IR 05000285/1987011

Insp Rept 50-285/87-11 on 870504-08.No Violations or Deviations Noted.Major Areas Inspected:Radiochemistry & Water Chemistry Control Programs,Including Organization & Mgt Controls,Training & Qualifications & Measurements

ML20215E729
Person / Time
Site:	Fort Calhoun
Issue date:	06/09/1987
From:	Murray B, Nicholas J, Zibulsky H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20215E721	List: IR 05000285/1987011 ML20215E719
References
50-285-87-11, NUDOCS 8706220079
Download: ML20215E729 (10)

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l APPENDIX U.S. NUCLEAR REGULATORY COMMISSION L

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REGION IV

NRC Inspection Report: 50-285/87-11 License: DPR-40 Docket: 50-285 Licensee: Omaha Public Power District (OPPD)

1623 Harney Street Omaha, Nebraska 68102 Facility Name: Fort Calhoun Station (FCS)

Inspection At: FCS Site, Blair, Nebraska .

Inspection Conducted: May 4-8, 1987 Inspectors: [/ /U _f/I'/N/

'J. S. Nicholas, Seniov Radiation Specialist, Date'

pg Facilities Radiological Protection Section

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&nnaar Zibulsky, Chemist, Redion I WWn Dhte'

Approved: [ /2/ J ? , II///U/ [

B~ Murray, Chief, facilitjes Radiological

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Protection Section /

Inspection Summary Inspection Conducted May 4-8, 1987 (Report 50-285/87-11)

Areas Inspected: Routine, unannounced inspection of the licensee's radiochemistry and water chemistry control programs including: organization and management contro1r> training and qualifications, secondary water quality, quality control of analytical measurements, and radiochemistry and water chemistry confirmatory measurement Results: Within the areas inspected, no violations or deviations were I~dentifie PDR ADOCK 05000205 G PDR

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. DETAILS ' Persons Contacted OPPD

• R. L. Andrews, Division Manager, Nuclear Production

• G. Gates, Manager, Fort Calhoun Station l P. Brenberger, Chemistry Technician T. Dukarski, Senior Chemistry Technician T. R. Gares, Chemistry Technician J. M. Glantz, Senior Chemistry Technician S. Hall, Chemistry Technician

• R. L. Jaworski, Section Manager, Technical Services L. T. Kusek, Supervisor, Operations R. Meng, Chemistry Technician

• D. J. Munderloh, Senior Engineer, Nuclear Regulatory and Industry Affairs

• A. W. Richards, Manager, Quality Assurance

• G. L. Roach, Supervisor, Chemical and Radiation Protection

• B. A. Schmidt, Chemist

• F. K. Smith, Plant Chemist

• D. Spires, Chemist, Technical Services

• R. K. Stultz, Supervisor, Radiological and Environmental Monitoring Services Other

• P. H. Harrell, NRC Senior Resident Inspector The NRC inspectors also interviewed other licensee personne * Denotes those present at the exit interview on May 8, 198 . Inspector Observations The following are observations the NRC inspectors discussed with the licensee during the exit interview on May 8, 1987. These observations are not violations, deviations, unresolved items, or open items. These observations were identified for licensee consideration for pragram improvement, but the observations have no specific regulatory requirements. The licensee stated that the observations would be reviewe Calibration Standards Verification - The licensee was not using two independent standard solutions for calibration and measurement quality contro The licensee was unable to verify the integrity of the standard solutions. The licensee had not initiated a two standards program which includes one standard stock solution L

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dedicated for instrument calibration and another independent standard stock solution dedicated for quality: control, Quality Control Charts - The licensee was not'using quality control charts to trend and evaluate biases experienced in daily or periodic quality control analyses. The licensee had not initiated the use of quality control charts so as to recognize biases in calibration standard data and changes and trends in instrument performanc . Program Areas Inspected l The following program areas were inspected. Unless otherwise noted, the inspection;was completed and revealed no violations, deviations, unresolved ittms, or open items. Notations after a specific. inspection item are_used to identify the following: I = item not inspected or only partially inspected; V = violation, D = deviation; U = unresolved item; and 0 = open ite Procedur Inspection Requirements 83722 Organization and Management Controls (Water Chemistry / Radiochemistry)

02.01 Organization-02.02 Staffing 02.03 Radiation Protection Manager 02.04 ' Identification and Correction of Program Weaknesses 02.05 Audits and Appraisal 83522 Organization and Management' Controls (Water Chemistry / Radiochemistry)

C2.01 Organization, Responsibilities, and Authorities 02.02 -Staffing 02.03 Identification and Correction of Weaknesses 02.04~ Audits and Appraisals 02 05 Communication to Employees 02.06 Documentation and Implementation 83723 Training and Qualifications (Water Chemistry /

Radiochemistry)

