Text

Insp Rept 50-482/85-36 on 850930-1004.No Violation or Deviation Noted.Major Areas Inspected:Corporate & Onsite Organizations & Mgt Controls,Staffing & Staff Qualifications & Chemistry/Radiochemistry Program
	ML20137K919
Person / Time
Site:	Wolf Creek
Issue date:	11/15/1985
From:	Murray B, Nicholas J, Wise R; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:	;
Shared Package
ML20137K899	List: IR 05000482/1985036; ML20137K893;
References
	50-482-85-36, NUDOCS 8512030316
	Download: ML20137K919 (18)
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APPENDIX

U.S. NUCLEAR REGULATORY COMMISSION

REGION IV

NRC Inspection Report: STN 50-482/85-36

Docket: STN 50-482 License: NPF-42

Licensee: Kansas Gas and Electric Company (KG&E)

P. O. Box 208

Wichita, Kansas 67201

Facility Name: Wolf Creek Generating Station (WCGS)

Inspection At: WCGS Site, Burlington, Kansas .,

Inspection Conducted: September 30-October 4, 1985

Inspectors:

J.,flairNicholas,\SeniorRadiation

Rf/rfff

Date '

Mpecialist, Facilities Radiological

Protection Section

0. A WulAa

Rpjfsell Wise, Radi'ation Specialist,

uhkr

Date

UFacilities Radiological Protection

Section

Approved: 40 OA'N[

BlaineMurray, Chief,/ Facilities

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Radiological Protection Section

Inspection Summary '

Inspection Conducted September 30-October 4, 1985 (Report STN 50-482/85-36)

Areas Inspected: Routine, announced inspection of the licensee's

chemistry / radiochemistry program including review of corporate and onsite

organizations and management controls, staffing and staff qualifications,

training program, chemistry / radiochemistry program, quality assurance (QA)

program of chemistry / radiochemistry activities, facilities and equipment,

0512030316 851115

PDH ADOCK 05000432

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postaccident sampling system (PASS), quality control of analytical

measurements, and whole body counting system confirmatory measurements.

The inspection involved 84 inspector-hours onsite and eight inspector-hours

offsite by two NRC inspectors.

Results: Within the areas inspected, no violations or deviations were

identified.

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Details

1. Persons Contacted

F. T. Rhodes, Plant Manager

G. D. Boyer, Superintendent, Technical Support

L. F. Breshears, Health. Physics Supervisor

H. Chernoff, Licensing Engineer

0. A. Dominques, QA Technician

K. R. Ellison, Regulatory, Quality, and Administration

J. D. Hartley, Chemistry Technician

J. D. Hawthorne, Secondary Chemistry Supervisor

S. A. Henry, Primary Chemistry Supervisor

C. J. Hoch, QA Technician

R. L. Hoyt, Emergency Planning Administrator

J. A. Ives, Site Health Physicist

R. L. Logsdon, Site Chemist

A. S. Mah, Superintendent :f Training

W. C. Manwaring, Instrume.t-s and Controls (I&C)

J. A. Moore, Chemistry Technician

T. S. Morrill, Radiochemist

M. M. Nichols, Superintendent of Plant Support

C. L. Palmer, Radwaste Chemistry Supervisor

C. E. Parry, Superintendent of Quality Systems Engineering

C. G. Patrick, Superintendent of Quality Evaluations

G. J. Pendergrass, Licensing Engineer

K. R. Peterson, Lead Licensing Engineering

C. C. Reekte, QA Auditor

B. D. Reischman, Senior Engineer (Nuclear Chemist), Nuclear Services

C. Rise, Health Physics Operations Supervisor

H. Stubby, Chemistry Training Instruc+or

C. A. Swartzendrubec, Manager of Radiological Services

P. E. Turner, Manager of Nuclear Training

D. Walsh, Maintenance Services Supervisor

R. W. Wollum, I&C Coordinator

J. A. Zell, Superintendent of Operations

M. G. Williams, Superintendent of Regulatory, Quality, and Administration

Others

B. L. Bartlett, NRC Resident Inspector

J. E. Cummins, Senior NRC Resident Inspector

Denotes those present during the exit briefing on October 4, 1985. .

