IR 05000482/1986023

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Insp Rept 50-482/86-23 on 860929-1003.No Violations or Deviations Noted.Major Areas Inspected:Chemistry/ Radiochemistry Program,Including Review of Corporate & Onsite Organizations & Mgt Controls & Staffing
ML20213E592
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 10/29/1986
From: Murray B, Nicholas J, Wise R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20213E566 List:
References
50-482-86-23, NUDOCS 8611130223
Download: ML20213E592 (17)


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J APPENDIX U.S. NUCLEAR REGULATORY COMMISSION

REGION IV

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NRC Inspection Report:- STN 50-482/86-23 License:

NPF-42

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Docket:

STN 50-482

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 i

Inspection Coqducted:

September 29 through October 3, 1986 i

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Inspectors:

lo[LTk$

J. B. Nicholas, Senfor Radiation Specialist, Date

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f Facilities Radiological Protection Section 10hfM

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b, Radiation Specialist, Facilities R

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Radiological Protection Section

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/JfE9k Approved:

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B.Muria), Chief, Faci [itiesRadiological Dat'e Protection Section

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i Inspection Summary Inspection Conducted September 29 through October 3, 1986 (Report SIN 50-482/86-23)

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Areas Inspected:

Routine, unannounced inspection of the licensee's

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chemistry / radiochemistry program including review of corporate and onsite

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organizations and management controls, staffing and staff qualifications,

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

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program of chemistry / radiochemistry activities, facilities and equipment, i

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8611130223 861107 DR ADOCK 05000482 PDR

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postaccident sampling system (PASS), quality control of radiological analytical measurements, and radiochemistry confirmatory measurements.

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

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-3-DETAILS

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1.

Persons Contacted s

KG&E

  • G. L. Koester, Vice President, Nuclear F. T. Rhodes, Plant Manager
  • G. D. Boyer, Deputy Plant Manager J. A. Bailey, Director, Engineering and Technical Services
  • L. E. Borders, Shift Supervisor
  • H. Chernoff, Licensing Engineer
  • T. M. Damashek, Quality Systems Engineer
  • T. F. East, Chemistry Training Specialist M. Estes, Superintendent, Operations s
  • A. A. Freitag, Manager, Nuclear Plant Engineering

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  • R. M. Grant, Director, QA l

J. D. Hartley, Chemistry Technician S. A. Henry, Primary Chemistry Supervisor

  • C. J. Hoch, QA Technician
  • R. L. Hoyt, Senior Engineering Specialist, Operations
  • J. A. Ives, Site Health Physicist W. M. Lindsay, Supervisor, Quality Systems R. L. Logsdon, Site Chemist L. K. Loney, Engineering Specialist, Nuclear
  • A. S. Mah, Superintendent, General Training
  • 0. L. Maynard, Manager, Licensing
  • T. S. Morrill, Chemistry Supervisor

G. A. McClelland, QA Auditor C. L. Palmer, Radwaste Chemistry Supervisor C. E. Perry, Superintendent, Quality Systems Engineering C. G. Patrick, Superintendent of Quality Evaluations W. D. Pyle, Radiochemistry Counting Room Coordinator

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  • G. J. Pendergrass, Licensing Engineer K. R. Peterson, Licensing Lead Engineer l

W. J. Rudolph Il Manager, QA

  • R. M. Stambaugh, Supervisor, QA Audits
  • H. L. Stubby, Chemistry Training Program Coordinator
  • M. G. Williams, Superintendent of Regulatory, Quality, and Administration
  • J. A. Zell, Manager, Nuclear Training Others
  • B. L. Bartlett, NRC Resident Inspector, Wolf Creek

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  • J. E. Cummins, Senior NRC Resident Inspector, Wolf Creek
  • E. A. Plettner Jr., NRC Resident Inspector, Cooper

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  • Denotes those present during the exit briefing on October 3,1986.

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Inspector Observations The following are observations the NRC inspectors discussed with the licensee during the inspection and at the exit briefing on October 3, 1986. These observations are neither violations nor unresolved items.

These items were recommended for licensee consideration for program improvement, but they have no specific regulatory requirement.

The licensee stated these items would be reviewed.

a.

Chemistry / Radiochemistry Training Records - The backlog of themistry/ radiochemistry training records needs to be transmitted to the nuclear training dersrtment for permanent record storage (see paragraph 5).

b.

