IR 05000298/1986009

Insp Rept 50-298/86-09 on 860303-07.No Violation or Deviation Noted.Major Areas Inspected:Chemistry/ Radiochemistry Program,Including Organization & Mgt Control, Staffing & Staff Qualifications & Training Program

ML20202F031
Person / Time
Site:	Cooper
Issue date:	03/28/1986
From:	Murray B, Nicholas J, Wise R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20202E993	List: IR 05000298/1986009 ML20202E987
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-TM 50-298-86-09, 50-298-86-9, NUDOCS 8604140091
Download: ML20202F031 (19)

Text

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APPENDIX

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U.S. NUCLEAR REGULATORY COMMISSION

REGION IV

NRC Inspection Report: 50-298/86-09 License: OPR-46 Docket: 50-298 Licensee: Nebraska Public Power District (NPPD)

P. O. Box 499 Columbus, Nebraska 68601 Facility Name: Cooper Nuclear Station (CNS)

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Inspection At: CNS Site, Brownville, Nebraska

Inspection Conducted: March 3-7, 1986 l

Inspectors: . J/tr[rg, JfBlairNicholas,lSeniorRadiationSpecialist Date Mcilities Radiation Protection Section  !

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yftlfG Russell Wise, Radiation Specialist, Facilities Date Radiological Protection Section Approved: /J b M // Jf M l/ 7/2k86 Blaine Murray', Chieff Facilities Radiological Eate /

Protection Sectiofi Inspection Summary Inspection Conducted March 3-7, 1986 (Report 50-298/86-09)

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

radiochemistry program including review of organization and management control,

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staffing and staff qualifications, training program, chemistry / radiochemistry program, facilities and equipment, postaccident sampling system (PASS),. quality assurance (QA) program of chemistry / radiochemistry activities, quality centrol

, of analyt.ical measurements, radiochemistry confirmatory measurements, and a whole body counting system confirmatory measurements. The inspection involved 78 inspector-hours onsite by two NRC inspector Results: Within '.he areas inspected, no violations or deviations were identifie Two previously identified open items were close weoelecovl 86r409

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PDR ADOCK 05000298-G PDR

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DETAILS Persons Contacted NPPD

• R. Horn, Division Manager, Nuclear Operations

• Beilke, Chemistry and Health Physics Supervisor T. J. Chard, Acting Health Physicist

• K. Fike, Chemist

• R. Goings, Regulatory Compliance Specialist D. Green, Chemistry Technician G. W. Ketner, Lead Chemistry Technician T. E. Lancelot, Health Physics Technician

• E. M. Mace, Acting Technical Manager J. M. heacham, Technical Manager D. L. Reeves, Training Manager D. Robinson, QA Specialist

• J. V. Sayer, Acting Technical Staff Manager D. L. Snyder, Chemistry Training Instructor

• V. L. Wolstenholm, QA Manager M. C. Wright, Chemistry Technician Others

• E. A. Plettner, NRC Resident Inspector

• Denotes those present during the exit briefing on March 7, 198 The NRC inspectors also interviewed other CNS personnel during the I inspectio . Licensee Action on Previous Inspection Findings (Closed) Open Item (298/8419-01): Canberra Gamma Spectrometer System Calibration - This item involved the calibration of the Canberra ganna spectrometer system without the use of an approved plant procedure for calibration and operation of the Canberra system. The NRC inspectors reviewed the Chemistry Procedure (CP) - 8.5.2.1, " Canberra System Operation," Revision 0, May 2, 1985, and results of the gamma spectrometer system calibration performed during May and June 1985 using the new plant approved procedure. This item is considered close (Closed) Open Item (298/8419-02): Tennelec Alpha / Beta Counting System Calibration - This item involved the lack of an annual voltage plateau and operating high voltage determination since initial installation of the alpha / beta counter in February 1983 and the lack of documentation showing semiannual alpha and beta efficiency determinations as described in