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2. Chemistry / Radiochemistry Organization and Management Controls

The NRC inspectors reviewed the licensee's corporate and onsite

organizations and staffing regarding chemistry / radiochemistry activities

to determine compliance with commitments in Chapter 13, " Conduct of

Operations," in the Final Safety Analysis Report (FSAR) and requirements

in Section 6.2, " Organization," in the Technical Specifications (TS) and

WCGS administrative procedures. The NRC inspectors verified that the

organizational structures of the corporate radiological services section

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and the onsite chemistry / radiochemistry section (C/RS) were as defined in

the FSAR, TS, and WCGS administrative procedures. The NRC inspectors

reviewed the corporate and WCGS management control procedures and position

descriptions for the assignment of responsibilities for the management and

implementation of the WCGS chemistry / radiochemistry program. The NRC

inspectors verified that the administrative control responsibilities

specified by the WCGS procedures were being implemented.

The NRC inspectors reviewed the staffing of the corporate radiological

services nuclear chemistry section and the onsite C/RS and noted that the

corporate nuclear chemistry section was fully staffed and the two staff

members were the same as reported in previous NRC inspection reports.

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Since the previous NRC inspection in April 1985, the onsite C/RS had lost.

its secondary chemistry supervisor and one chemistry technician. The

secondary chemistry supervisor position had been filled by one of the

senior chemistry technicians leaving 14 chemistry technician positions

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filled and two vacancies. The site chemist was actively recruiting to

fill the staff vacancies.

No violations or deviations were identified.

3. Chemistry / Radiochemistry Personnel Qualifications

The NRC inspectors reviewed the qualifications of tha corporate

radiological services nuclear chemistry personnel and onsite C/RS

personnel to determine compliance with commitments in Cnapter 13 " Conduct

of Operations," in the FSAR and requirements in Section 6.3, " Unit Staff

Qualifications," in the TS.

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The NRC inspectors reviewed the resumes for each of the corporate nuclear

chemistry technical support personnel and verified that they met the

I required qualifications specified in the FSAR and position descriptions.

l Based on the review of the onsite C/RS staff resumes, the NRC inspectors

determined that the site chemist, radiochemist, and the three laboratory

supervisors met the ANSI /ANS 3.1-1978 qualifications as committed to in

the FSAR and TS. Eight of fourteen chemistry technician positions were

filled with personnel who satisfied the ANSI /ANS 3.1-1978 qualifications.

The C/RS has eight shift qualified technicians, three technicians who

should be shift qualified by December 1985, and three newly hired

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technicians who were presently in qualification training. The NRC

inspectors determined that the C/RS shift rotation was composed of ANSI

and shift qualified personnel.

No violations or deviations were identified.

4. Chemistry / Radiochemistry Training Program

The NRC inspectors. reviewed the licensee's chemistry / radiochemistry

training program to determine compliance with commitments in Chapter 13.2,

" Training," in the FSAR, and requirements in Section 6.4, " Training," in

the TS, 10 CFR Part 19.12, and WCGS administrative procedures.

The NRC inspectors reviewed the training program for C/RS personnel with

the nuclear training manager and the C/RS training coordinator. The

nuclear training department had added to its staff an instructor with

expertise in nuclear power plant chemistry / radiochemistry. The NRC

inspectors inspected the new training facilities and training chemistry

laboratory.

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The NRC inspectors reviewed the nuclear training department procedures

which had been completed and approved and determined that several WCGS

administrative procedures were still being used to direct nuclear training

department activities until all training department procedures have been

completed. The licensee's program for qualification and training of WCGS

chemistry staff is described in WCGS Procedure ADM-04-004, " Chemistry

Group Training Program," Rev. 6, August 15, 1985. The NRC inspectors

reviewed the licensee's program and found it being implemented in

accordance with the above procedure.

The NRC inspectors reviewed the licensee's task analysis for C/RS

personnel which was in progress.

The nuclear training department had developed a health physics / chemistry

technician course in cooperation with local universities. The NRC

inspectors reviewed the course lecture outline and study materials.