Documentation of Corporate Reviews - The licensee should document the performance of technical reviews performed by the radiological services section (see paragraph 6).

c.

Contractor Laboratory Analytical Results - The licensee should followup on contractor laboratory analytical results which are in disagreement with known isotopic concentrations (see paragraph 12).

3.

Chemistry / Radiochemistry Organization and Management Controls The NRC inspectors reviewed the licensee's corporate and WCGS organizations and staffing regarding chemistry / radiochemistry activities to determine adherence to commitments in Chapter 13 of the Final Safety Analysis Report (FSAR) and requirements in Section 6.2 of the Technical Specifications (TS).

The NRC inspectors verified that the organizational structures of the

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j corporate radiological services nuclear chemistry section and the WCGS chemistry / radiochemistry section (C/RS) were as defined in the FSAR and TS l

and unchanged from previous NRC inspections.

The corporate and C/RS staff l

assignments, management controls, and position descriptions were reviewed i

for the assignment of responsibilities for the management and l

implementation of the corporate radiological services nuclear chemistry section and the WCGS chemistry / radiochemistry programs.

It was verified that the administrative control responsibilities specified by the WCGS procedures were being implemented.

l The NRC inspectors reviewed the staffing of the corporate radiological l

services nuclear cher..istry section and the WCGS C/RS and noted that the l

corporate nuclear chemistry section was fully staffed and the two staff members were the same as reported in previous NRC inspection reports.

Since the previous NRC inspection in October 1985, the WCGS C/RS had lost and replaced two chemistry technicians.

The corporate and WCGS C/RS organizational structures and staffing were determined to be in accordance with licensee commitments.

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No violations or deviations were identified.

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-5-4.

Chemistry / Radiochemistry Personnel Qualifications The NRC inspectors reviewed the qualifications of the corporate radiological services nuclear chemistry personnel and WCGS C/RS personnel to determine adherence to commitments in Chapter 13 of the FSAR and requirements in Section 6.3 of the TS.

The NRC inspectors reviewed the education and experience backgrounds of the present corporate nuclear chemistry personnel and verified that they met the required qualifications specified in the FSAR and position descriptions.

Based on the review of the WCGS C/RS staff resumes, It was determined that all the supervisor staff and 9 of 14 chemistry technician positions were filled with personnel who satisfied the ANSI /ANS 3.1-1978 qualifications.

The C/RS has 12 shift qualified technicians and two recently hired technicians who were presently in qualification training.

The NRC inspectors reviewed the six-shift rotation schedule and determined that each shift was composed of at least one ANSI and shift qualified person.

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No violations or deviations were identified.

5.

Chemistry / Radiochemistry Training Program The NRC inspectors reviewed the licensee's chemistry / radiochemistry training program to determine adherence to commitments in Chapter 13.2 of the FSAR and the requirements in Section 6.4 of the TS.

The NRC inspectors discussed the training program for C/RS personnel with the chemistry training program coordinator.

The nuclear training department had recently expanded its staff and added a training instructor in chemistry who had formerly been a technician in the WCGS C/RS.

The NRC inspectors reviewed the training department organization, chemistry training staff qualifications, position assignments, classroom and laboratory facilities, implementing procedures, initial chemistry technician training program outline, and C/RS training schedule.

Lesson plan development was reviewed and it was determined that the identified lesson plans were approximately 85 percent complete overall with 30 percent of the lesson plans finished and available for teaching.

The NRC inspectors also reviewed the development of the on-the-job (0JT)

training / qualification cards and found them based on objectives as determined by tasks analyses and approximately 85 percent complete.

The chemistry training program coordinator indicated that the goal was to complete the identified course lessons plans and 0JT training /

qualification cards by the end of 1986.

The NRC inspectors reviewed selected nuclear training department procedures which had been completed and approved since the previous NRC inspection in October 1985.

The NRC inspectors also reviewed WCGS Procedure ADM-04-004, " Chemistry Group Training Program," Revision 7, September 19, 1986, and found it

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-6-adequate to direct and document the training of the C/RS personnel.

It was noted that the licensee was in the process of preparing a self evaluation report describing the chemistry training program and objectives based on position task analyses to be submitted to the Institute of Nuclear Power Operations (INPO) as part of the INP0 training accreditation program.

