ML20155D410

Insp Rept 50-483/88-08 on 880502-06.No Violations or Deviations Noted.Major Areas Inspected:Confirmatory Measurements & Radiological Environ Monitoring Programs, Including Plant Chemistry,Organization & Mgt Control

ML20155D410
Person / Time
Site:	Callaway
Issue date:	05/31/1988
From:	Bocanegra R, Januska A, Schumacher M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20155D407	List: ML20155D404 ML20155D410
References
50-483-88-08, 50-483-88-8, NUDOCS 8806150161
Download: ML20155D410 (10)

See also: IR 05000483/1988008

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U. S. NUCLEAR REGULATORY COMMISSION

REGION III

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. Report No. 50-483/88008(DRSS)

Occket No. 50-483 License No.- NPF-30

Licensee: Union Electric Company

Post Office Box 149

St. Louis, MO 63166

Facility Name: Callaway Plant, Unit 1

8

Inspection At: Callaway Site, Steedman,' Missouri

Inspection Conducted: May 2-6, 1988

hA, a,w s/n .

Inspector: inuska 0-29-88

Date r

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Accompanied By: R.'Bocanegra 7/!gy

Date

f,b:h/~J/uu'

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Approved By: M.~ Schumacher, Chief 'MF

Radiological Effluents Date

and Chemistr/ Section

Inspection

f Summary

Inspection on May 2-6,1988 (Report No. 50-483/88008(ORSS))

Areas Inspected: Routine, announced inspection of confirmatory measurements,  :

and Radiological Environmental Monitoring programs including: plant chemistry L

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organization, management controls,-trainin and qualifications (IP 83722,

83723); quality assurance and confirmatory measurements for in plant

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radiochemical analysis (IP 84725); and radiological environmental monitoring

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(IP 80721). Collection of collocated thermoluminescent dosimeter (TLD)

measurement resuits (TI 2500/22, IP 80721) was performed and the licensee's

. action on an open item was reviewed.

Results: Management attention to detail in radiological measurements has

resulted in an cverall strong program; however, timeliness in completing

calibration confirmation tests and inspector-observed poor laboratory '

. practices need to be addresse d . No viol ations or' deviations were

identified during this inspection.

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8806150161 880531

PDR .ADOCK 05000483

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OETAILS

1. Persons Contacted

• W. R. Robinson, Assistant Plant Manager

• D. R. Bromwell, QA Engineer

• J. C. Gearhart, Superintendent, QA Operations Support

• C. Graham, Supervisor, Health Physics Technical Support

• F. J. Forck, QA Scientist

• J. R. Peevy, Assistant Manager, Technical Services

• C.' A. Riggs, Supervisor, Chemistry

• R. 'R. Roselius, Superintendent, Health Physics

• E. M. Thornton, QA Engineering Evaluator

• M._A. Trusty, Acting Counting Room Foreman

J. D. Nurrenbern, Health Physicist

G. Clark, Senior Rad / Chem Technician

R. Seitz, Rad / Chem Technician

L. Godley, Rad / Chem Technician

P. Bell, Chemist

• B. H. Little, NRC Senior Resident Inspector

,

• Denotes those present at the exit meeting.

2. Licensee Action on Previous Inspection Findings

(Closed) Open item (483/87016-01): Licensee to complete changes in'the

QA/QC program. QC ch rt limits to be modified, boron QC charts and

control sample results tabulated by July 25, 1987. The licensee has

revised procedures to address the concerns in this open item. The

licensea now determines the standard deviation (s.d.) and the upper

and lower warning and control levels every six months using a minimum

of 15 current data points for key parameters defined in CDP-ZZ-00700.

Perfortince check data for each key parameter is recorded on a "Control

Chart D:ta Sheet." The boron control chart data indicated that the

six months update of the s.d. and control and warning levels had been

performed. The licensee now uses independent sources to check stability

of standards by assuring that, as a minimum, different lot numbers for

calibration standards and control standards are used. There has been no

change in the status of obtaining a computer for tabulation and analysis

of data.