The NRC inspectors reviewed the C/RS individual staff training records and

qualification cards and found that training was being completed and

documented as per procedure.

No violations or deviations were identified.

5. Chemistry / Radiochemistry Program

The NRC inspectors reviewed the licensee's chemistry / radiochemistry

program to determine compliance with commitments in Chapter 5, " Reactor

Coolant System and Connected Systems;" Chapter 9, " Auxillary Systems;" and

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Chapter 11. " Radioactive Waste Management;" and requirements in

Section 3/4.4.7, " Chemistry," in the TS and C/RS procedures.

The NRC inspectors' review of the chemistry / radiochemistry program found

that the licensee had completed and approved all identified administrative

procedures, surveillance procedures, chemical control procedures,

instrument calibration and performance check procedures, sampling

procedures, and analytical procedures. A review of selected procedures,

logs, and analytical data indicated that the C/RS had established

sufficient administrative and analytical procedures to meet the

requirements of the FSAR and TS.

The NRC inspectors verified that the secondary chemistry laboratory

instruments and the primary chemistry laboratory instruments had been

calibrated according to procedures and a quality control program had been

implemented.

The NRC inspectors reviewed the status of the chemical and reagent

inventory program and found the C/RS staff implementing the program in the

laboratories according to procedure.

No violations or deviations were identified.

6. Quality Assurance Program

The NRC inspectors reviewed the licensee's QA organization and

audit / surveillance program regarding chemistry / radiochemistry activities

to determine compliance with commitments in Chapter 17, " Quality Assur-

ance," in the FSAR, requirements in Section 6.5.2.8, " Audits," in the TS,

and QA manual procedures.

The NRC inspectors. reviewed the QA department organization, selected QA

audit and surveillance procedures, audit plans for 1985 and 1986, QA

auditor qualificatibns, and audit and surveillance reports. Audit and

surveillance reports generated from QA activities during 1984 and 1985 in

the areas of chemistry and radiochemistry, chemistry personnel

qualifications, chemistry instrument calibration and quality control, and

system chemical control were reviewed for scope to ensure thoroughness of

program evaluation and timely follow-up of identified deficiencies. The

NRC inspectors found that the audit plans and checklists generated from a

list of essential elements and attributes dealing with

chemistry / radiochemistry activities were comprehensive and that the

responses and corrective actions to QA findings were timely. It was noted

that the chemistry / radiochemistry audits were being performed by an audit

team which included a lead auditor qualified to the requirements of

ANSI /ASME N45.2.23-1978 and a qualified technical specialist knowledgeable

! in chemistry / radiochemistry activities at a nuclear power facility.

No violations or deviations were identified,

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7. Facilities and Equipment

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The NRC inspectors inspected the secondary chemistry laboratory and

sampling area, primary chemistry laboratory and sampling area,

radiochemistry counting room, postaccident sampling area, and radwaste

laboratory and sampling area. The laboratories were equipped with the

necessary chemicals, reagents, standards, labware, and analytical

instrumentation to perform the required analytical procedures. At the

time of the inspection, it was noted that three of the four high purity

germanium (HPG) detectors connected to the Nuclear Data gamma spectroscopy

system and located in the radwaste laboratory and radiochemistry counting

room were temporarily out-of-service for electronic malfunctions.

The NRC inspectors noticed during the inspection that every process

instrument located on the secondary chemistry instrument panel (RM-171)

was not operational. These process instruments included the sodium

analyzers, dissolved oxygen analyzers, conductivity meters, pH cells, and

associated recorders. The NRC inspectors discussed their concerns with

this instrument problem with the licensee and it was emphasized at the

exit briefing that this panel and associated instruments be kept in

current calibration and routine operation to maintain current status of

secondary chemical parameters and provide documentation of secondary

chemistry trends. The licensee acknowledged the NRC inspectors' concerns

with the inoperable instrumentation and stated that the instruments would

be checked and repaired prior to November 8, 1985, subject to availability

of needed parts.

No violations or deviations were identified.