The NRC inspectors reviewed the C/RS individual staff training records and 1985 and 1986 requalification cards and found that training was being completed and documented in accordance with procedure.

It was noted that there was still a backlog of training records which need to be transmitted to the nuclear training department to be incorporated into the C/RS individual training records and microfilmed for permanent QA records.

The NRC inspectors discussed this observation with the licensee during the inspection and at the exit briefing.

The licensee agreed to evaluate this observation and transmit the training records as soon as possible.

No violations or deviations were identified.

6.

Chemistry / Radiochemistry Program The NRC inspectors reviewed the licensee's chemistry / radiochemistry program to determine adherence to commitments in Chapters 5, 3, and 11 of the FSAR and in Section 3/4.4.7 of the TS.

The NRC inspectors' review of the chemistry / radiochemistry program found that the licensee had revised and approved administrative procedures, surveillance procedures, chemical control procedures, instrument calibration and quality control procedures, sampling procedures, and analytical procedures.

A review of selected procedures revised and written since the previous NRC inspection in October 1985, daily logs, and analytical data indicated that the C/RS had established sufficient programmatic procedures to meet the requirements of the FSAR and TS.

The NRC inspectors reviewed chemistry and radiochemistry logs and records of completed chemical and radiochemical analyses and completed surveillance test records since the previous NRC inspection in October 1985 and determined that the required analyses were being performed.

The review also included discussions of the recorded trends of the secondary water quality data and reactor coolant chemistry parameters with the C/RS personnel.

The NRC inspectors reviewed the effectiveness of the secondary water chemistry program to measure and prevent the introduction of chemical containments into the secondary water systems and found the licensee's limits were established according to the Electric Power Research Institute owner's group guidelines for pressurized water reactor secondary water chemistry.

Interviews were held with C/RS personnel and it was determined that the staff at all levels understood the importance and need for water chemistry control.

The occupational exposure (person-rem) to plant personnel was reviewed as it relates to water chemistry control and found no evidence of increased occupational exposure as a result of poor water chemistr.

-7-The NRC inspectors verified that the secondary chemistry laboratory instruments and the primary chemistry laboratory instruments had been calibrated in accordance with procedures and an instrument quality control program had been implemented.

The licensee had implemented an inter-laboratory crosscheck program with several other utilities as well as an internal laboratory analytical accuracy crosscheck program to verify performance of C/RS technicians on analytical procedures.

The NRC inspectors reviewed the 1986 results of the two crosscheck programs and found that they demonstrated a high quality analytical capability.

The NRC inspectors reviewed the semiannual chemistry reports for the periods July through December 1985 and January through June 1986 produced by the nuclear chemistry radiological services section.

The reports included analyses trends of important chemical parameters in both the secondary and primary water systems.

The graphs and narrative portions of the reports indicated where specific problem areas may be developing, when out-of-specification conditions existed, and corrective actions which were taken to reestablish normal chemical parameters.

The chemistry reports were complete and helpful in evaluating plant chemistry performance.

The NRC inspectors reviewed several corporate procedures used to describe and implement the radiological services section nuclear chemistry program.

It was noted that not all aspects of technical review of the WCGS chemistry program were being routinely performed and the reviews documented.

These reviews of chemistry specifications, chemistry analytical procedures, chemistry quality control program, chemistry personnel training, and chemistry department activities, if performed, were not readily available for review.

This observation was discussed with the licensee during the inspection and at the exit briefing.

The licensee agreed to evaluate this observation and provide better documentation of chemistry reviews performed by the radiological services section in the future.

No violations or deviations were identified.

7.

Quality Assurance Program The NRC inspectors reviewed the licensee's QA organization and audit / surveillance program regarding chemistry / radiochemistry activities to determine adherence to commitments in Chapter 17 of the FSAR and the requirements in Section 6.5.2.8 of the TS.

The NRC inspectors reviewed the QA department organization, selected QA audit and surveillance procedures, audit schedule for 1986, QA auditor qualifications, and audit and surveillance reports. Audit and surveillance reports generated from QA activities during the period from August 1985 through September 1986 in the areas of chemical / radiochemical control, indoctrination and training, chemistry instrument calibration, chemistry sampling and analyses, and chemistry technical specifications surveillance were reviewed for scope to ensure thoroughness of chemistry / radiochemistry program evaluation and timely follow-up of

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-8-identified deficiencies.

