IR 05000285/1987018

Insp Rept 50-285/87-18 on 870723-24.No Violations or Deviations Noted.Major Areas Inspected:Licensee Radiochemistry Program Including Review of Organization & Mgt Control,Training & Qualifications & QA

ML20237K006
Person / Time
Site:	Fort Calhoun
Issue date:	08/17/1987
From:	Murray B, Nicholas B, Wise R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20237K005	List: IR 05000285/1987018 ML20237K003
References
50-285-87-18, NUDOCS 8708270005
Download: ML20237K006 (8)

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APPENDIX U.S. NUCLEAR REGULATORY COMMISSION

REGION IV

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NRC Inspection.' Report: 50-285/87-18 License: DPR-40 I Docket: 50-285 i

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 ' Licensee: Omaha Public Power District (0 PPD)

1623 Harney Street Omaha, Nebraska 68102 a Facility'Name: Fort Calhoun (FCS) 1

,  Inspection At: FCS Site, Blair, Nebraska   <

Inspection Conducted: July 23-24,1987 i-Inspectors: ., __ F/n/P7 '

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   .J//- B. Nicholas, Senior Radiation Specialist Date !
   ' Mcilities Radiological Protecti'on Section   '
   ) du 2??k?w R. Wise, Radiation Specialist, Facilities
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       '8//7/97 Odte . ' l 8 . Radiological Protection Section
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Approved: b M8jfL4ky1 M/[[ B' Murray, Chie", Facil' .es Radiological D&te / Protection Section Inspection Summary Inspection Conducted July 23-24, 1987 (Report 50-285/87-18) Areas Inspect'ed: Routine, unannounced inspection of the licensee's radiochemistry program including a review of organization and management control, training and qualifications, and quality assurance and radiochemistry confirmatory measurement Results: Within the areas inspected, no violations or deviations were identifie PDR ADOCK 05000285 0 PDR _ _ _ - _ _ _ _ _ _ _

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DETAILS

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        -l . Persons' Contacted'
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M OPPD-

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  * G. Gates, Manager,' Fort Calhoun Statio !
  *J. M.' Glantz, Senior Chemistry Technician-  . ,.  .
  *M. A. Klanderud, Engineer, Nuclear Regulatory and. Industry Affairs  '

  *A.-W. Richards, Manager,l Quality Assurance    .l
  *G. L. Roach, Supervisor, Chemical and Radiation Protection-   i
  *B. A.'Schmidt, Chemist      i
  *F. K. Smith, Plant Chemist     'l q
  .' Others .
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j i*P. H.~Harrell, NRC Senior Resident Inspector, Fort Calhoun Station

  * Denotes those present at'the exit interview on July 24, 198 '
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_j Program Areas Inspected

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The following program areas-were inspected. Unless otherwise noted,-the

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  -inspection was completed and revealed no violations, deviations, unresolved ..

items,;or'openLitems. Notations after a specific inspection item are used-

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to identify the following: . I = iteminot inspected or only partially .

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  ' inspected; V = violation; D = deviation; V = unresolved' item; and 0 = open  1
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u .. . I Procedure- Inspection Requirements 83722' Organization and Management Controls (Water , Chemistry / Radiochemistry ( 02.'01 Organization 02.02 Staffing i 02.04 Identification and Correction of Program Weaknesses { 02.05 Audits and' Appraisal' '

  '83522 Organization and Management Controls (Water  !

Chemistry / Radiochemistry ,

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02.01 Organization, Responsibilities, and Authorities 1 02.02 Staffin j 02.03 Identification and Correction of Weaknesses 02.04 Audits and Appraisals

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02.05 Communication to Employees ) 02.06 Documentation and Implementation