8. Postaccident Sampling System

The NRC inspectors reviewed the licensee's PASS to determine compliance

with the requirements of NUREG-0737, Item II.B.3, and Section 6.8.4.d,

"Postaccident Sampling," in the TS.

The NRC inspectors inspected the areas in the plant where the PAS!

hardware is installed. The NRC. inspectors verified that the equipment and

associated procedures satisfied the requirements of NUREG-0737,

Item II.B.3, and TS for representative sampling and analysis of reactor

coolant and containment atmosphere following a reactor incident. The

licensee had completed operator training as part of shift qualification

training for chemistry technicians and had established an instrument

calibration and maintenance program in compliance with TS requirements.

The NRC inspectors reviewed the in-line instrument calibration and quality

control records. The licensee demonstrated PASS operability by collecting

a sample of reactor coolant and performing required analyses including

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gamma isotopic, pH, boron, and conductivity. The licensee also collected

a sample of containment atmosphere and performed a gamma isotopic

analysis. The licensee demonstrated to the NRC inspectors the use of the

manual local control panel for obtaining an undiluted grab sample for

analyses. The NRC inspectors noted that the reactor coolant system

hydrogen analyzer was out-of-service for repair and the dissolved oxygen

analyzer was due for cell reconditioning. The NRC inspectors verified

that work orders had been issued to maintain these instruments and place

them back in service. The NRC inspectors determined that the licensee's

procedures, analytical sensitivities, and analytical results of chemistry

parameters were consistent with PASS requirements. '

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No violations or deviations were identified.

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Quality Control of Radiological Analytical Measurements

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The NRC inspectors inspected the radiochemistry counting room and reviewed

the licensee's program for calibration and quality control of radiological

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analytical measurements to determine compliance with the requirements in

Section 6.8, " Procedures and Programs," in the TS.

The NRC inspectors examined the licensee's radiochemistry counting room

instrument calibration and quality control procedures, counting instrument

calibration data and performance check data, and other documentation of

instrument performance. Data for the period January through

September 1985 were reviewed.

No violations or deviations were identified.

h 10. -Analytical Measurements

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a. Confirmatory Measurements

Confirmatory measurements were performed on the following samples and

standards in the Region IV mobile laboratory at the WCGS site during

the inspection:

1. NRC Particulate Filter Standard (SRS-17818-109)

2. Containment Atmosphere Charcoal Cartridge

3. Liquid Radwaste Effluent (Waste Tank TH8078)

4. Reactor Coolant System Gas

5. Reactor Coolant System Degassed Liquid

Reactor Coolant System Iodines

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7. Ccc.tainment Atmosphere (1 Liter Gas Marinelli)

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8. Containment Atmosphere (30 cc gas bulb)

9. NRC Face Loaded Scott Charcoal Cartridge (SRS-17817-109)

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10. NRC Tritum Sample

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The confirmatory measurements counting arrangements are essentially

, the same as those discussed in NRC Inspection Report 50-482/84-40.

Attachment 1 contains the criteria used to compare results.

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b. Results

The licensee maintains three HPG detectors in the radiochemistry

counting room and two HPG detectors in the radwaste laboratory. All-

five detectors are used for routine isotopic analysis of radioactive

samples to demonstrate compliance with TS and regulatory

requirements. At the time of the inspection the two HPG detectors in

the radwaste laboratory and one HPG detector in the radiochemistry

counting room were out-of service. The two in-service HPG detectors

were cross-checked on selected count!ag geometries. The HPG detector

labeled (1) is maintained by the C/RS and the HPG detector labeled

(2) is maintained by the health physics section. The analytical

results from the two detectors were compared with the NRC results, as

well as with each other. The licensee performed the tritium sample

analysis on their liquid scintillation counting system. The

individual sample analyses and comparison of analytical results of

the confirmatory measurements are tabulated in Attachment 2.

The licensee's gamma isotopic results from the listed samples in

Attachment 2 showed 94 percent agreement with the NRC analysis

results based on 58 agreement results out of 62 nuclides identified

and compared. The licensee's tritium result on the NRC tritium

sample was in agreement with the NRC analysis result. The licensee's

results cross-checked with 100 percent agreement between the two HPG

detectors for all counting geometries compared.