02.01 Adequacy of Training 02.02 Employee Knowledge 02.03 Transportation /Radwaste Training 02.04 Qualification Requirements 02.05 New Employees l- 02.06 INP0 Accreditation

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-5-02.07 Audits and Appraisals 02.08 Training not Covered by INPO 83523 Training and Qualifications (Water Chemistry /

Radiochemistry) ,

02.01 Training and Qualification Program 02.02 Education and Experience 02.03 -Adequacy and Quality of Training ,

79701 LWR Water Chemistry Control and Chemical Analysis 02.01 Audits and Appraisals - I i

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02.02 Changes 02.03 Implementation of a Water Chemistry Control Program 02.04 Implementation of a QA Program 79501 LWR Water Chemistry Control and Chemical Analysis 02.01 Establishment of a Water Chemistry Control Program 02.02 Implementation of a Water Chemistry Control Program 02.03 Water Sampling 02.04 Facilities and Equipment 02.05 Establishment of a QA Program 02.06 Implementation of a QA Program 02.07 Laboratory Safety 79502 Plant Systems Affecting Plant Water Chemistry i

02.01 Audits and Appraisals - I

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02.02 Primary and Secondary Water Systems - I 02.03 Auxiliary Water Systems - I 02.04 Demineralizers - I i 4. Attachments The licensee's confirmatory measurement results concerning radiochemistry and water chemistry samples are documented in Attachments 1, 2, 3, 4, and . Exit Interview The NRC inspectors met with the NRC senior resident inspector and the licensee representatives denoted in paragraoh 1 at the conclusion of the inspection on May 8, 1987. The lead NRC inspector summarized the scope of the inspection and discussed the inspection findings and the results of

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the confirmatory measurements.

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t ATTACHMENT 1

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l Analytical Measurements

' Nonradiological Water Chemistry Confirmatory Measurements

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During the inspection, standard chemical solutions were provided to the !

licensee for. analysis. - The standard solutions were prepared by the l c Brookhaven National Laboratory (BNL), Safety and Environmental Protection l Division, for the NRC. The standards were analyzed by the licensee using

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routine methods and equipment. The analysis of chemical standards is used 3 to verify the licensee s capability to monitor chemical parameters in i various ~ plant systems with respect to Technical Specification requirements ,

and' other industry standards. In addition, the analysis of standards is

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i used to evaluate the licensee's analytical ;nredures with respect to j accuracy and precisio j The results of the measurements comparison are listed in. Attachment Attachment 3 contains the criteria used to compare results. All standards were' analyzed in-triplicate. The licensee's original analytical results indicated that 26 of,the 29 results were in agreement. Those analytical l results which were found in disagreement after the first ion chromatograph ,

analysis were rerun by the licensee in an attempt to resolve any problems !

associated with-sample preparation or analysis. .The licensee was able to j resolve the analytical problems associated with the_ ion chromatograph and l the rerun analysis results were all in agreemen !

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As part of the inspection, actual inplant water samples were split between !

-the licensee and the NRC in order to verify the licensee's measurement I capabilities on actual plant water samples. The analyses will be performed by licensee using their. normal methods and instrumentation and by BNL for the NRC Region IV. -The analyses to be performed are baron, fluoride, and chloride on a reactor. coolant sample; and iron, copper',

nickel, chromium, fluoride, chloride, and sulfate on a condensate water

' sample. On completion of the analyses by both laboratories, the results j will be compared by the NRC Region IV office and the intercomparison results will be documented in a subsequent NRC inspection repor . Radiological Confirmatory Measurements Confirmatory measurements were performed by the licensee on liquid ;

radiochemistry samples prepared by the Radiological Environmental Sciences i Laboratory (RESL) in Idaho Falls, Idaho. The samples were provided to the licensee for analysis in April 1986. The licensee's analytical results j were compared to the known sample activities and the results of the l'

comparisons are presented in Attachment 4 for official documentatio Attachment 5 contains the criteria used to compare results. The  ;

licensee's results for the 1986 RESL sample were in 71 percent agreement.

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ATTACHMENT 2 j

Nonradiological Water Chemistry Confirmatory Measurements Results ]

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= Fort Calhoun Nuclear Station  ;

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Chemical' Analytical- FCS NRC- FCS/NRC . Comparison Parameter Procedure Results Results- Ratio Decision '4 Results in parts per billion (ppb).

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Sodium Atomic Absorption- 4.3310.04 4.5810.50 0.9510.14 Agreement Flame Emission 10.6710.06 9.23 0.80 1.1610.'10 Agreement- i

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13.4010.60 14.4010.80 0.93 0.07 Agreement Fluoride Ion .

