatory Measurements for in-plant Radiochemical Analyses, Verification of TLD Collocation & Action on Previous Items

ML20149E812
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	01/04/1988
From:	Januska A, Schumacher M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20149E803	List: IR 05000155/1987029 ML20149E799
References
50-155-87-29, NUDOCS 8801140022
Download: ML20149E812 (10)

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. O. S. NUCLEAR REGULATORY COMMISSION

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REGION III ,

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Report No. 50-155/87029(DRSS)

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 Point Site, Charlevoix, Michigan Inspection conducted: December 14-18, 1987 (Onsite) w N >

Inspectors: A.hanuska #f4f 88 Date i

Accompanied by: R. Bocanegra ,

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]9/,i Approved by: M. 'fhtywlU Schumacher, Chief Radiological Effluents Date and Chemistry Section

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Inspection Summary i

Inspection on December 14-18, 1987 (Report No. 50-155/87029(DRSS))

Areas Inspected: Routine announced inspection of: (1) quality assurance and '

confirmatory measurements for in plant radiochemical analyses; (2) verification of TLD collocation; and (3) action on open items identified during previous :

inspection Results: No violations or deviations were identified during this inspectio ,

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. DETAILS

' Persons Contacted

• R. Alexander, Technical Engineer R. Bearss, Senior Chemistry and Health Physics Technician

• Burdette, Senior Health Physicist

• T. Elward, Plant Manager

. *R. Garrett, Chemistry and Health Physics Supervisor r

• L. Monshor, QA Superintendent J. Plunkett, Senior Chemistry and Health Physics Technician

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• Denotes those present at the exit meetin . Licensee Action on Previous Inspection Findings (Closed) Open Item (155/86012-01): Purchase a suitable gas standard and calibrate gas geometries within two weeks after receipt. The licensee determined the ratios of attenuation of water to air for

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11 energies and applied them to efficiencies determined from a newly purchased NBS traceable liquid standard counted in the off gas vial geometr Documentation cf the calibration was reviewed and appeared '

to be technically correct.

i (Closed) Open Item (155/86012-02): Add Sn-113 to appropriate  !

libraries and jobstreams. The inspector reviewed the licensee's LIB. LIQ and LIB. DIS libraries which had been revised August 13, 1986 and found that Sn-113 had been added to both, (Closed) Open Item (155/86012-03): Analyze liquid sample for gross beta, H-3, Sr-89, Sr-90 and report results to RIII. Results of sample comparisons are listed in Table 1; comparison criteria are given in Attachmont The lone disagreement, gross beta was due to '

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, the fact that the sample was not prepared until well after it was collected which allowed some activity to plate out onto the container '

walls and bottom thus reducing the concentration of activity in the The delay in preparing the sample is atypical of routine

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beta counting. This effect has been noted on previous occasion The sample collected during this inspection was pipetted onto l

planchets at the time of the spli (Closed) Open Item (155/86012-04): Perform monthly source checks on l

the backup / emergency gamma spectroscopy system and energy calibrate ;

if require Procedure CIP-6 (T30-47) entitled "Operation of the !

Nuclear Data Radioisotope Analyzer" was last revised October 31,

1986 to include the backup / emergency system (Detector 2) on a reouir

J of-monthly preventive maintenance schedule. The inspector ,

^ctiewed the maintenance check lists and found them to be complete, e i

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• (Closed) Open Item (155/86012-05): Provide training to C&HP technicians on the gamma spectroscopy system in six month f The licensee provided. training to C&HP technicians on Practical *

Factors for N06685 Multichannel Analyzer. The seven factors ,

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, covered appeared to be comprehensiv . Confirmatory Measurements Sample Split Five samples (air particulate, charcoal adsorber, reactor coolant,  !

liquid waste, and gas) were analyzed for gamma emitting isotopes

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by the licensee and in the Region III Mobile Laboratory on sit !

Comparisons were made on the licensee's count rcom detector  !

(Detector 1) and backup / emergency detector (Detector 2). Results t of the sample comparisons are given in Table 2; the comparison  ;

criteria are given in Attachment The licensee achieved  !

56 agreements out of 59 comparison The particulate filter, charcoal adsorber, and gas comparisons were l

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all agreements. The liquid waste sample resulted in one disagreement, :

Co-58, on each detector when the licensee failed to identify this j nuclide. This nuclide was masked by two others with higher j concentrations and was not detected by the licensee's ' software. The !

inspectors examined the licensee's LLD calculations and verified i that the LLD requirements of their Technical Specification for Co-58 l

were being met. The licensee plans to upgrade his spectroscopy  :

system and incorporate revised peak identification softwar l

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A portion of the liquid waste sample will be analyzed for gross beta, !

j H-3, Sr-89, and Sr-90 and the results reported to Region III for  !

l comparison with analysis by the NRC Reference Laboratory on a split  !

i of the sample (0 pen Item No. 50-155/87029-01). j j A reactor coolant sample counted immediately after filtration I resulted in all agreements on Detector 1 and a disagreement for  !