Confirmatory measurements were performed by the licensee on a liquid

unknown sample prepared by Radiological Environmental Sciences

Laboratory using known nuclide concentrations of sosp, soSr, tritium,

and gamma emitting nuclides. The licensee analyzed the sample and

reported the results as requested. The licensee's analytical results

were compared to the known sample activities and t he results of the

comparisons are presented in Attachment 2, sample 11. The licensee's

results were in 100 percent agreement with the certified activities

in the sample.

No violations or deviations were identified.

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11. Whole Body Counting System

l The NRC inspectors reviewed the licensee's whole body counting system to

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determine compliance with 10 CFR Part 20.103.

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The NRC inspectors reviewed the health physics procedures which provide

guidance in the operation, calibration, and quality control of the whole

body counting system. The licensee's calibration program and QA program

l for the whole body counting system were reviewed. The licensee

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participates in a cross-check program on a qudrterly basis with a

commercial vendor who supplies unknown activities in the phantom

configuration used by the licensee.

The NRC inspectors supplied the 1icensee with a whole body counting

phantom to perform confirmatory measurements in their chair style whole

! body counting system. The counting arrangements were essentially the same

as those discussed in NRC Inspection Report 50-482/84-40. The results of

the body positioning test and the comparison of the analytical results of ,

the confirmatory measurements against the standard activities are

tabluated in Attachment 3.

The results of the body burden activity measurements were approximately

the same as experienced during the tests performed during the NRC

inspection conducted in October 1984. In general, the licensee's results

were approximately 50 percent lower than the certified activities of the

NRC standards.

No violations or deviations were identified.

12. Exit Briefing

Tne NRC inspectors met with the NRC resident inspectors and licensee

representatives identified in paragraph 1 of this report at the conclusion

of the inspection on October 4, 1985. The NRC inspectors summarized the

scope of the inspection and discussed the inspection findings including

the results of the confirmatory measurements performed on various

intercomparison samples and the whole body counting system. The licensee

committed to repair the secondary chemistry process instrumentation on

panel RM-171 by November 8, 1985, subject to availability of needed parts

and have all the instruments calibrated and operational.

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triteria for Comparing Analytical Measurements . !

l The following are the criteria used in comparing the results of capability l

i tests and verification measurements. The criteria are based on an empirical ~

{ relationship established through prior experience and this program's

, analytical. requirements.

!. In these criteria, the judgement ifmits vary in relationship to .the comparison

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of the resolution.

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i NRC VALUE

i Resolution = NRC UNCERTAINTY l

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Ratio = LICENSEE VALUE l

NRC VALUE ,

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Comparisons are made by first determining the resolution and then reading

{ across the same line to the corresponding ratio. The following table shows !

the acceptance values.

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q RESOLUTION AGREEMENT RATIO I

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<4 0.4 - 2.5 ;

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4-7 0.5 - 2.0

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16 - 50 0.75 - 1.33

i 51 - 200 0.80 - 1.25 '

j. >200 0.85 - 1.18

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{ The above criteria are applied to the following analyses:

(1) Gamma Spectrometry.

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} (2) Tritium analyses of 11guld samples,

q (3) Iodine on absorbers.

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3 (4) noSr and 'OSr determinations.

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(5) Gross Beta where samples are counted on the same date using the same l

j reference nuclide.

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ATTACHMENT 2

Confirmatory Measurements Results

1. NRC Particluate Filter Standard (SRS-17818-109)

(Standardized 11:00 CDT, July 1,1985)

WCGS WCGS Results NRC Results WCGS/NRC Comparision-

Nuclide Det. (uci/ Sample) (uCi/ Sample) Ratio Decision

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57Co (1) 1.6610.02E-02 1.9210.01E-02 0.87 Agreement

(2) 1.7910.03E-02 0.94 Agreement

SOCo (1) 4.5210.06E-02 4.7410.04E-02 0.96 Agreement

(2) 4.8110.08E-02 1.02 Agreement (

ssY (1) 1.0910.13E-01 1.1010.01E-01 0.99 Agreement !