3. Management Controls and Organization (IP 83722, 83723)

The inspectors reviewed the management controls and organdzation cf the

Health Physics Technical Support (n?T5) Group. The group is headed by

a HPTS Supervisor who reports to the Health Physics Superintendent who

in turn reports to the Assistant Manager Technical Services. The HPTS

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Supervisor supervises a Rad / Chem Foreman who in turn supervises 11 Rad / Chem

Technicians (RCT) and their activities in the laboratory and counting room.

During this inspection an RCT was appointed Acting Rad / Chem Foreman during

the absence of the Rad / Chem Foreman. Since the inspection in May 1986

(Report No. 86014) one RCT has lef t Union Electric Company, one has

j transferred, and two have been promoted to another group. Three

I experienced RCTs have transferred into the group leaving the group with a

I net. loss of one RCT. The licensee has eliminated this vacant RCT position.

No violations or devfations were identified.

4. Confirmatory Measurements (IP 84725)

a. Quality Assurance

The inspectors reviewed the radioactivity measurements laboratory

quality assurance program including the ohysical facilities,

latuatory operations, and procedines. Pertinent laboratory and

counting room operating procedures found in Health Physics Department

Procedures (HDP) and Health Physics Technical Procedures (hip) were

reviewed for technical content by the inspectors. Procedures reviewed

included Count Room Quality Control Program (HOP-ZZ-04700), Calibration

of Intrinsic Germanium Detectors (HTP-ZZ-04538), Count Room Analytic

and Quality Control Calculations and Methods (HTP-ZZ-06020), and

Operation of the Gamma Spectroscopy Counting System (HTP-ZZ-04537).

The inspectors also reviewed Quality Control records and related

supporting documentation. Documents inspected included results for

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germanium detector calibratier. and efficiency tables. The inspectors

also verifitd that calibrations for release geometries had been

confirmed semiannually per HTP-ZZ-04538 4.8. However, the insp -tors

expressed concern to the licensee that the latest confirmation tests

of detector calibrations performed in January 1988 had not been closed

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out. Charcoal and planchette geometry confirmation tests showed some

inconsistencies that had not been resolved by the licensee. The

licensee will giva priority to completing the last confirmation tests

and will initiat9 a change in p"ocedure to require completion of

future confirmation tests within a reasonable length of time.

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The licensee participates in a quarterly intercomparison crosscheck

program with an outside vendor. Some of these samples are forwarded

to the licensee's contract laboratory f or Sr-89, Sr-90, and Fe-55

analyses. A review of the fourto quarter 1986 results for these

specific analyses showed the t.ontract laboratory achieved one out

. of three agreements. A licasee assessment (UOTH-87-154) of the

ccatract laboratory's past perferniance resulted in a new laboratory

being selected for future analyses. The 1987 intercomparison

results showed a marked improvement. Crosscheck program results

for in-house gamma-ray analysi t for tM rd quarter 1986, first

quarter 1987, and first quarter 1988, were reviewed. The results

were centrally good with some minor disagreements.

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Daily QC charts for the germanium detectors were inspected. he

Health Physicist responsible for interpreting and evaluating the

charts was interviewed by an inspector and appeared to be competent

and knowledgeable in this area. Rad / Chem Technicians were observed

and evaluated on sample acquisition and preparation, and general

laboratory practices. One technician was observed pouring low level

radioactive liquid into a container without wearing gloves. The

licensee acknowledged the inspectors' concern and agreed to discuss

the laboratory practices with Rad Chem personnel,

b. Sample Split

Six samples (air particulate, charcoal absorber, charcoal spike,

reactor coolant, liquid waste and gas) were analyzed for gamma

emitting isotopes by the licensee and in the Region III mobile

laboratory on site. Comparisons were made on combinations of

the licensee's four normally used count room detectors and on

a back up system in the E0F. Results of the sample comparisons

are given in Table 1; comparison criteria are given in Attachment 1.

The licensee achieved 87 agreements out of 89 comoarisons.

A containment air particulate, a liquid waste monitor tank, a reactor

coolant and a gas sample yielded all agreements. The licensee agreed

to analyze or have a portion of the liquid sample analyzed for gross

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

to Region III (0 pen _ Item 50-483/88008-01).

