ML20246L899

Insp Rept 50-346/89-08 on 890213-17.No Violations Noted. Major Areas Inspected:Confirmatory Measurements & Environ Monitoring programs,including,audits,QA,in-plant Radiochemical Analyses & post-accident Sampling

ML20246L899
Person / Time
Site:	Davis Besse
Issue date:	03/15/1989
From:	Januska A, Schumacher M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20246L892	List: ML20246L888 ML20246L899
References
50-346-89-08, 50-346-89-8, NUDOCS 8903240310
Download: ML20246L899 (14)

See also: IR 05000346/1989008

Text

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F. U. S. NUCLEAR REGULATORY COMMISSION H

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' REGION III

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' Report No. . 50-346/89008(DRSS) [

1 Docket No. 50-346 License No. NPF-3 -

~ Licensee: Toledo Edison Company.  !

Edison Plaza

300 Madison Avenue- ,

Toledo, OH. 43652 i

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' Facility Name: Davis-Besse Nuclear-Power Station j

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Inspection Ati _ Davis-Besse Nuclear Power Station, Oak Harbor,:0hio

Inspection-Conducted: February 13-17, 1989 .

0, . amW .

. Inspectors: A.'G.(anuska Y/f/99 1

Date ;o i

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-Approved By: M. humacher, Chief 3//s'f/'f. 0

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Radiological. Controls and Date ,j

Chemistry Section -i

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Inspection Summary i

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Inspection on February 13-17, 1989 (Report No. 50-346/89008(DRSS))

Areas Inspected: . Routine announced inspection of confirmatory measurements ,

and environmental monitoring programs (IP 84750) including: audits, quality j

assurance, confirmatory measurements of in plant radiochemical analyses, post

accident sampling, implementation of the environmental monitoring program j

and open items (IP 92701).  ;

Results: Confirmatory measurements comparisons improved. Two of the i

three disagreements during this inspection appear to be anomalies. The ,

three licensee detectors tested gave results that compared closely. The 1

Environmental Monitoring Program is well implemented.

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. DETAILS

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1. Persons Contacted

• L. Bonker, Rad Health General' Supervisor  ;

J. Bunk,. Quality Engineer, SAI-

V. Capozziello, Chemistry Analyst

R. Claes, . Chemistry Analyst : .

.E. Delicate,' Assistant Nuclear Technologist

• R. Edwards, Associate Chemistry Analyst I

• G. Honma, Compliance Supervisor

• J. Magers, Associate Licensing Technologist

• J. Oldman, Associate Radiological Control Technologist j

• J. Polyak, Rad Control Managor

R. Rinderman, QA Verification. Supervisor

• R. Scott, Chemistry Superintendent

• B.. Smith, Associate Nuclear Technologist

• D. Kosloff, Resident Inspector

• Denotes those present at the exit interview.

2. Licensee Action on Previous Inspection Finding (IP 92701)

a. (0 pen) Open Item (50-346/88008-03): Licensee spiked and analyzed

a condensate sample with anions and another with metals and split.

the samples with Brookhaven National Laboratory. The results of the l

analyses submitted to Region III on fluoride, chloride, sulfate,

'

iron, and copper are shown in Table 1 with the acceptance criteria  !

in Attachment 1. The licensee had three agreements in five analyses.

! The results with disagreements were given relative standard

deviations of i 3%, uncertainties that appear to be' reasonable for

these types of analyses The licensee appeared to have a problem

with the ion chromatograph results for chloride and sulfate. This .l

matter will be reviewed in a subsequent inspection.