(2) 1.1310.02E-01 1.03 Agreement '

108Cd (1) 1.0410.01E+00 1.3110.01E+00 0.80 Disagreement

(2) 1.1310.01E+00 0.86 Agreement

118Sn (1) 6.5210.07E-02 7.1010.04E-02 0.92 Agreement

(2) 7.3510.09E-02 1.04 Agreement

137Cs (1) 4.1810.05E-02 3.6110.02E-02 1.16 Agreement

(2) 4.4610.06E-02 1.24 Agreement '

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taoCe (1) 3.0910.03E-02 3.3910.02E-02 0.91 Agreement

(2) 3.4010.04E-02 1.00 Agreement

20sHg (1) 5.7210.08E-02 6.1910.05E-02 .0.92 Agreement

(2) 6.2710.12E-02 1.01 Agreement

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2. Containment Atmosphere Charcoal Cartridge

(Sampled 12:00 CDT, October 2, 1985) ,

WCGS WCGS Results NRC Results WCGS/NRC Comparision

Nuclide Det. (uCi/ Sample) (uCi/ Sample) Ratio Decision

1811 . (1) 5.1210.18E-03 5.5810.06E-03 0.92 Agreement l

tas! (1) 1.3510.17E-03 1.5310.0SE-03 0.88 A0reement ;

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3. Liquid Radwaste Effluent (Waste Tank TH8078)

(Sampled 16:45 CDT, September 30, 1985)

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l WCGS WCGS Results NRC Results WCGS/NRC Comparision

l Nuclide Oe t. (uC1/ml) (uCf/ml) Ratio Decision

stCr (1) 2.9710.44E-06 2.9910.39E-06 0.99 Agreement

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54Mn (1) 1.3910.31E-07 Not Identified --

No Comparison 1

i ssCo (1) 6.6810.19E-06 6.5110.13E-06 1.03 Agreement .

88Fe (1) 4.2910.86E-07 5.2910.63E-07 0.81 Agreement

osZr (1) 3.1410.81E-07 2.4410.66E-07 1.29 Agreement

1811 (1) 4.4610.71E-07 5.7310.50E-07 0.78 Agreement

1831 (1) 6.0710.79E-07 6.0710.52E-07 1.00 Agreement

140La (1) 7.0111.05E-07 8.6410.64E-07 0.81 Agreement

187W (1) 2.0710.30E-07 2.0710.20E-07 1.00 Agreement

E! No nuclide identification was made by the NRC. Nuclide activity

was less than 10 percent of the isotopic value for liquid as

stated in 10 CFR Part 20, Appendix B, Table II; therefore, no '

comparison was made.

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4. Reactor Coolant System Gas

(Sampled 16:55 CDT, October 1, 1985)

WCGS WCGS Results NRC Results WCGS/NRC Comparision ,

Nuclide Det. (uCf/cc) (uCi/cc) Ratio Decision

41Ar (1) 4.0710.04E-02 1# --

No Comparison

"S"Kr (1) 1.4410.05E-03 1.2710.02E-03 1.13 Agreement

a7Kr (1) 2.9410.14E-03 2.4010.09E-03 1.23 Agreement !

anKr (1) 3.8810.17E-03 3.2510.07E-03 1.19 Agreement

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ssXe (1) 3.7410.12E-03 3.5510.05E-03 1.05 Agreement

186*Xe (1) 4.0310.35E-03 2/ --

No Comparison

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135Xe (1) 6.7210.08E-03 5.8410.04E-03 1.15 Agreement

188Xe (1) 7.58E-03 2/ --

No Comparsion

1 Isotopic peak was present in the spectial data; however, the

gas efficiency calibration used for the analysis did not

include efficiencies for gamma energies greater than 514 kev.

Therefore, no NRC analysis was made and no comparison.

Isotopic activity had decayed to below the lower level of

detectability at the time of sample analysis.