The NRC inspectors determined that the audit plans and checklists generated from a list of essential chemistry / radiochemistry program elements and attributes were comprehensive.

It was verified that the list of essential elements and attributes used by the QA auditors in preparing their audit checklists had not changed since the previous NRC inspection in October 1985.

It was acknowledged 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. The NRC inspectors found that the QA audit / surveillance program appeared to be adequate.

No violations or deviations were identified.

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8.

Facilities and Equipment The NRC inspectors inspected the facilities and equipment used by the C/RS staff.

The following facilities were inspected:

secondary chemistry laboratory and sampling area, primary chemistry laboratory, radiochemistry counting room, shop chemistry laboratory, and radwaste laboratory and sampling area.

The facilities inspected had not been changed since the previous NRC inspection of these areas in October 1985.

It was noted that a new hydrogen analyzer had been purchased and was being used at the primary sampling panel for analysis of dissolved hydrogen in the reactor coolant.

It was also noted that the sodium analyzers and dissolved oxygen analyzers on the secondary chemistry instrument panel were not operational.

The NRC inspectors reviewed the licensee's plant modification requests generated as a result of the licensee's evaluation of the past performance of these instruments.

The licensee was processing and taking action on the plant modification requests at the time of the j

inspection.

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No violations or deviations were identified.

9.

Postaccident Sampling System The NRC inspectors reviewed the licensee's PASS to determine adherence to requirements in Section 6.8.4.d of the TS and of NUREG-0737, Item II.B.3.

The NRC inspectors verified that the PASS equipment and operating procedures met the requirements of NUREG-0737, Item II.B.3, and TS for representative sampling and analysis of reactor coolant, reactor sump, and containment atmosphere following a reactor incident.

The licensee had completed PASS operator training as part of shift qualification training for chemistry technicians and established a requalification training program on PASS which was being conducted every 6 months.

The PASS was being operated daily by rotating shift chemistry technicians to verify sys em operation and maintain technician proficiency on the system.

The licensee had implemented an in-line instrument calibration and preventative maintenance program in compliance with TS requirements.

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-9-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 analyses including gamma isotopic, pH, boron, conductivity, and dissolved oxygen and comparing the results of these analyses with reactor coolant grab sample analysis results.

The results compared were in agreement.

The licensee also collected and analyzed a containment atmosphere sample for gamma isotopic content.

The NRC inspectors noted that the reactor coolant system hydrogen analyzer was giving low comparable results to routine grab sample analysis results and verified that a work request had been submitted to evaluate and correct the problem.

It was determined that the licensee's equipment, procedures, analytical sensitivities, and analytical results of chemistry and radiochemistry parameters were consistent with PASS requirements.

The NRC inspectors verified that the PASS equipment was operational on demand.

No violations or deviations were identified.

10.

Quality Control of Radiological Analytical Measurements The NRC inspectors inspected the radiochemistry counting room and reviewed the licensee's program for calibration and quality control of radiological analytical measurements to determine compliance with the requirements in Section 6.8 of 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 October 1985 through September 1986 were reviewed.

No violations or deviations were identified.

11.

Analytical Measurements a.

Confirmatory Measurements Confirmatory measurements were performed on the following standards and samples in the Region IV mobile laboratory at Wolf Creek during the inspection:

(1) Reactor Coolant Liquid (20 ml Scintillation Vial)

(2) Gas Sample (1 Liter Gas Marinelli)

(3) Particulate Filter Standard (CSN0134)

(4) Charcoal Cartridge Standard (CSN0132)

i (5) Liquid Standard (1 Liter Marinelli CSN0133)

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-10-(6) Tritium Sample The confirmatory measurements tests consisted of comparing measurements made by the licensee and the NRC mobile laboratory.

The NRC's mobile laboratory measurements are referenced to the National Bureau of Standards (NBS) by laboratory intercomparisons.

Confirmatory measurements are made only for those nuclides identified by the NRC as being present in concentrations greater than 10 percent of the respective isotopic values for liquid and gas concentrations as stated in 10 CFR Part 20, Appendi> B, Table II.

Attachment 1 contains the criteria used to compare results, b.

Results At the time of the inspection, the licensee utilized detectors in chemistry and radwaste for comparison with the NRC results.