A containment charcoal absorber yielded a disagreement on Detector 2

and on the E0F detector for Br-82. In addition to the disagreement,

the iodine comparisons, although agreements, were biased low. A

spiked charcoal absorber was analyzed as an unknown on Detector 2

and by the inspectors resulting in all agreements. The inspectors

then demonstrated to the licensee that activity distribution on the

sample and the calibration standard were not the same which caused

the low bias in the analyses. The licensee was cautioned of the

potential for under reporting halogen fission products in samples

collected under abnormal conditions. The licensee acknow' edged

the inspectors comments.

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c. Audits

The inspectors reviewed several surveillance reports and audit recorts

related to radiochemistry. There were no findings made relating r.c

confirmatory measurements. The inspector also noted the high qunity

of the surveillance reports and, in particular, the technical qtality

of "Surveillance of EBAR" performed in January 1988.

No violations or deviations were noted.

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5. Environmental Protection (IP 80721)

The inspectors reviewed the radiological portion of the licensee's "Annual

Environmental Operating Report" for 1986 and 1987. The levels of

radioactivity in the samples collected around the plant were generally

consistent with previous data. There appears to be no evidence that the

plant operation has had any significant environmental impact.

No violations or deviations were identified.

6. ~ Collocated TLD Verification (TI 25000/22, IP 80721)

The inspectors exar,1,cd ten locations where licensee and NRC dosimetet s

were thought to be collocated. Eight of the locations appeared close

enough in distarce and azimuth to be so regarded. NRC TLD Stations

Nos. 8 and 27 were not collocated with Licensee's Stations Nos. 47

and 15, respectively.

No violations or deviations were identified.

7. Open Items

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

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

on the part of the NRC or licensee or both. An open item disclosed during

the inspection is discussed in Section 4b.

8. Exit Meeting

The inspectors met with licensee representatives' denoted in Section 1

at the conclusion of the inspection on May 6, 1988. The scope of the

inspection and findings were discussed.

During the inspection the inspectors discussed the likely informational

content of the inspection report with regard to documents or processes

reviewed by the inspectors during the inspection. Licensee represen-

tatives did not identify any such documents or procedures as proprietary.

Attachments:

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1. Attachment 1, Criteria for

Comparing Analytical

Measurements

, 2. Table 1, Confirmatory Measurements

2

Program Results, 1st Quarter 1988

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-ATTACHMENT 1

CRITERIA FOR COMPARING ANALYTICAL MEASUREMENTS

This attachment provides criteria for comparing results of capability tes.ts

and verification measurements. The criteria are based on an empirical

relationship which combines prior experience and the accuracy needs of this

program.

In these criteria, the judgment limits are variable in relation to the com-

parison of the NRC's value to its associated one signa uncertainty. As that

ratio, referred to in this program as "Resolution", increases, the acceptability

cf 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 to

maintain statistical consistency with the number of significant figures reported

by the NRC Reference Laboratory, ualess such rounding will result in a narrowed

category of acceptance.

RESOLUTION RATIO = LICENSEE VALUE/NRC REFERENCE VALUE

Agreement

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<3 No Comparison

2;3 and <4 0.4 -

2.5 ,

2,4 and <8 0.5 -

2.0

jd) and <16 0.6 -

1.67

2J6and <51 0.75 - 1.33

251 and <200 0.80 - 1.25

.g200 0.85 - 1.18

Some discrepancies may result from the use of different equipment, technique?,

and for some specific nuclides. These may be factored into the acceptance

criteria and identified on the data sheet.