5. Resctor Coolant System Degassed Liquid

(Sampled 15:14 COT, October 1, 1985)

WCGS WCGS Results NRC Results WCGS/NRC Comparision

Nuclide Det. (uct/ml) (uCi/ml) Ratio Decision

24Na (1) 1.8110.05E-03 1.9110.03E-03 0.94 Agreement

naCo (1) 5.6710.42E-04 4.9310.23E-04 1.15 Agreement

anRb (1) 5.7810.43E-03 2.2210.27E-02 0.26 Disagreement

80Rb (1) 5.6110.27E-03 1/ --

No Comparison

'8Nb (1) 2.7510.33E-04 1.4410.19E-04 1.91 Disagreement

"7Nb (1) 9.78E-05 8.9112.56E-05 1.10 Agreement

388Cs (1) 1.1010.02E-02 1.2610.02E-02 0.87 Agreement

188Ba (1) 1.2410.23E-03 1.6810.16E-03 0.74 Agreement

187W (1) 4.52E-04 9.7911.05E-04 0.46 Disagreement

1 Primary line for nuclide identification was not present;

therefore, no nuclide identification and no comparison.

6. Reactor Coolant System lodine Analysis

"(Sampled 16:14 CDI, October 1,198b)

WCGS WCGS Results NRC Results WCGS/NRC Comparision

Nuclide Det. (uci/ml) (ucf/ml) Ratio DecIsfon

tan! (1) 2.4710.24E-04 2,4810.15E 04 1.00 Agreement

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1s21 (1) 5.1410.07E-03 4.6610.05E-03 1.10 Agreement

1881 (1) ,

3.0110.04E-03 2.7510.02E-03 1.09 Agreement

184I (1) 1.0710.02E-02 1.1410.02E-02 0.94 Agreement

185I (1) 5.64 0.15E-03 6.3910.11E-03 0.88 Agreement

7. Containment Atmosphere (1 Liter Gas Marinelli)

(Sampled 10:25 CDT, October 2,1985)

WCGS WCGS Results NRC Results 'WCGS/NRC Comparision

Nuclide Det. (uct/ Sample) (uCf/ Sample) Ratio Decision

41Ar (1) 1.8710.12E-06 1! --

No Comparison

(2) 1.6010.13E-06

183Xe (1) 9.8110.15E-06 9.7310.19E-06 1.01 Agreement

(2) 9.6510.19E-06 0.99 Agreement

tasXe (1) 9.8511.42E-08 8.94tl.95E-08 1.10 Agreement

(2) 9.41tl.64E-08 1.05 Agreement

1 Isotopic peak was present in the spectral data; however, the

gas efficiency calibration used for the analysis did not include

efficiencies for gamma energies greater than 514 kev. Therefore,

no NRC analysis was made and no comparison.

8. Containment Atmosphere (30cc gas bulb)

(Sampled 10:18 COT, October 2,1985)

WCGS WCGS Results NRC Results WCGS/NRC Comparision

Nuclide Det. (uCi/cc) (uC1/cc) Ratio Decision ;

183Xe (1) 4.1810.61E-06 4.31tl.01E-06 0.97 Agreement

,

'

9. NRC Face Loaded Scott Charcoal Cartridge Standard (SRS-17817-109) "

(Standardized 11:00 COT, July 1,1985)

WCGS WCGS Results NRC Results II WCGS/NRC Comparision

Nuclide De t ._ (uct/ Sample) (uci/ Sample) Ratio Decision

87C0 (2) 1.6410.03E-02 1.95E-02 0.84 Agreement

soCo (2) 4.9910.08E-02 4.99E-02 1.00 Agreement

w

r .

. . ,

i

-5-

1

asY (2) 1.2010.02E-01 1.18E-01 1.02 Agreement

108Cd (2) 9.5510.09E-01 1.26E+00 0.76 Agreement

218Sn (2) 7.2610.11E-02 7.42E-02 0.98 Agreement

137Cs (2) 4.5710.07E-02 4.75E-02 0.96 Agreement

188Ce (2) 3.2110.05E-02 3.54E-02 0.91 Agreement

20sHg (2) 6.6510.13E-02 7.08E-02 0.94 Agreement

1!

'

! NRC results were taken from the standard certification

supplied to the Region IV office by the commercial vendor

and traceable to the National Bureau of Standards.