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83723 Training and Qualifications (Water Ch'emistry/ Radiochemistry) 1 02.01 Adequacy of Training - I 02.02 Employee Knowledge 02.04 Qualification Requirements 02.05 New Employees 02.06 INP0 Accreditation - I 02.07 Audits and Appraisals - I 02.08 Training not Covered by INP0 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 - I 84725 Quality Assurance and Confirmatory Measurements For In-Plant Radiochemical Analysis' 02.01 Audits and Appraisals 02.02 Changes 3 02.03 Confirmatory Measurements j 02.04 Postaccident Sample Analysis - 'I l 02.05 Implementation of the Quality Assurance Program 02.06 Contractor Activities 84525 Quality Assurance and Confirmatory Measurements For In-Plant Radiochemical Analysis 02.01 Facilities, Equipe nt, and Supplies 02.02 Procedures 02.03 Confirmatory Measurements  ! 02.04 Postaccident Sample Analysis - I 02.05 Quality Assurance Program 02.06 Contractor Activities 3. Attachments - The licensee's radiochemistry confirmatory measurements results are documented in Attachments 1, 2, and . Exit Interview The NRC inspectors met with the NRC senior resident inspector and the licensee representatives denoted in paragraph 1 at the conclusion of the inspection on July 24, 1987. The NRC inspectors summarized the scope of the inspection and discussed the inspection findings and the results of l' the confirmatory measurement .- -- .__ _ _ - _ _ - _ _ _ _ _ _ _ - _ _ - _ - _ _ - _ _ _ -_-_

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r, u ATTACHMENT 1 x , Analytical Measurements

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Radiological Confirmatory Measurements-

Confirmatory measurements were performed on the following samples and standards in the NRC Region IV mobile laboratory at FCS during the inspection: Air Particulate Filter Standard (21478-109) Stack Charcoal Cartridge (RM-060)

, c; Waste Liquid Monitor Tank "B" (4 liter Marinelli beaker) Waste Gas Sample (1 liter Marinelli beaker) ! Reactor Coolant Ga Reactor Coolant Degassed Liquid Reactor Coolant. 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 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, Appendix Table II. ' Attachment 2 contains the criteria used to compare result The licensee maintains two germanium-lithium (GeLi) detector' systems in the radiochemistry counting room. . At the time:of the inspection, the Canberra Series 90 detector system was out of-service. Both gamma spectrometer systems are used.for routine isotopic analysis of radioactive samples to demonstrate compliance with Technical Specifications and
 ' regulatory requirements. The analytical results from the Canberra Series 80 detector cystem were compared with the NRC results. The licensee performed the tritium analysis on their Beckman liquid scintillation counting system. The individual sample analyses and comparison of analytical results of the confirmatory measurements are tabulated in Attachment The licensee's gamma isotopic results from the listed samples in Attachment 3 showed 97 percent agreement with the NRC analyses based on 30 agreement results out of 31 total results compare The licensee's tritium result on the reactor coolant sample was in agreement with the NRC analysis result.

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I i ATTACHMENT 2 i

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Criteria for Comparing Analytical Measurements q 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 requirement In these criteria, the judgement limits vary in relation to the comparison of the resolutio NR A UE Resolution = NRC UNCERTAINTY g,gg, , LICENSEE VALUE 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 value RESOLUTION AGREEMENT RATIO

  <4  0.4 - .5 - .6 - 1.66        .

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

  >200  0.85 - 1.18         !

i l The above criteria are applied to the following ahalyses:

(1) Gamna Spectrometr (2) Tritium analyses of liquid sample ,
(3) Iodine on adsorber (4) 895r and 80Sr determination (5) Gross Beta where samples are counted on the same date using the same reference nuclide, i

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   ' ATTACHMENT 3
- ' Radiological Confirmatory Measurements Results Fort Calhoun Station Air' Particulate Filter' Standard (21478-109)'
 (Standardized 12:00 p.m. CDT, July 23,1987).