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TABLE 1

U S NUCLEAR RFGULATORY COMMISSION

OFFICE OF INSPECTION AND ENFORCEMENT

CONFIRMATORY MEASUREMENTS PROGRAM

FACILITY: CALLAWAY

FOR THE 2 OUARTER OF 1993

---

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

SAMPLE ISOTOPE RESULT ERROR RESULT EPROR RATIO RES T

PRIMARY NA-24 1.2E-03 4.6E-05 1.2E-03 5.0E-05 9.7E-01 2.6E 01 A

b6Tl CR-51 4.0E-03 3.5E-04 3.4E-03 2.9E-04 3.7E-01 1.!E 01 A

MN-54 5.1E-04 4.0E-05 6.0E-04 3.8E-05 1.2E 00 1.3E 01 A

CO-58 4.0E-03 6.2E-05 3.5E-03 6.!E-05 8.7E-01 6.5E 01 A

CO-60 3.4E-04 2.9E-05 3.2E-04 2.8E-05 9.3E-01 1.2E 01 A

I-131 5.7E-03 6.6E-05 5.GE-03 6.4E-05 1.0E 00 8.6E 01 A

I-132 4.5E-03 7.4E-05 4.4E-03 7.3E-05 9.8E-01 6.0E 01 A

I-133 1.!E-02 7.9E-05 1.!E-02 0.3E-05 9.9E-01 1,4E 02 A

I-135 4.9E-03 1.6E-04 4.8E-03 1.7E-04 9.8E-01 3.1E 01 A

CS-137 5.3E-04 3.8E-05 4.7E-04 3.4E-05 S.7E-01 1.4E 01 A

P FILTER CR-51 6.8E-12 6.8E-13 6.8E-12 3.5E-13 1.0E 00 1.0E 01 A

MN-54 5.7E-13 6.8E-14 5.4F-13 4.5E-14 9.5E-01 0.4E 00 A

b6f4 1.1E 00 3.2E 01 A

CO-58 6.0E-12 1.9E-13 6.3E-12 1.3E-13

CO-60 6.2E-13 6.8E-14 5.9E-13 5.3E-14 9.6E-01 9.1E 00 A

I-131 6.4E-13 6.9E-14 4.7E-13 0.0E-01 7.3E-01 9.2E 00 A

ZR-95 7.0E-13 1.2E-13 5.3E-13 6.6E-14 7.5E-01 5.9E 00 A

NB-95 6.1E-13 8.4E-14 6.0E-13 4.7E-14 9.9E-01 7.3E 00 A

MO-99 1.7E-12 4.7E-13 1,5E-12 3.1E-14 9.3E-01 3.5E 00 A

CS-134 4.6E-13 1.2E-13 2.7E-13 4.3E-14 5.9E-01 3.9E 00 A

CS-137 1.2E-12 1.2E-13 9.2E-13 6.0E-14 8.0E-01 9.9E 00 A

CE-144 6.8E-13 6.7E-1; 7.2E-13 1.3E-13 1.0E 00 1.0E 01 A ,

HF-181 3.3E-13 9.5E-14 2.4E-13 0.0E-01 7.3E-01 3.5E CO A

. PRIMARY NA-24 1.2E-03 4.4E-05 1.2E-03 3.4E-05 9.8E-01 2.7E 01 A

l CR-51 3.1E-03 3.3E-04 3.8E-03 2.0E-04 1.2E 00 9.4E 00 A

b 67'3 3.9E-05 7.9E-01 1.7E 01 A

MN-54 8.3E-04 4.8E-05 6.5E-04

CO-58 3.9E-03 6.0E-05 4.0E-03 5.0E-05 1.0E 00 6.5E 01 A

CO-60 3.9E-04 2.8E-05 3.0E-04 2.3E-05 7.7E-01 1.4E 01 A

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I-131 5.8E-03 6.8E-05 5.9E-03 5.5E-05 1.0E 00 8.5E 01 A

I-132 4.4E-03 6.3E-05 4.6E-03 5.6E-05 1.0E 00 6.9E 01 A

I-133 1.1E-02 7.8E-05 1.2E-02 7.0E-05 1.0E 00 1.4E 02 A

T TEST RESULTS:

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AoAGREEMENT i

D: DISAGREEMENT

ocCRITERIA RELAXED

N:NO COMPARISON

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TABLE 1

U S NUCLEAR REGULATORY COMMISSION

OFFICE OF INSFECTION AND ENFORC.EMENT

CONFIRMATORY MEASUREMENTS PROGRAM

FACILITY CALLAWAY

FOR THE 2 OUARTER OF 1930

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

SAMPLE ISOTOPE RESULT ERROR RESULT ERROR RATIO REG T

PRIMARY I-135 5.3E-03 1.7E-04 5.1E-03 1.4E-04  ?.5E-01 3.1E 01 A

D6r 3 cour.CS-134 1. ' +E-04 3.0E-05 1.3E-04 2.5E-05 5.3E-01 4.6E 00 A

CS-137 5.4E-04 3.8E-05- 5.3E-04 2.7E-05 9.9E-01 1.4E 01- A ,

P-FILTER CR-51 6.8E-12 6.8E-13 6.4E-12 3.5E-13 9.5E-01 1.0E 01 A

14r CO-58 6.0E-12 1.9E-13 5.7E-12 1.2E-13 9.5E-01 3.2E 01 A

MN-54 5.7E-13 6.8E-14 6.0E-13 5.2E-14 1.0E 00 8.4E 00 A

CO-60 6.2E-13 6.8E-14 5.7E-13 5.3E-14 9.3E-01 9.1E 00 A

I-131 6.4E-13 6.9E-14 6.0E-13 0.0E-01 c.4E-01 9.2E 00 A

ZR-95 7.0E-13 1.2E-13 6.5E-13 7.5E-14 9.3E-01 5.9E 00 A

NB-95 6.1E-13 8.4E-14 5.8E-13 5.oE-14 C.5E-01 7.3E 00 A

MO-99 1.7E-12 4.7E-13 1.5E-12 3.2E-14 9.3E-01 3.5E 00 A

CS-134 4.6E-13 1.2E-13 2.8E-13 4.4E-14 6,2E-01 3.9E 00 A

CS-137 1.2E-12 1.2E-13 9.4E-13 6.3E-14 8.1E-01 9.9E 00 A

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CE-144 6.8E-13 6.7E-14 6.2E-13 1.3E-13 9.0E-01 1.0E 01 A