The licensee performed the tritium analysis on their liquid scintillation I

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 92 percent agreement with the NRC analysis results.

The liceasee's tritium result was in agreement with the NRC analysis result.

Confirmatory measurements were performed by the licensee on a liquid sample prepared by the Radiological Environmental Sciences Laboratory (RESL) in Idaho Falls, Idaho.

The licensee's analytical results were compared to the known sample activities and the results of the comparisons are presented in Attachment 2, sample 7.

No violations or deviations were identified.

12.

Contractor Activities The NRC inspectors determined that the licensee was not using contractor personnel onsite to perform chemical or radiochemical analyses.

However, the licensee was using a contractor to perform the SSFe analysis on radioactive liquid waste effluent required by TS.

The licensee had uerformed a QA audit of the contract laboratory and had placed it on the approved vender list for the site.

The licensee stated that the results of the annual RESL confirmatory measurements sample will be used as a quality control check on the contractor laboratory.

The NRC inspectors discussed the ssFe analysis disagreement with the licensee as shown in Attachment 2, sample 7, and the licensee agreed to investigate the contract laboratory's analysis results in an attempt to resolve the l

disagreement.

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No violations or deviations were identified.

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13.

Exit Briefing

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The NRC inspectors met with the two WCGS NRC resident inspectors and the licensee representatives identified in paragraph 1 of this report at the

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conclusion of the inspection on October 3, 1986.

The lead NRC inspector summarized the scope of the inspection, discussed the inspection findings, and presented the results of the confirmatory measurements.

The licensee

agreed to review the NRC inspecto s' observations listed in paragraph 2.

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ATTACHMENT

Criteria for Comparing Analytical Measurements The following are the criteria used in comparing the results of capability 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 limits vary in relation to the comparison of the resolution.

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Resolution =

NRC UNCERTAINTY LICENSEE VALUE Ratio =

NRC VALUE 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.

RESOLUTION AGREEMENT RATIO

<4 0.4 - 2.5 4-7 0.5 - 2.0 8 - 15 0.6 - 1.66

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16 - 50 0.75 - 1.33

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51 - 200 0.80 - 1.25

>200 0.85 - 1.18 The above criteria are applied to the following ahalyses:

(1) Gamma Spectrometry.

(2) Tritium analyses of liquid samples.

(3) Iodine on adsorbers.

(4) 8SSr and 80Sr determinations.

(5) Gross Beta where samples are counted on the same date using the same reference nuclid __

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ATTACHMENT 2 CONFIRMATORY MEASUREMENTS RESULTS 1.

Reactor Coolant Liquid (20 ml Scintillation Vial)

(Sampled 13:40 CDT, September 30, 1986)

WCGS Results NRC Results WCGS/NRC Comparison Nuclide (uCi/ml)

(uCi/ml)

Ratio Decision 41Ar 1.89710.422 E-3 2.285i0.044 E-3 0.83 Agreement 1.67110.186 E-3 0.73 Disagreement 2.40310.149 E-3 1.05 Agreement m

8s Kr 6.27212.306 E-4 7.951 0.296 E-4 0.79 Agreement 7.182 1.253 E-4 0.90 Agreement 8.77011.463 E-4 1.10 Agreement t

87Kr 1.64810.584 E-3 2.06810.072 E-3 0.80 Agreement 1.69910.337 E-3 0.82 Agreement 1.97810.339 E-3 0.96 Agreement 88Kr 2.45010.395 E-3 2.062 0.109 E-3 1.18 Agreement 1.966 0.216 E-3 0.95 Agreement

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2.03410.257 E-3 0.99 Agreement

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133Xe 3.81410.548 E-3 4.04910.061 E-3 0.94 Agreement 3.69010.274 E-3 0.91 Agreement

4.29610.389 E-3 1.06 Agreement 135"Xe 4.567 0.747 E-3 1.096 0.022 E-2 0.42 Disagreement

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2.41910.181 E-2 2.21 Disagreement l

5.206 0.394 E-3 0.48 Disagreement 13SXe 5.67710.317 E-3 6.98310.045 E-3 0.81 Agreement

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5.97410.181 E-3 0.86 Agreement 7.07810.227 E-3 1.01 Agreement

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F 138Xe 6.79911.223 E-3 1.034 0.075 E-2 0.66 Agreement 8.33212.636 E-3 0.76 Agreement