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b. (Closed) Open Item (50-346/87023-02): Analyze liquid sample for

gross beta, H-3, Sr-89, Sr-90 and Fe-55 and report results to

Region III. After having difficulty with the sample collected

during inspection 50-346/87023 the licensee agreed to analyze a

spiked liquid sample supplied by RESL, the NRC's reference

laboratory. The comparisons are listed in Table 2; the comparison i

criteria are given in Attachment 2.

c. (Closed) Open Item (50-346/86026-06): Licensee to revise REMP

Surveillance Test Procedure ST 5099.03, " Radiological Environmental

Monitoring Program," Revision 13 to assign responsibilities to the

current REMP management. Revision 14, issued February 27, 1987 was

changed to reflect responsibility assignment and now includes tasks

which had not been proceduralized. The requirements of AD 1843.00

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have been incorporated into NG-HS-00501 to update the REMP

requirements and show the transfer of responsibility for the  !

conduct, management and reporting of the REMP from Chemistry and

Health Physics to Environmental Compliance.

3. Confirmatory Measurements

a. Sample Split

Six samples (air particulate, charcoal adsorber, crud filter used as

an air particulate, reactor coolant, gas and liquid were analyzed

for gamma emitting isotopes by the licensee and in the Region III

Mobile Laboratory onsite. Comparisons were made on the licensee's

Radiological Control (RC) and Chemistry (CHM 1 and CHM 2) detectors.

The licensee achieved 101 agreements in 105 comparisons as listed in

Table 3; the comparison criteria are given in Attachment 2.

Comparisons of a particulate filter, charcoal and a Miscellaneous

Waste Drain Tank (MWDT) results yielded in all agreements. The

licensee agreed to analyze or have analyzed a portion of the

MWDT for H-3, Sr-89, Sr-90 and Fe-55 and report the results to

Region III for comparison with an analysis by the NRC Reference

Laboratory (0 pen Item 50-346/89008-01).

A reactor coolant filter (CRUD) was analyzed as a particulate to

further test this geometry. The licensee's detectors initially

failed to identify I-134 (not shown in Table 3) and Zr-97. Review

of the data revealed that only 20% of the normal sample size had

been used at the request of the inspector and I-134 had decayed to

approximately 3.5% of its initial value prior to analysis. The

review also revealed that a high abundance line of the daughter of

Zr-97, normally used to quantify Zr-97, was not listed in the

licensee's library. The licensee changed his nuclide library prior

to the end of the inspection and the results became agreements.

Sample size is believed to be part of the problem for failure to

identify and quantify Mn-54 and I-135. A stringent quantification

test for I-135 combined with a lower detector sensitivity ,

appear.to have also contributed to the disagreements. 1

Results of comparison of primary coolant yielded a disagreement for

I-134 on all detectors (not shown in Table 3) and for Na-24 on the

RC detector. This particular sample was counted well beyond

the procedure specified 55 to 65 minute counting window and the

I-134 had decayed to less than 10% of its initial value. Also,

the licensee's counting efficiency was about 30% of that of the NRC.

The inspector reviewed data from past primary coolant samples analyzed

55 to 65 minutes after sampling as required by DB-CH-03000,

" Primary Coolant System Radiochemistry" and confirmed the

quantification of I-134 in all results examined. No reason for

failure to accurately quantify Na-24 was determined.

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A disagreement for Xe-133 was noted on CHM-1.. A review of data did d

not reveal the reason; however, a subsequent review of Table 3 gas- '

results indicates a slight bias on.both chemistry detectors for this

geometry. ,

b. Quality Assurance

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The inspector examined results of the licensee's 1988

l intercomparison results from a crosscheck program with an outside a

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vendor. Analyses. included liquid for gamma.in a one liter marinelli-

L and a 30cc bottle, alpha, beta, H-3, Sr-89, Sr-90, Fe-55 and

I-131. A two inch filter comparison was added during the year.

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There was only one disagreement during the year for all analyses and

it is being.. investigated.