I-131 on Detector 2 (results not shown on Table 2). As the licensee's procedure calls for a three hour decay before counting,  ;

, the remainder of the sample was split and counted at three hours i after collection. Detector 2 yielded all agreements but Detector 1 (

had one disagreement, I-133. A review of the peak search revealed l that there are three peaks within 7 kev of each other and of the four analyses made during the inspection, the system software correctly (

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deconvoluted the peaks three times but failed on the fourth. The  !

licensee stated that as a part of the normal review of analytical  ;

results additional attention to these peaks and the iodine results  ;

will be stressed. The pending software upgrade should help rectify  :

this proble !

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Quality Assurance ,

l The inspectors reviewed the radioactivity measurements laboratory

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quality assurance program including the physical facilities, .

1 laboratory operations, . and procedures. All the counting equipment i was found to be in good working order. Chemistry and Health Physics ,

Technicians were observed and evaluated on sample collection and preparation, sample splitting and analysis. A reagent bottle with

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an expired date was found by the inspectors in the laboratory. The .

., reagent was used for an analysis no longer performed by the licensee '

and was promptly discarde The inspectors reviewed Big Rock Point Chemistry Procedures bicluding Operation of Tennelec Well Type Gamma Counter (CIP-1), Operation of RIOL Gamma Spectrometer (CIP-2), Use of NMC Proportional Counter PC-5 (CIP-4), and Operation of ND Radioisotope Analyzer (CIP-6).

The inspectors also reviewed documentation related to scheduled preventative maintenance, QA checks, and yearly calibration i Audits Audit reports QT-86-17 conducted August 25-29, 1987.and QT-87-20 conducted August 24-28, 1987 were reviewed. No items relevant to this inspection were note No violations or deviations were identifie . Thermoluminescent Dosimeter (TLD) Collocation Verification The inspectors confirmed by observation that collocated NRC TLD's were [

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located closely adjacent to the licensee's TLD's.

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'l No violations or deviations were identified.

! Open Items t

Open items are matters which have been discussed with the licensee, which ,

will be reviewed further by the inspector, and which involve some action ,

l on the part of the NRC or licensee or bot An open item disclosed during

] the inspection is discussed in section 3.a.

Exit Meeting

3 The inspectors met with licensee representatives denoted in Section 1 at ,

the conclusion of the inspection on December 18, 1987. The scope of the

{j inspection was discusse '

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During the inspection the inspecters discussed the likely informational content of the inspection report with regard to iocuments or processes reviewed by the inspectors during the inspection. Licensee representatives did not identify any such documents or procedures as proprietar Attachments: Attachment 1. Criteria for Comparing Analytical Measurements Table 1, Confirmitory Measurements Program Results, 3rd Quarter 1986 Table 2, Confirmatory Measurements Program Results, 4th Quarter 1987

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TABLE 1 U S NUCLEAR-REGULATORY COMMISSION OFFICE OF 11'3PECTION AND ENFORCEMENT CONFIRMATORY MEASUREMENTG'PROGRA*1 FACILITY: BIG ROCK'

FOR.THE 3 OUARTER OF 1986

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NRC------- ----LICENSEE---- ---LICENSEEINRC----

SAMPLE ISOTOPE RESULT ERROR RESULT ERROR RATIO RES T

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L TASTE l G BETA 2.8E-03 9.0E-05 1.7E-04 2.9E-05 6.0E-02 3.1E 01 D t H-3 5.4E-03 8.0E-05 5.3E-03 1.5E-05 9.8E-01 6.8E 01 .A i

.SR-Sc 1.2E-05 8.0E-07 7.8E-06 3.0E-07 6.5E-01 1.5E-01 A l SR-9 ' 1.5E-06 2.0E-07 U.0E-07 1.0E-07 5.3E-01 7.5E 00 A

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T TEST RESULTS A= AGREEMENT D= DISAGREEMENT o= CRITERIA RELAXED N=NO COMPARIS"N  !