10. NRC Tritium Sample

(Sampled 16:31 CDT, October 1, 1985)

WCGS Results NRC Results WCGS/NRC Comparision

Nuclide (uC1/ Sample) (uCi/ Sample) Ratio _ Decision

,

8H 2.96E-01 2.90E-01 1.02 Agreement

11. RESL Unknown Liquid Sample

(Standarized 12:00 MSi, January 11, 1985)

WCGS Results NRC Results 1 WCGS/NRC Comparision

Nuclide (uCi/ml) (uCi/ml) Ratio Decision

8H 6.8910.39E-05 6.5410.13E-05 1.05 Agreement

soSr 3.1210.09E-04 2.7510.08E-04 1.13 Agreement

80Sr 2.2810.19E-05 3.0310.12E-05 0.75 Agreement

is7Cs 1.3810.06E-05 1.3610.03E-05 1.01 Agreement

60Co 1.2610.07E-05 1.2210.02E-05 1.03 Agreement

1 NRC results were taken from the standard certification

supplied to the Region IV office as prepared by RESL

and traceable to the National Bureau of Standards. ,

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L

ATTACHMENT 3

Whole Body Countina System Confirmatory Measurements

1. Positioning Verification Test

'

NRC Whole Body Phantom With 5 Percent Lung Burden Standard

' Tests (1), (2), and (3)

WCGS Result WCGS Result WCGS Result Standard

Nuclide Test (1) Test (2) Test (3) Average Deviation

60Co 0.274 0.292 0.310 0.292 0.018

2. Analytical Measurements

a. Luna Test

NRC Whole Body Phantom With Various Lung Organ

Burden Activities of Cobalt-60

WCGS Results NRC Results* WCGS/NRC

Test No. % MP08 (uC1) (uC1) Ratio

4 5% 0.307 0.500 0.61

5 10% 0.572 1.000 0.57

6 50% 2.488 5.000 0.50

7 100% 4.584 10.000 0.46

8 200% 9.040 20.000 0.45

b. Thyroid Test

NRC Whole Body Phantom With Various Thyroid Oraan

Burden Activities of Barium-133 as Mock Iodine-131

WCGS Results NRC Results* WCGS/NRC

Test No. % MPOB (uci) (uCl) Ratio

9 5% 0.016 0.036 0.44

10 10% 0.033 0.070 0.47

_.

_ .

o .. ..

-2-

11L 50% 0.168 0.350 0.48

12 100% 0.363 0.700 0.52

13 200% 0.686 1.400 0.49

c. Luna and Thyroid Scan

NRC Whole Body Phantom With Various Combinations of Luna

and Thyroid Organ Burden Activities of Cobalt-60 in the

Lunas and Barium-133 as Mock Iodine-131 in the Thyroid

WCGS Results NRC Results* WCGS/NRC

Test No. Nuclide % MP0B (uCI) (uC1) Ratio

14 133Ba 200% 0.709 1.400 0.51

60Co 10% 0.517 1.000 0.52 r

15 183Ba 100% 0.335 0.700 0.48 l

SoCo 10% 0.507 1.000 0.51 '

I

16 183Ba 100% 0.332 0.700 0.47 '

60Co 5% 0.263 0.500 0.53

17 188Ba 5% 0.018 0.036 0.50 ,

ooCo 5% 0.263 0.500 0.53

d. Luna ' Text (mixed isotopic standards)

NRC Whole Body Phantom With Various Luna Organ ,

,

Burden Activities of Cesium-137 and Cobalt-60 '

WCGS Results NRC Results* WCGS/NRC

Test No. Nuclide % MPOB (uC1) (uC1) Ratio ,

3

18 837Cs 5% 0.825 1.570 0.53

80Co 5% 0.201 0.502 0.40

19 187Cs 10% 1.677 3.130 0.53

80Co 10% 0.457 1.000 0.46

20 137Cs 50% 7.51 15.70 0.48

80Co 50% 2.03 5.02 0.40

NRC values were taken from the standard certificates

supplied with the standards as prepared by a commercial

vendor and verified by the NRC's reference laboratory.

RESL, in Idaho Falls, Idaho,

t

l

._

ML20137K919

Text

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