The inspector performed a limited review of the counting room ,

quality assurance implementation. Records and discussions with lab

personnel indicate that performance tests are being performed as  ;

required. j

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c. Audits '

No formal quality assurance audit of radiochemistry was performed

since the last Confirmatory Measurements inspection; however, the

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inspector did examine plans for an audit scheduled for February 27-  :

,through March 10, 1989. The inspector noted that qualified auditors

and Technical Specialists were to be used and that the planned audit  !

appeared to be reasonably comprehensive. j

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d. Post Accident' Sampling

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The inspector discussed the Post Accident Sampling System (PASS) and l

examined its operation with the licensee. The system has en in-line i

hydrogen analyzer and the capability of obtaining undiluted

reactor coolant from any of five appropriate sample points which

then can be stripped for gas. The system is tested monthly, when

flow is available, in accordance with Procedure DB-CH-4001, Post  !

Accident Sampling Monthly Test at which time a H-3 sample is

analyzed to verify sample representativeness. The inspector

observed the performance of this procedure by two Chemistry Testers

and the training of a Chemistry Tester'on this system by the

. Training Supervisor. Any required liquid or gas dilutions will be

performed in the " hot" portion of the Chemistry Laboratory. A

separate Emergency Containment Atmosphere Grab Sample system will

be used to collect a containment air particulate, radiciodine or gas

sample. ,

No violations or deviations were identified.

4. Environmental Monitoring

The inspector reviewed the licensee's Annual Environmental Operating

Report for 1987. Results were at or below LLO or the same as previous

years. All required samples were accounted for.

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'No violations or deviations were identified.

5. Open Items

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

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

on the part of the NRC or licensee or both. Open-items disclosed during

the inspection are discussed in Section 3.

6. . Exit Meeting

The inspector-met with the licensee representatives denoted in

Section 1. The scope.of the. inspection and findings were discussed with

emphasis on the capability of the counting system.

'During the exit interview, the inspector discussed the likely ,

informational content of the inspection report with regard to documents

e or processes reviewed by the inspector during the inspection. l.icensee

representatives did not identify.any such documents or processes as.

proprietary.

Attachments:

1. Table 1, Nonradiological

Interlaboratory Split

Sample Results, June 1988

12. Attachment 1, Criteria for

Comparing Analytical

Measurements (Nonradiological) .;

3. Table 2, Radiological Confirmatory  :

Measurements Program Results

3rd Quarter 1987 ,

4. Attachment 2, Criteria for '!

Comparing-Analytical 4

Measurements:(Radiological) (

5. . Table'3, Radiological Confirmatory j

Measurements Program Results

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1st Quarter 1989 i

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TABLE.1

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l Nonradiological Interlaboratory Split Sample Results

Davis-Besse Nuclear Power Plant I

March 1988

b

Analytical NRC Licensee Ratio Comparison

a

Analyte Method Y i SD- X i SD Z i SD ,1 2 SD

Reactor Coolant Water Concentration, ppb

Fluoride IC 50.0 0.6 47.8 i 1.4 0.956 i 0.030 A

Chloride IC 45.3 1 0.3 52.9 i 0.2 1.168 1 0.009 0*

Sulfate IC 41.2 0.4 50.0 1 1.6 1.214 i 0.041 D*  !

Feedwater

Iron AAS/FL 490 10 527 i 11 1.076 0.045 A* d

Copper AAS/FL' 480 10 489 1 0 1.019 i 0.022 A

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a. Analytical method:

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IC Ion chromatography

AAS/FL Atomic absorption spectrophotometry / Flame

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b. Comparison:

A Agree

O Disagree

c. * Assumed a relative standard deviation (RSD) of 3% for both the licensee

and BNL results. 4

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' ATTACHMENT 1

Criteria for Comparing Analytical Measurements f

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This attachment provides criteria for comparing results of the capability tests.  !

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'The acceptance limits are based on the uncertainty (standard deviation) of the

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i ratio of the licensee's mean value (X) to the NRC mean value (Y), where  !