19.41 .11.61 .67 0.07 Disagreement Chromatogra .21 .81 .9710.08' Agreement 44.81 .81 .0710.09 Agreement Rerun 11.81 .61 .0210.07' Agreement 20.3 .81 .9310.07 ' Agreement

.40.71 .8i .9710.04 Agreement j Chloride ~ Ion 20.91 .11 .7310.54 Agreement Chromat'ograph 28.91 .71 .5510.17 Disagreement

'45.311 .31 .1210.29 Agreement Rerun' 10.01 .111~.6 0.8310.14: ' Agreement-19.91 .7 .0610.06 . Agreement 42.11 .3 .0410.04- Agreement'

Sulfate' Ion 13.71 .01 .3710.30 Agreement Chromatograph 23.21 .51 .1310.17 Agreement 45.2 6'.2 40.41 .1210.16 Agreement Rerun 10.51 .01 .0510.07 Agreement 18.91 .51 .9210.05 Agreement 37.71 .41 .9310.05 Agreement

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Chloride Specific Ion 16.01 .11 .3210.22 Agreement l Electrode 27.01 .71 .4410.12 Disagreement Silica Spectro- 30.01 .21 .1010.12 Agreement i photometry 53.71 .51 .9910.07 Agreement 80.31 .01 .0010.01 Agreement Results in parts per million (ppm)

Hydrazine Spectro- 0.10010.01 0.112 0.01 0.8910.08 Agreement photometry 0.102 0.01 0.11410.01 0.89 0.09 Agreement 0.19110.01 0.20810.01 0.9210.05 Agreement

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-2-Ammonia Spectro- 0.08110.01 0.08810.01 0.9210.15 Agreement photometry 0.28010.02 0.31410.03 0.8910.11 Agreement 0.95310.01 0.938i0.09 1.0210.10 ' Agreement Boron Mannitol 1008113 985110 1.0210.02 Agreement :

Titration 2995113 2980:50 1.0110.02 Agreement !

5025113 4870160 1.0310.01 Agreement Boron PASS 3080 2980150 1.03 Agreement Ion 5280 4870160 1.08 Agreement Chromatograph l Chromium Atomic Absorption 0.144 0.14310.008 1.00 Agreement Flame ,

Note: Licensee analyses were run in triplicate and were separato analyses and/or dilutions. The uncertainty associated with these anelyses is an estimate of the total uncertainty of the measurement protes!..

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ATTACHMENT 3 Criteria For Comparing Analytical Measurements This attachment provides criteria for comparing results of capability test In these criteria the judgement limits are based on the uncertainty of the ratio of the licensee's value to the NRC value. The following steps are performed:

(1) the ratio of the licensee's value to the NRC value is computed Licensee Value (ratio = NRC Value );

(2) the uncertainty of the ratio is propagate If the absolute value of one minus the ratio is less than or equal to twice the ratio uncertainty, the results are in agreement. (ll-ratiol 5 2 uncertainty)

Z= X, then Sz2 = Sx2 + ys 2 V F F- Y2 (From: Bevington, P.R., Data Reduction and Error Analysis for the Physical Sciences, McGraw-Hill, New York, 1969)

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ATTACHMENT 4 RADIOLOGICAL CONFIRMATORY MEASUREMENTS RESULTS Fort Calhoun Nuclear Station-RESL Liquid Sample (Standardized 12:00, MSTi. January 11,1986)

FCS Results- NRC Results1!' FCS/NRC Comparison

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Nuclide (pCi/ml) (pCi/ml) Ratio Decision 3H- 9.6511.41 E-05 9.3810.19 E-05 1.0 Agreement 89Sr 2.8111.22 E-04 1.1810.04 E-04 2.38 Disagreement.-

90S .0211.34 E-06 1.1210.04 E-05 0.81 Agreement

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55Fe 4.7210.86 E-05 6.9610.14 E-05 0.68 Disagreement 54Mn- 1.0510.04 E-05 1.0710.02 E-05 0.98 Agreement 60Co- 1.5810.04 E-05 1.5510.03 E-05- 1.02- Agreement-137Cs 1.9710.04 E-05 '1.7410.05 E-05 1.13 Agreement

134Cs 1.3110.18 E-06 Not Present  !

SI NRC results were'taken from the standard certification supplied to the NRC Region IV office.as prepared by RESL and traceable to the National Burea 'of Standard i

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Criteria for Comparina 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

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relationship established through prior experience and this program's analytical ,

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requirement In these criteria, the judgement' limits vary in relation to the comparison of the resolutio A E Resolution = j NRC UNCERTAINTY Ratio =

LICENSEE VALUE ]

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NRC VALUE l, k

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 value f

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l RESOLUTION AGREEMENT RATIO

<4 0.4 - ,

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4-7 0.5 - .6 - 1.66 .

16 - 50 0.75 - 1.33 51 - 200 0.80 - 1.25 j

>200 0.85 - 1.18 i l

The above criteria are applied to the following ahalyses:

(1) Gamma Spectrometry.

g (2) Tritium analyses of liquid sample ,

(3) Iodine on adsorber (4) s95r and 80Sr determination (5) Gross Beta where samples are counted on the same date using the same reference nuclide.

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