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A TABLE 2 U S NUCL EAR REGUL.ATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT CONFIRMATORY MEASUREMENTS PROGRAM FACILITY: BIG ROCK

.FOR THE 4 QUARTER OF 1987

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NRC------- ----LICENSEE---- ---LICENSEEINRC----

SAMPLE ISOTOPE RESULT ERROR RESULT ERROR RATIO RES T OFF GAS XE-135M 2.6E-02 1.9E-03 2.0E-02 6.2E-04 7.9E-01 .1.3E 01 A D8Ti XE-138 1.0E-01 5.1E-03 9.9E-02 2.7E-03 9.7E-01 2.0E 01 A

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P FILTER CR-51 9.4E-04 2.5E-04 1.0E-03 1.7E-04 1.1E 00 3.8E 00 A Thsrs CO-60 4.3E-04 1.2E-04 4.4E-04 4.1E-05 1.0E 00 3.6E 00 A CS-134 1.8E-04 3.2E-05 2.2E-04 2.7E-05 1.2E 00 5.5E 00 A CS-137 5.0E-04 4.7E-05 5.6E-04 3.2E-05 1.1E 00 1.!E 01 A LA-140 5.4E-03 6.6E-04 3.8E-03 5.1E-04 7.0E-01 8.1E 00 A OFF GAS KR-85M 1.0E-03 1.4E-05 9.6E-04 3.6E-05 9.3E-01 7.2E 01 A tFTA KR-87 5.5E-03 2.4E-04 5.1E-03 2.4E-04 9.3E-01 2.3E 01 A KR-88 3.5E-03 1.9E-04 3.2E-03 1.3E-04 9.0E-01 1.9E 01 A XE-133 4.2E-04 5.6E-05 4.1E-04 4.6E-05 9.BE-01 7.5E 00 A 1 XE-135 4.7E-03 7.0E-05 4.2E-03 6.4E-05 9.!E-01 6.6E 01 A l

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P FILTER CR-51 9.4E-04 2.5E-04 7.6E-04 1.8E-04 8.0E-01 3.8E 00 A

% Fr a CO-60 4.3E-04 1.2E-04 4.7E-04 5.2E-05 1.1E 00 3.6E 00 A CS-134 1.8E-04 3.2E-05 2.7E-04 4.7E-05 1.5E 00 5.5E 00 A CS-137 5.0E-04 4.7E-05 5.8E-04 3.8E-05 1.!E 00 1.1E 01 A LA-140 5.4E-03 6.6E-04 3.5E-03 6.3E-04 6.5E-01 8.1E 00 A C FILTER I-131 2.3E-03 1.0E-04 2.3E-03 6.8E-05 1.0E 00 2.3E 01 A l gg7 g I-133 5.3E-03 2.6E-04 4.7E-03 1.6E-04 9.0E-01 2.0E 01 A l BR-82 5.3E-03 2.5E-04 5.0E-03 1.5E-04 9.4E-01 2.1E 01 A L WASTE CR-51 3.SE-05 4.9E-Oe 3.9E-05 4.6E-06 1.OE 00 7.7E 00 A i g er g MN-54 1.0E-04 1.4E-06 1.0E-04 1.4E-06 9.9E-01 7.2E 01 A '

CO-58 4.2E-06 6.3E-07 0.0E-01 0.0E-01 0.0E-01 6.6E 00 D CO-60 3.5E-04 2.2E-06 3.6E-04 2.6E-06 1.0E 00 1.6E 02 A ZN-65 3.4E-05 2.0E-06 3.2E-05 2.0E-06 9.4E-01 1.7E 01 A CS-134 1.9E-05 8.2E-07 1.9E-05 1.42-06 1.0E 00 2.3E 01 A CS-137 3.3E-04 2.0E-06 3.2E-04 2.1E-06 9.5E-01 1.7E 02 A T TEST RESULTS:

A= AGREEMENT D= DISAGREEMENT

• • CRITERIA RELAXED N=NO COMPARISON

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TABLE 2 Li S NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT CONFIRMATORY MEASUREMENTS PROGRAM FACILITY: BIG ROCK FOR THE 4 QUARTER OF 1907

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NRC------- ----LICENSEE---- ---LICENSEE:NRC----