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(1) Z = X/Y is the ratio, and

(2) S is the uncertainty of the ratio determined from the )

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pfopagationoftheuncertaintiesoflicensee'smeanvalue,

S , and of the NRC's mean value, Sy.1 Thus,

x

S2z _ 32

x

s2

y , so that

Tz- y + y

s2D

S

z

=Z*1 [S*2 + Y

y2)  ;

(X2

The results are considered to be in agreement when the bias in the ratio

(absolute value of difference between unity and the ratio) is less than or

equal to twice the uncertainty in the ratio, i.e.

l 1-Z l < 2*S 7

1. National Council on Radiation Protection and Measurements,

-A Handbook of Radioactivity Measurements Procedures, NCRP

Report No. 58, Second Edition, 1985, Pages 322-326 (see

Page 324).

4/6/87

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TABLE 2 l

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U.S NUCLEAR REGULATORY COMMISSION l

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OFFICE OF INSPECTION AND ENFORCEMENT i

CONFIRMATORY MEASUREMENTS PPOGRAM

FACILITY: DAVIS BESSE

FOR THE 3 QUARTER OF 1987

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NRC- ---

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LICENSEE---- ---LICENSEE:NRC---- 'J

SAMPLE ISOTOPE RESULT ERROR RESULT ERROR RATIO RES T. l

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L WASTE H-3 5.9E-05 1.2E-06 .5.7E-05 0.0E-01 9.6E-01 5.OE 01 A

SR-89 4.5E-04 1.3E-05 5.0E-04 1.0E-05 1.1E 00 3.5E 01 A

SR-90 2.7E-05- 1.1E-06 2.6E-05 1.0E-06 9.6E-01 2.5E 01 A

FE-55 5.9E-05 1.2E-06 5.6E-05 4.0E-06 9.6E-01 4.9E 01 A

T TEST RESULTS:

A= AGREEMENT

D= DISAGREEMENT

-c= CRITERIA RELAXED

N=NO COMPARISON

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ATTACHMENT 2

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CRITERIA FOR COMPARING ANALYTICAL MEASUREMENTS ,

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This attachment provides criteria for comparing results of capability tests {

and verification measurements. The criteria are based on an empirical

relationship which combines prior experience and the accuracy needs of this l

program.

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, 1

referred to in this program as " Resolution", increases, the acceptability of a .

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licensee's measurement should be more selective.

should be considered acceptable as the resolution decreases. Conversely, poorer agr i

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The values in the

ratio criteria may be rounded to fewer significant figures reported by the NRC  ;

Referene.e Laboratory, unless such rounding will result in a narrowed category of i

acceptance.

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RESOLUTION

RATIO = LICENSEE VALUE/NRC REFERENCE VALUE

r 5

Agreement

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0.4 - 2. s

4- 7

0.5 - 2.0 '

8- 15

0. 6 - 1.66

16 - 50 0.75 - 1.33 '

51 - 200 0.80 - 1.25

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200 - 0.85 - 1.18

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Some

and fordiscrepancies

some specificmay result from the use of different equipment, techniques,

nuclides.

criteria and identified on the data sheet.These may be factored into the acceptance  ;

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TABLE 3

U S NUCLEAR REGULATORY COMMISSION

OFFICE OF INSPECTION AND ENFORCEMENT

,

CONFIRMATORY MEASUREMENTS PROGRAM

FACILITY: DAVIS-BESSE

FOR THE 1 QUARTER OF 1989

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SAMPLE ISOTOPE RESULT ERROR RESU'T ERROR RATIO RES T

P FILTER CS-134 3,7E-04 4.OE-05 2.4E-04 0.OE-01 6.4E-01 9.3E 00 A

RC CS-137 7.3E-04 4.9E-05 5.0E-04 0.0E-01 6.9E-01 1.5E 01 A 1

I-131 2.9E-04 3.1E-05 2.2E-04 0.OE-01 7.7E-01 9.3E 00 A

I-133 2.3E-04 4.7E-05 2.9E-04 0.0E-01 1.3E 00 4.8E 00 A

C FILTER I-131 2.5E-03 2.7E-04 2.1E-03 0.0E-01 8.7E-01 9.2E 00 A

Rc I-133 1.7E-03 2.2E-04 8.8E-04 0. 0E-0 3. 5.3E-01 7.6E 00 A

P FILTER CS-134 3.7E-04 4.OE-05 2.8E-04 3.OE-05 7.6E-01 9.3E 00 A ,

CHM A CS-137 7.3E-04 4.9E-05 6.4E-04 6.5E-05 8.8E-01 1.5E 01 A  !