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9.93611.610 E-3 0.96 Agreement 24Na 2.96810.473 E-3 2.57110.038 E-3 1.15 Agreement 2.49910.135 E-3 0.97 Agreement 2.478 0.132 E-3 0.96 Agreement ssCo

< 3.707 E-4 3.210 0.240 E-4 1.15 Agreement

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2.17710.725 E-4 0.68 Agreement

3.08110.780 E-4 0.96 Agreement l

88Rb 1.02110.393 E-2 1.486 0.118 E-2 0.69 Agreement 1.97510.535 E-2 1.33 Agreement

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8.11111.204 E-3 0.55 Disagreement

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-2-89Rb 8.73411.765 E-3 7.85110.406 E-3 1.11 Agreement 9.15913.136 E-3 1.17 Agreement 6.09010.804 E-3 0.78 Agreement 131I

< 4.25 E-4 4.648 0.387 E-4 0.91 Agreement 5.06611.399 E-4 1.09 Agreement 4.48111.593 E-4 0.96 Agreement 132I 1.14510.040 E-2 1.129 0.008 E-2 1.01 Agreement 1.10810.022 E-2 0.98 Agreement 1.15110.026 E-2 1.02 Agreement 1331 6.04510.240 E-3 6.18310.042 E-3 0.98 Agreement 6.000 0.147 E-3 0.97 Agreement 6.267 0.158 E-3 1.01 Agreement 134I 2.03110.098 E-2 2.14310.017 E-2 0.95 Agreement 1.920 0.064 E-2 0.90 Agreement 2.06710.047 E-2 0.96 Agreement 135I 1.11610.133 E-2 1.197 0.017 E-2 0.96 Agreement 1.16910.067 E-2 0.98 Agreement 1.13910.059 E-2 0.95 Agreement

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tasCs 2.13910.125 E-2 2.20510.021 E-2 0.97 Agreement 2.204i0.082 E-2 1.00 Agreement 1.94310.050 E-2 0.88 Agreement

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1398a 1.662 0.860 E-3 2.34010.153 E-3 0.71 Agreement 2.02710.495 E-3 0.87 Agreement

1.439i0.511 E-3 0.61 Agreement l

2.

Gas Sample (1 Liter Gas Merinelli)

(Standardized 08:00 CDT, October 1, 1986)

WCGS Results NRC Results WCGS/NRC Comparison l

Nuclide (uCi/cc)

(uCi/cc)

Ratio Decision 127Xe 3.39610.022 E-4 3.15010.006 E-4 1.08 Agreement 3.42410.014 E-4 1.09 Agreement i

ssKr 1.65510.032 E-2 1.378 0.006 E-2 1.20 Disagreement 1.63010.017 E-2 1.18 Agreement taaXe 2.15610.032 E-4 2.11210.008 E-4 1.02 Agreement 2.16110.018 E-4 1.02 Agreement i

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Particulate Filter Standard (CSN0134)

(Standardized 08:00 CDT, October 1, 1986)

WCGS Results NRC Results WCGS/NRC Comparison Nuclide (uCi/ sample)

(uCi/ sample)

Ratio Decision 109Cd 4.08610.117 E-1 4.00610.011 E-1 1.02 Agreement 4.10910.076 E-1 1.03 Agreement 57Co 7.80710.311 E-3 7.850 0.034 E-3 0.99 Agreement 7.595 0.231 E-3 0.97 Agreement 139Ce 5.88910.351 E-3 6.021 0.033 E-3 0.98 Agreement 6.007 0.234 E-3 1.00 Agreement 203 Hg 5.30110.434 E-3 5.666 0.042 E-3 0.94 Agreement 4.95210.237 E-3 0.87 Agreement 113Sn 1.024 0.080 E-2 1.13710.007 E-2 0.90 Agreement 1.048 0.047 E-2 0.92 Agreement 137Cs 1.445i0.115 E-2 1.463 0.009 E-2 0.99 Agreement 1.39210.060 E-2 0.95 Agreement soCo 1.331 0.159 E-2 1.184 0.012 E-2 1.12 Agreement 1.17810.065 E-2 0.99 Agreement 88Y 1.44610.185 E-2 1.335 0.014 E-2 1.08 Agreement 1.442 0.041 E-2 1.07 Agreement 4.