SAMPLE ISOTOPE RESULT ERROR RESULT ERROR RATIO RES T C FILTER I-131 2.3E-03 1.0E-04 2.5E-03 8.0E-05 !.1E 00 2.3E 01 A I-133 5.3E-03 2.6E-04 5.0E-03 2.1E-04 9.4E-01 2.0E 01 A lb g7 A BR-82 5.3E-03 2.5E-04 5.2E-03 1.9E-04 9.7E-01 2.1E 01 A PRIMARY NA-24 9.4E-04 5.5E-05 0.5E-04 3.8E-05 9.1E-01 1.7E 01 A typ7 CR-51 1.8E-03 2.5E-04 2.1E-03 1.4E-04 1.2E 00 7.1E 00 A CO-60 1.2E-04 4.0E-05 9.1E-05 2.8E-05 7.5E-01 3.0E 00 A I-131 1.4E-04 2.4E-05 1.2E-04 1.8E-05 8.0E-01 6.1E 00 A I-132 3.4E-03 1.4E-04 3.3E-03 9.7E-05 9.6E-01 2.4E 01 A I-133 1.8E-03 4.6E-05 6.2E-04 3.8E-05 3.4E-01 3.9E 01 D I-134 1.2E-02 9.9E-04 1.0E-02 6.7E-04 8.8E-01 1.2E 01 A I-135 3.7E-03 2.1E-04 4.4E-03 1.5E-04 1.2E 00 1.8E 01 A SR-91 9.4E-04 1.8E-04 7.0E-04 7.6E-05 7.5E-01 5.2E 00 A SR-92 2.6E-03 1.2E-04 2.3E-03 9.3E-05 8.7E-01 2.2E 01 A BA-139 3.8E-03 5.GE-04 2.4E-03 2.4E-04 6.4E-01 6.5E 00 A MO-99 4.8E-03 4.6E-05 4.7E-03 2.6E-05 9.8E-01 1.0E 02 A

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L UASTE CR-C1 4.4E-05 5.7E-06 2.9E-05 5.4E-06 6.8E-01 7.7E 00 A g g7 g MN-54 9. 9E-05 1.4E-06 9.9E-05 1.BE-06 1.0E 00 6.9E 01 A CO-58 3.9E-06 8.6E-07 0.0E-01 0.0E-01 0.0E-01 4.5E 00 D CO-60 3.5E-04 2.2E-06 3.6E-04 3.2E-06 1.0E 00 1.6E 02 A CS-134 2.0E-05 7.7E-07 1.8E-05 1.2E-06 8.9E-01 2.6E 01 A CS-137 3.3E-04 1.9E-06 3.1E-04 2.4E-06 9.4E-01 1.7E 02 A i PRIMARY NA-24 8.3E-04 5.3E-05 9.2E-04 4.6E-05 1.1E 0 .6E 01 A CR-51 1.7E-03 2.1E-04 1.7E-03 1.8E-04 1.0E 00 7.9E 00 A l TMFr A I-131 1.5E-04 2.9E-05 1.3E-04 2.0E-05 8.5E-01 5.3E 00 A I-132 3.2E-03 1.3E-04 3.6E-03 1.0E-04 1.tE 00 2.5E 01 A I-133 1.7E-03 4.7E-05 1.7E-0~ 3.6E-05 9.9E-01 3.6E 01 A I -134 1.OE-02 7.9E-04 1.0E-02 5.8E-04 9.9E-01 1.3E 01 A I-135 4.5E-03 2.1E-04 4.5E-03 1.9E-04 1.0E 00 2.2E 01 A ,

SR-91 1.2E-03 1.6E-04 7.8E-04 1.1E-04 6.7E-01 7.4E 00 A j l

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T TEST RESULTS:

A= AGREEMENT D=DfSAGREEMENT

• = CRITERIA RELAXED NANO COMPARISON i-2-

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TABLE 2 U S NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT CONFIRMATORY MEASUREMENTS PROGRAM FACILITY: BIG ROCK FOR THE 4 QUARTER OF 1987

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NRC------- ----LICENSEE---- ---LICENSEE:NRC----

SAMPLE ISOTOPE RESULT ERROR RESULT ERROR RATIO PES T PRIMARY SR-92 2.2E-03 1.2E-04 2.7E-03 1.1E-04 1.2E 00 1.8E 01 A BA-139 3.5E-03 4.5E-04 2.9E-03 2.1E-04 0,1E-01 7.8E 00 A MO-99 5.0E-03 4.8E-05 4.6E-03 3.2E-05 9.1E-01 1.0E 02 A T TEST RESULTS:

A= AGREEMENT D= DISAGREEMENT o= CRITERIA RELAXED N=NO COMPARISON

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ATTACHMENT 1 1

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CRITERIA FOR COMPARING ANALYTICAL MEASUREMENTS ,

This attachment provides criteria for comparing results of capability tests and verifit.ation measurements. The criteria are based on an empirical relationship which combines prior experience and the accuracy needs of this progra In these criteria, the judgment limits are variable in relation to the comparison of the NRC'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 considered acceptable as the resolution decreases. The values in the ratio criteria may be rounded to fewer significant figures reported by the NRC acceptance. Laboratory, unless such rounding will result in a narrowed category of Reference RESOLUTION RATIO = LICENSEE VALUE/NRC REFERENCE VALUE ri Agreement

<4 0.4 - .F - .6 - 1.66 16 - 50 0.75 - 1.33 51 - 200 0.80 - 1.25 200 - 0.85 - 1.18

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Some and fordiscrepancies some specificmay result from the use of different equipment, techniques, nuclide These may be factored into the acceptance criteria and identified on the data shee . l

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