I-131 2.9E-04 3.1E-05 2.5E-04 3.3E-05 8.6E-01 9.3E 00 A i

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I-133 2.3E-04 4.7E-05 3.1E 04 4.3E-05 1.4E 00 4.8E 00 A

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CRUD FIL CR-51 7.1E-02 2.6E-03 6.9E-02 3.9E-03 9.7E-01 2.7E 01 A

R C, MN-54 1.1E-03 1.8E-04 8.0E-04 1.1E-04 7.3E-01 6.1E 00 A

FE-59 7.9E-04 3.4E-04 1.1E-03 1.5E-04 1.4E 00 2.3E 00 A

CO-58 2.0E-01 1.1E-03 1.8E-01. 6.8E-03 9.0E-01 1.9E O2 A l

CO-60 1.SE-02 3.8E-04 1.4E-02 5.OE-04 9.1E-01 4.1E 01 A

W-187 3.9E-03 1.2E-Oo c.7E-03 3.4E-04 9.5E-01 3.4E 00 A

NP-239 3.OE-03 3.OE-04 3.7E-03 6.3E-04 1.2E 00 1.OE 01 A

I-131 2.5E-03 2.7E-04 1.9E-03 1.6E-04 7.5E-01 9.2E 00 A

I-133 8.2E-03 4.6E-04 7.9E-03 5.3E-04 9.6E-01 1.8E 01 A

I-135 1.1E-02 1.OE-03 9.5E-03 5.4E-04 8.9E-01 1.0E 01 A

ZR-95 3.2E-03 3.7E-04 2.7E-03 2.OE-04 8.6E-01 8.6E 00 A

ZR-97 2.1E-03 2.4E-04 1.8E-03 1.8E-04 8.7E-01 8.7E 00 A

TE-132 8.7E-04 9.9E-05 6.1E-04 1.3E-04 7.OE-01 8.8E 00 A

P FILTER CS-134 3.7E-04 4.0E-05 2.5E-04 5.1E-04 6.9E-01 9.3E 00 A

CHni CS-137 7.3E-04 4.9E-05 5.4E-04 6.5E-05 7.5E-01 1.5E 01 A

I-131 2.9E-04 3.1E-05 2.5E-04 3.5E-05 8.6F-01 9.3E 00 A

I-133 2.3E-04 4.7E-05 3.OE-04 4.4E-05 1.3E 00 4.8E 00 A

CRUD FIL CR-51 7.1E-02 2.6E-03 6.9E-02 4.5E-03 9.8E-01 2.7E 01 A

CH M i

T TEST RESULTS:

A= AGREEMENT

D= DISAGREEMENT

• = CRITERIA RELAXED

N=NO COMPARISON

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TABLE 3

.U S NUCLEAR REGULATORY COMMISSION

OFFICE OF INSPECTION AND ENFORCEMENT l

CONFIRMATORY MEASUREMENTS PROGRAM l

FACILITY: DAVIS-BESSE i

FOR THE 1 QUARTER OF 1989

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

' SAMPLE ISOTOPE RESULT ERROR RESULT  ; ERROR RATIO RES T

-CRUD FIL MN-04 1.1E-03 .1.8E-04 0.OE-01 0.OE-01 0.OE-01 6.1E 00 D

FE-59 7.9E-04 3.4E-04 1.2E-03 2.5E-04 1.5E 00 2.3E 00 A

CO-58 2.OE-01 1.1E-03 1.9E-01 7.6E-03 9.3E-01 1.9E O2 A

.CO-60 1.5E-02 3.8E-04 1.5E-02 6.4E-04 9.5E-01 4.1E 01 A

W-187 3.9E-03 1.2E-03 4.5E-03 6.7E-04 1.2E 00 3.4E 00 A

I-131 2.5E-03 2.7E-04 1.7E-03 2.5E-04 7.OE-01 9.2E 00 A

I-133- 8.2E-03 4.6E-04 7.7E-03 6.3E-04 9.4E-01 1.'8E 01 A

I-135 1.1E-02 1.OE-03 0.OE-01 0.0E-01 0.0E-01 1.0E 01- D

ZR-95 3.2E-03 3.7E-04 2.8E-03 3.2E-04 8.8E-01 8.6E 00 A

ZR-97 2.1E-03 2.4E-04 1.8E-03 2.7E-04 8.6E-01 8.7E 00 A

TE-132 1.3E-03 1.5E-04 1.1E-03 1.6E-04 8.5E-01 8.8E 00 A

C FILTER I-131 2.5E-03 2.7E-04 2.5E-03 3.1E-04 1.0E 00 9.2E 00 A

CHHg .I-133 1.7E-03 2.2E-04 1.2E-03 2.4E-04 6.9E-01 7.6E 00 A

PRIMARY I-131 3.6E-03 7.9E-05 3.5E-03 2.2E-04 9.7E-01 4.5E 01 A

cgs g I-132- 9.6E-03 1.3E-04 9.1E-03 4.1E-04 1.1E 00 6.5E 01 A

I-133 1.5E-02 9.8E-05 1.5E-02 8.6E-04 1.OE 00 1.5E 02 A

I-135 1.8E-02 3.4E-04 1.8E-02 6.3E-04 9.8E-01 5.3E 01 A

NA-24 1.2E-03 6.7E-05 9.5E-04 1.5E-04 7.9E-01 1.8E 01 A

CS-134 7.1E-04 4.OE-05. 7.'5E-04 7.3E-05 1.1E 00 1.8E 01 A

CS-137 1.4E-03 5.OE-05 1.4E-03 1.4E-04 9.6E-01 2.8E 01 A

W-187 3.6E-03 2.5E-04 4.4E-03 2.5E-03 1.2E 00 1.5E 01 A

C FILTER I-131 2.5E-03 2.7E-04 2.6E-03 3.3E-04 1.1E 00 9.2E 00 A j

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CWH g I-133 1.7E-03 2.2E-04 1.2E-03 2.6E-04 7.4E-01 7.6E 00 A

CRUD FIL CR-51 7.1E-02 2.6E-03 7.3E-02 2.7E-03 1.OE 00 2.7E 01 A

d4M g FE-59 7.9E-04 3.4E-04 1.5E-03 0.OE-01 1.9E 00 2.3E 00 A l

.CO-58 2.OE-01 1.1E-03 2.OE-01 2.2E-03 9.8E-01 1.9E O2 A l

CO-60 1.5E-02 3.8E-04 1.6E-02 4.7E-04 1.OE 00 4.1E 01 A  !

W-187 3.9E-03 1.2E-03 4.7E-03 4.9E-04 1.2E 00 3.4E 00 A

T TEST RESULTS:

A= AGREEMENT  ;