. OPPD Results NRC Results CPPD/NRC Comparison Nuclide (uCi/ Sample) (uCi/ Sample) Ratio Decision'. s7Co l'.7410.12E-02 1.7010.01E-02 1.02- Agreement: 60Co 2.8710.20E-02 2.7610.04E-02 1.04 Agreement 88Y 1.3010.09E-02 1.2810.03E-02 1.01 Agreement 209Cd 8.7710.91E-01 8.6610.04E-01 1.01- Agreement 128Sn 1.0410.09E-02 1.1110.02E-02 0.94 Agreement 137Cs 4.6210.33E-02 4.6810.04E-02 0.99 Agreemcnt 139Ce 7.3310.61E-03 7.6010.09E-03 0.96 Agreement' 203Hg 1.1710.14E-03 1.2410.08E-03 0.94 Agreement Stack Charcoal Cartridge (RM-060)

 (Sampled 12:00 p.m. CDT, July 23, 1987)

OPPD Results NRC Results OPPD/NRC Comparison Nuclide (uCi/ Sample) (uCi/ Sample) Ratio Decision 232I 2.2010.21E-04 2.4010.10E-04- 0.92 Agreement Waste Liquid Monitor Tank "B" (4 liter Marinelli Beaker)

 (Sampled 3:03 p.m. CDT, July. 23, 1987)

OPPD Results NRC Results~ OPPD/NRC Comparison Nuclide (uCi/ml) (uCi/ml) Ratio Decision 5800 2.5510.17E-06- 3.3110.07E-06 0.77- Agreement 234Cs 3.6910.24E-06 4.4810.09E-06 0.82 Agreement j l f 137Cs~ 6.5910.49E-06 8.2510.12E-06 0.80 Agreement i

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2 Waste Gas Sample (1 liter Marinelli Beaker)

  -(Sampled 10:50 a.m. CDT, July 24, 1987)

OPPD Results NRC Results OPPD/NRC Comparison Nuclide (uCi/cc) (uCi/cc) Ratio Decision 85*Kr 7,9010.77E-05 '7.7010.03E-05 ~ 1.03 Agreement 87Kr 1.5610.13E-04 1.5410.01E-04 1.02 Agreement 88Kr 1.89 0.10E-04 1.9210.01E-04 0.98 Agreement laaXe 5.2610.56E.04 4.7310.02E-04 1.11 Agreement

  '235Xe 5.1810.59E-04 5.5810.01E-04 0.93 Agreement 138Xe 6.3310.45E-04 5.6010.07E-04 1.13 Agreement Reactor Coolant Gas (5 cc gas vial)
   (Sampled 12:00 p.m. CDT, July 24,1987)

OPPD Results NRC Results OPPD/NRC Comparison Nuclide (uCi/cc) (uCi/cc) Ratio Decision 85"Kr 2.4010.19E-02 2.1910.01E-02 1.10 Agreement 87Kr 3.1910.29E-02 2.5210.04E-02 1.27 Disagreement 88Kr 5.0610.41E-02 4.6810.04E-02 1.08 Agreement 133Xe 1.7610.24E-01 1.5910.01E-01 1.10 Agreement 185Xe 1.8210.15E-01 1.6910.01E-01 1.08 Agreement Reactor Coolant Degassed Liquid (8 ml vial)

   (Sampled 12:00 p.m. CDT, July 24, 1987)

OPPD Results NRC Results OPPD/NRC Comparison Nuclide (uCi/ml) (uCi/ml) Ratio Decision 24Na 5.88 0.63E-03 6.7210.18E-03 0.88 Agreement 88Rb 5.6110.77E-01 8.37 1.28E-01 0.67 Agreement 138Cs 9.2310.73E-02 5.6612.42E-02 1.63 Agreement 1811 1.3510.12E-02 1.3010.02E-02 1.04 Agreement 132I 1.3710.10E-01 1.4110.01E-01 0.97 Agreement 133I 1.4010.12E-01 1.2910.01E-01 1.08 Agreement l

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134I 1.4510.09E-01 1.3810.02E-01 1.05 Agreement

1851 2.1610.15E-01' 2.0810.02E-01 1.04 Agreement j i 7. Reactor Coolant Tritium Sample (Sampled 12:00 p.m. CDT, July 24, 1987) J OPPD Result NRC Result OPPD/NRC Comparison ., Nuclide (uCi/ml) (uCi/ml) Ratio Decision -]

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3H 1.6310.05E-01 1.6910.06E-01 0.96 Agreement

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