HF-181 3.3E-13 9.5E-14 1.5E-13 0.0E-01 4.4E-01 3.5E 00 A

C FILTER BR-82 1.3E-11 4.8E-13 8.5E-12 2.1E-13 6.8E-01 2.6E 01 D

I-131 5.5E-11 6.8E-13 4.9E-11 3.3E-13 9.0E-01 8. E 01 A

barA I-133 3.4E-12 3.!E-13 2.9E-12 1.!E-13 8.7E-01 1.1E 01 A

L WASTE CR-51 2.2E-05 2.1E-06 2.7E-05 1.3E-06 1.2E 00 1.1E 01 A

gop MN-54 5.9E-06 3.1E-07 5.5E-06 1.2E-07 9.3E-01 1.9E 01 A

FE-59 1.2E-06 2.7E-07 1.4E-06 1.7E-07 1.2E 00 4.3E 00 A

CO-58 3.!E-05 3.8E-07 2.8E-05 2.0E-07 9.2E-01 0.!E 01 A

CO-60 2.1E-06 1.5E-07 2.2E-06 9.5E-08 1.0E 00 1.4E 01 A

W-187 1.6E-06 7.7E-07 2.3E-06 3,0E-07 1.4E 00 2.1E 00 A >

I-131 1.0E-04 6.0E-07 9.8E-05 3.2E-07 9.5E-01 1.7E 02 A

I-132 1.3E-05 8.2E-07 1.2E-05 3. 4 E-07 9. 2E- 01 1.6E 01 A

I-133 1.3E-04 6.9E-07 1.2E-04 3.5E-07 9.3E-01 1.9E 02 A

I-135- 4.!E-05 1.3E-06 3.9E-05 7.3E-07 9,4E-01 3.1E 01 A

CS-134 4.1E-06 3.2E-07 3.9E-06 1.3E-07 9.4E-01 1.3E 01 A

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T TEST RESULTS

AoAGREEMENT

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DoDISAGREEMENT

CaCRITERIA RELAXED

N:NO COMoARISON

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TABLE 1

U S NUCLEAR PEGlLATORY COMMISSION ,

OFFICE OF INSPECTION AND ENFORCEMENT

CONFIRMATORY NEASUREMENTS PROGRAM

FACILITY: CALLAWAY

FOR THE 2 OUAPTER OF 1909

---

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

SAMPLE ISOTOPE RESULT ERROR RESULT ERRCR RATIO RES T

'L WASTE CS-136 2.GE-06 2.2E-07 2.8E-06 1.2E-07 1.0E 00 1.3E 01 A

2.9E-07 1.5E-05 1.5E-07 9.4E-01 5.6E 01 A

- 6c5 Cour CS-137 1.6E-05

C FILTER BR-82 1,3F-11 4.8E-13 8.3E-12 2.1E-13 6.6E-01 2.6E 01 D

yor I-131 5.5E-!! 6.8E-13 4.6E-11 3.0E-13 0.3E-01 8.1E 01 A

I-133 3.4E-12 3.1E-13 2.6E-12 1.2E-13 7.8E-01 1.1E 01 A

OFF GAS XE-133 7.8E-04 1.5E-05 7.7E-04 1.4E-06 1.0E 00 5,3E 01 A

9pcra XE-135 1.8E-05 2.1E-06 1.7E-05 1.3E-07 9.1E-01 8.7E 00 A

C SPIKED CO-57 9.2E-03 1.7E-04 9.7E-03 9.4E-05 1.1E 00 5.4E 01 A

16TA CO-60 2.0E-02 5.8E-04 1.9E-02 3.3E-04 9.9E-01 3.4E 01 A

HG-203 6.3E-03 2.5E-04 6.6E-03 1.2E-04 1.0E 00 :2. LE 01 A

Y-88 2.'1E-02 6.5E-04 2.1E-02 3.2E-04 1.0E OD 3.2E 01 A -

CD-109 5.2E-01 6.4E-03 5.5E-01 3.5E-03 1.1E 00 8.1E 01 A

SN-113 1.3E-02 3.9E-04 1.4E-02 2.1E-04 1.1E 00 3.3E 01 A

CS-137 1.8E-02 5.5E-04 2.0E-02 2.7E-04 1.1E 00 3.3E 01 A

CE-139 7.3E-03 2.0E-04 7.6E-03 9.8E-05 1.0E 00 3.6E 01 A

.OFF GAS XE-133 7.6E-04 1.4E-05 7.8E-04 1.2E-06 1.0E 00 5.4E 01 A

g e73 XE-135 1.4E-05 1.7E-06 1.7E-05 1.2E-07 1.2E 00 8.4E 00 A

L WASTE NA-24 1.0E-05 3.2E-07 1.0E-05 1.9E-07 1.0E 00 3.2E 01 A

t er 4 CR-51 2.7E-05 2.0E-06 2.8E-05 1.6E-06 1.0E 00 1.3E 01 A

MN-54 5.4E-06 2.6E-07 4.2E-06 1.4E-07 7.SE-01 2.1E 01 A

CO-58 3.0E-05 4.1E-07 2.9E-05 2.6E-07 9.6E-01 7.4E 01 A

CO-60 2.0E-06 2.2E-07 2.3E-06 1.1E-07 1.1E 00 9.#E 00 A

U-187 2.4E-06 6.BE-07 3.1E-06 0.0E-01 1.3E 00 3.3E 00 A

I-131 1.0E-04 6.3E-07 1.0E-04 3.7E-07 9.9E-01 1.7E 02 A

I-132 1.3E-05 3.5E-07 1.3E-05 1.9E-07 9.9E-01 3.8E 01 A

I-133 1.3E-04 6.5E-07 1.3E-04 4.1E-05 9.7E-01 2.0E 02 A

I-135 3.9E-05 1.2E-06 4.0E-05 7.2E-07 1.0E 00 3.2E 01 A

i

T TEST RESULTSt

, AnAGREEMENT

! DsDISAGREEMENT

l osCRITERIA RELAXED

i NsNO COMPARISON

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TABLE 1

U S NUCLEAR REGULATORY COMMISSION ,

,

OFFICE OF~ INSPECTION AND ENFORCEMENT ~

CONF!RMATORY MEASUREMENTS PROGRAM

FACILITY

CALLAWAY

I FOR THE 2 GUARTER OF 1908

y ------NRC------- ----LICENSEE---- ---LICENSEE 1NRC----

' SAMPLE ISOTOPE RESULT ERROR RESULT ERROR RATIO REG T

L WASTE CS-134 4.0E-06 2.5E-07 3.9E-06 1.7E-05 1.0E 00 1.6E 01 A

gg7 k ofS-136 3.4E-06 2.4E-07 3.2E-06 1.6E-07 9.3E-01 1.4E 01 A

CS-137 1.SE-05 3.2E-07 1.6E-05 1.9E-07 1.OE 00 4.7E 01 A ,

T TEST RESULTS -

AoAGREEMENT

beDISAGREEMENT -

i

1 c= CRITERIA RELAXED'

NANO' COMPARISON ,

.

J

l

-4- [

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