D= DISAGREEMENT

c= CRITERIA HELAXED

N=NO COMPARISON

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TABLE 3 i

U S. NUCLEAR REGULATORY COMMISSION 4

OFFICE OF INSPECTION AND ENFORCEMENT

CONFIRMATORY MEASUREMENTS PROGRAM

FACILITY: DAVIS-BESSE

FOR THE 1 QUARTER OF 1989

---

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

SAMPLE ISOTOPE RESULT ERROR RESULT ERROR RATIO RES T

CRUD FIL I-131 2.5E-03 2.7E-04 2.1E-03 2.2E-04 8.3E-01 9.2E 00 A

I-132 '5.8E-03 9.5E-04 6.3E-03 4.7E-04 1.1E 00 6.1E 00- A

I-133 8.2E-03 4.6E-04 8.7E-03 4.5E-04 1.OE 00 1.8E-01 A

I-135 1.1E-02 1.OE-03 1.1E-02 7.8E-04 1.OE 00 1.OE 01 A

ZR-95 3.2E-03 3.7E-04 2.3E-03 3.5E-04 7.3E-01 8.6E 00 A-

ZR-97 2.1E-03 -2.4E-04 1.9E-03 2.6E-04 8.9E-01 8.7E 00 A

-TE-132 1.3E-03 1.'5E-04 1.OE-03 1.4E-04 7.7E-01 8.8E 00 A

L' WASTE- MN-54 4.3E-06 1'.OE-06 3.6E-06 3.7E-07 8.3E-01 4.2E 00 A

CHH l CO-58 2.3E-05 9.2E-07 2.3E-05 1.2E-06 1.OE 00 2.5E 01 A

CO-60 -6.4E-05 1.4E-06 6.6E-05 2.1E-06 1.OE 00 4.6E 01 A

AG-110M 5.7E-05 1.4E-06 5.2E-05 1.OE-06 9.2E-01 4.1E 01 A

I-131 1.8E-04 2.2E-06 1.7E-04 5.8E-06 9.9E-01 8..E

O 01 A

CS-134 2.2E-04 '2.2E-06 2.1E-04 4.4E-06 9.4E-01 1.OE O2 A

CS-136 1.7E-05 9.9E-07 1.3E-05 4.7E-07 7.8E-01 1.7E 01 A

CS-137 4.6E-04 2.8E-06 4.6E-04 2.2E-05 9.9E-01 1.6E O2 A

PRIMARY. -I-131 3.6E-03 7.9E-05 3.6E-03 2.3E-04 1.OE 00 4.5E 01 A

g e; I-132 8.6E-03 1.6E-04 8.1E-03 3.8E-04 9.4E-01 6.5E 01 A

I-133 1.5E-02 9.8E-05 1.3E-02 7.6E-04 9.1E-01 1.5E O2 A

I-135 1.8E-02 3.4E-04 1.6E-02 5.9E-04 9.2E-01 5.~3E 01 A

NA-24 1.2E-03 6.7E-05 7.9E-04 1.4E-04 6.5E-01 1.8E 01 D

CS-134 7.1E-04 4.OE-05 6.5E-04 6.4E-05 9.3E-01 1.8E 01 A

CS-137 1.4E-03 5.OE-05 1.5E-03 1.4E-04 1.OE 00 2.8E 01 A

W-187 3.6E-03 2.5E-04 3.7E-03 2.6E-04 1.OE 00 1.5E 01 A

OFF GAS KR-85M 2.7E-05 3.2E-06 2.7E-05 3.7E-06 9.9E-01 8.7E 00 A

.c gg g XE-131M 3.1E-04 5.5E-05 2.2E-04 5.6E-05 7.3E-01 5.6E 00 A

XE-133 2.1E-02 5.OE-05 1.8E-02 1.8E-03 8.6E-01 4.2E O2 A

XE-133M 2.3E-04 1.7E-05 2.1E-04 2.5E-05 9.1E-01 1.4E 01 A

XE-135 5.5E-04 6.4E-06 5.4E-04 3.2E-05 9.8E-01 8.5E 01 A

C WASTE MN-54 4.3E-06 1.OE-06 3.2E-06 3.1E-07 7.4E-01 4.2E 00 A

T TEST RESULTS:

A= AGREEMENT

'D= DISAGREEMENT

• =CRfTERIA RELAXED

N=NO' COMPARISON

3

-__ _ - _ _ _ _ _ - _ . _ _

gr.w=- w=--- = :n-==a

. ma g - xww. a < v=.

. . 7-m .a - ~

. .c = .w - . = - , . . - , - - - - -

...

.

e,-.. . . .

,, .- u

, .