Charcoal Cartridge Standard (CSN0132)

(Standardized 08:00 CDT, October 1, 1986)

WCGS Results NRC Results WCGS/NRC Comparison Nuclide (uCi/ sample)

(uCi/ sample)

Ratio Decision 109Cd 6.19510.167 E-1 7.384 0.017 E-1 0.84 Disagreement 6.304 0.116 E-1 0.85 Agreement 57Co 1.178i0.045 E-2 1.419 0.005 E-2 0.83 Disagreement 1.22610.034 E-2 0.86 Agreement 139Ce 9.187 0.486 E-3 1.060 0.005 E-2 0.87 Agreement 9.14010.337 E-3 0.86 Agreement 203Hg 3.671 0.507 E-3 4.387 0.044 E-3 0.84 Agreement 4.02910.280 E-3 0.92 Agreement

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-4-113Sn 1.61210.118 E-2 1.91410.010 E-2 0.84 Agreement 1.67910.066 E-2 0.88 Agreement 137Cs 2.131 0.172 E-2 2.54610.013 E-2 0.84 Agreement

,

2.16710.090 E-2 0.85 Agreement 80Co 2.02810.194 E-2 2.04410.016 E-2 0.99 Agreement 1.759 0.095 E-2 0.86 Agreement i

i 88Y 2.29410.225 E-2 2.322 0.019 E-2 0.99 Agreement 2.09710.112 E-2 0.90 Agreement 5.

Liquid Standard (1 Liter Marinelli CSN0133)

(Standardized 08:00 CDT, October 1, 1986)

WCGS Results NRC Results WCGS/NRC Comparison Nuclide (uCi/ml)

(uCi/ml)

Ratio Decision

'

109Cd 9.80710.316 E-4 1.015i0.006 E-3 0.97 Agreement 9.42910.157 E-4 0.93 Agreement s7Co 1.77710.068 E-5 1.928i0.018 E-5 0.92 Agreement 1.805 0.047 E-5 0.94 Agreement

,

139Ce 1.45310.077 E-5 1.44910.014 E-5 1.00 Agreement 1.36810.044 E-5 0.94 Agreement 203Hg 1.13610.084 E-5 1.20710.015 E-5 0.94 Agreement 1.17010.050 E-5 0.97 Agreement

113Sn 2.41110.146 E-5 2.67610.027 E-5 0.90 Agreement 2.60910.086 E-5 0.97 Agreement

{

137Cs 3.39710.201 E-5 3.54210.033 E-5 0.96 Agreement l

3.36410.104 E-5 0.95 Agreement 80Co 2.923 0.229 E-5 2.908 0.036 E-5 1.01 Agreement 2.737i0.011 E-5 0.94 Agreement

'

,

88Y 3.365 0.260 E-5 3.164i0.042 E-5 1.06 Agreement

3.214i0.129 E-5 1.02 Agreement 6.

Tritium Sample

'

(Sampled October 2, 1986)

WCGS Result NRC Result WCGS/NRC Comparison

,

j Nuclide (uCi/ml)

(uCi/ml)

Ratio Decision 3H 3.0910.008 E-2 3.01 0.03 E-2 1.03 Agreement

.

-,-.

w..-~-

,-,,--,-,c-

- - - - - -, -, - -.,, -

,n.--

- -

.

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

.

-

.

. _

_.. -

..

.

-.

-_

__

. -.

'

..

.

-5-

,

7.

RESL Liquid Sample (Standardized 12:00 MST, January 11, 1986)

WCGS Results NRC Results 1/

Nuclide (uCi/ml)

(uCi/ml) -

WCGS/NRC Comparison Ratio Decision

?

3H 1.03 0.03 E-4 1.11i0.02 E-4 0.93 Agreement 895r 1.74i0.03 E-4 1.4010.04 E-4 1.24 Agreement 90Sr 7.1410.72 E-6 1.3310.05 E-5 0.54 Disagreement i

ssFe

<5 E-9 uCi/ml 8.26 0.17 E-5

-

Disagreement 137Cs 1.7910.02 E-5 1.9110.06 E-5 0.94 Agreement

!

60Co 1.7610.02 E-5 1.70 0.03 E-5 1.04 Agreement 54Mn 1.1410.02 E-5 1.18 0.02 E-5 0.97-Agreement l

r

?

}

!

-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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,

i l

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