(

,

TABLE 3

-U S NUCLEAR REGULATORY COMMISSION-

OFFICE 0F INSPECTION AND ENFORCEMENT

. CONFIRMATORY MEASUREMENTS PROGRAM

FACILITY: DAVIS-BESSE t

FOR THE 1 QUARTER OF 1989

---

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

SAMPLE ISOTOPE RESULT ERROR RESULT ERROR RATIO RES T-

L' WASTE CO-58 2.3E-05 9.2E-07 2.5E-05 6.4E-07 '1.1E 00 2.5E 01. A

cgg A CO-60 6.4E-05 1.4E-06 6.8E-05 8.6E-07 1.1E 00 4.6E 01 A-

AG-110M 5.7E-05 1.4E-06 5.5E-05 5.6E-07 9.6E-01 -4.1E 01 A

I-131 1.8E-04 2.2E-06 1.8E-04 1.7E-06 1.OE 00 .Gl.OE 01 A-

CS-134 2.2E-04 2.2E-06 2.1E-04 1.4E-06 9.8E-01 1.OE O2 A

'CS-136 1.7E-05 9.9E-07 1.3E-05 3.3E-07 7.8E-01 1.7E 01 -A

.CS-137 4.6E-04 2.8E-06 4.7E-04 4.1E-06 1.OE 00 1.6E O2 A

T: TEST RESULTS:

s A= AGREEMENT

D= DISAGREEMENT.

• = CRITERIA RELAXED

N=NO COMPARISON

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L_i____ _._ _ _________ _

'

= ., . -

.

. . - . .

. . - . ~ . _ , . . . _ . . -

__

.

.

,

'

,

, .

.

Y

.

TABLE 3

U S NUCLEAR REGULATORY COMMISSION.

OFFICE OF INSPECTION AND ENFORCEMENT

.

-

CONFIRMATORY MEASUREMENTS PROGRAM

FACILITY: DAVIS BESSE

FOR THE 1 QUARTER OF 1989

I'

i

---

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

' SAMPLE ISOTOPE RESULT ERROR RESULT ERROR RATIO RES T

KR-85M 2.7E-05 3.2E-06 2.4E-05 3.9E-06 8.7E-01 8.7E 00 A

OFF GAS

XE-131M 3.1E-04 5.5E-05 2.7E-04 7.1E-05 8.7E-01 5.6E 00 A

c y pr.; D

XE-133 2.1E-02 5.OE-05 1.7E-02 1.7E-03 8.0E-01 4.2E 02

XE-133M 2.3E-04 1.7E-05 1.9E-04 2.5E-05 8.1E-01 1.4E 01 A  !

XE-135 5.5E-04 6.4E-06 5.2E-04 3.2E-05 9.4E-01 8.5E 01 A l

L WASTE MN-54 4.3E-06 1.0E-06 3.4E-06 3.2E-07 7.8E-01 4.2E 00 A

CO-58 2.5E-05 1.2E-06 1.1E 00 2.5E 01 A

Rc 2.3E-05 .9.2E-07

4.6E 01 A

'CO-60 6.4E-05 1.4E-06 6.8E-05 2.1E-06 1.1E 00

AG-110M 5.7E-05 1.4E-06 5.3E-05 1.0E-06 9.3E-01 4.1E 01 A

I-131 1.8E-04 2.2E-06 1.8E-04 5.7E-06 1.0E 00 8.0E 01 A

CS-134 2.2E-04 2.2E-06 2.1E-04 4.4E-06 9.8E-01 1.0E 02 .A

CS-136 1.7E-05 9.9E-07 1.3E-05 4.5E-07 7.9E-01 1.7E 01 A

CS-137 4.6E-04 2.8E-06 4.7E-04 2.3E-05 1.0E 00 1.6E 02- A

T TEST'RESULTS:

A= AGREEMENT

D= DISAGREEMENT

• = CRITERIA RELAXED

NANO COMPARISON

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l

l

5 1

!

- - - - - - - -. - - - - - - - _ - - - - - _ _ _ _ - - __

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