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CP-8.5.2.2, " Alpha / Beta Counter," Revision 0, June 22,198 The NRC inspectors reviewed the licensee's corrective action and curreit revision to CP-8.5.2.2, " Alpha / Beta Counter," Revision 2, April 19, 1985. The procedure has been revised so as not to require an annual voltage plateau determination and the semiannual alpha and beta efficiency determinations have been revised to an annual frequency. The NRC inspectors reviewed the licensee's calibrction data for the Tennelec Alpha / Beta Counting System for the period 1983 through 1986 and found it in compliance with the requirements of the current procedure. This item is considered close . Inspector Observations The following are observations the NRC inspectors discussed with the licensee during the exit briefing on March 7, 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 inoicated these items would be reviewe Chemistry / Radiochemistry Personnel Training - The licensee has not completed the desina rid implementation of a formal training and requalification pr .m for chemistry personnel (see paragraph 6). Chemistry / Radiochemistry Program - The licensee has not written or implemented a program for inventory and control of laboratory chemicals and reagents and for trending of all chemical and radiochemical water chemistry parameters (see paragraph 7). Postaccident Sampling System - The licensee has not incorporated into their semiannual surveillance of the PASS any operability testing of valves or sample collection devices associated with the sampling of containment atmosphere (see paragraph 9). Confirmatory Measurements - The percent agreement between the licensee and NRC analysis results was below the expected value for these kinds of measurements (see paragraph 12.b).

4. Chemistry / Radiochemistry Organization and Management Controls The NRC inspectors reviewed the licensee's organization and staffing of the chemistry /radiochemisty section (C/RS) to determine compliance with Chapter 13 of the Updated Safety Analysis Report (USAR), Section 6.1 of the Technical Specifications (TS), and in CNS procedure The NRC inspectors verified that the organizational structure of the C/RS was as defined in the USAR, TS, and CNS procedures. The NRC inspectors reviewed the CNS staff assignments, management controls, and position descriptions for the assignment of responsibilities for the management and implementation of the CNS chemistry / radiochemistry progra The NRC inspectors found that the administrative control responsibilities specified by the CNS procedures were being implemente . .

The NRC inspectors reviewed the staffing of the C/RS and noted that since the previous NRC chemistry / radiochemistry inspection in September 1984, the C/RS had lost a technician to the training department as an instructor and had developed a position of senior chemistry / health physics specialis The new senior chemistry / health physics specialist position had been filled by the plant chemist and the plant chemist position had been filled by one of the chemistry technicians leaving two chemistry technician positions vacant. At the time of the inspection, one chemistry technician position had been filled and the chemistry and health physics supervisor was recruiting to fill the remaining staff vacanc The CNS C/RS organizational structure and staffing were determined to be in accordance with licensee commitment No violations or deviations were identifie . Chemistry / Radiochemistry Personnel Qualifications The NRC inspectors reviewed the qualifications of the C/RS personnel to determine compliance with commitments in Chapter 13 of the USAR and the requirements in Section 6.1.4 of the T The NRC inspettors reviewed the resumes of each of the C/RS personnel and verified that the present C/RS staff, except for the recently hired technician, met the educational and experience qualification requirements committed to in the USAR and TS and recommended in ANSI N18.1-197 The new chemistry technician was transferred into the C/RS from the CNS health physics section where he had been qualified in health physics in accordance with ANSI N18.1-1971 recommendations. The new technician has been trained and qualified to work back-shift and perform required duties in health physics and chemistry specified by CNS procedures and has received all General Electric chemistry / health physics technician training presented at CN The new technician is presently undergoing chemistry / radiochemistry on-the-job training to complete his chemistry qualification No violations or deviations were identifie . Chemistry / Radiochemistry Personnel Training Program The NRC inspectors reviewed the licensee's chemistry / radiochemistry training program to determine compliance with commitments in Chapter 13.3 of the USAR, the requirements of Section 6.1.4 of the TS, 10 CFR Part 19.12, and CNS procedure The NRC inspectors reviewed the C/RS staff individual training records and made the following observations: All staff except for the newly hired technician had completed the chemistry qualification outlin The chemistry qualification outline is not part of an approved procedure; therefore, it may not be considered an official training recor i

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5 Training records in the staff's individual training files did not ;

indicate the subject matter covered in PASS training and training on mitigating core damage. No formal course outline or testing has been develope Training records for the C/RS staf f were found not in much better order than during previous inspections and were not being maintained by the training departmen The NRC inspectors reviewed the licensee's actions to Open Item 298/8227-03

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which involved the lack of a formal training and requalification program ]

l for chemistry / radiochemistry personnel. The licensee had contracted with ,

General Electric to develop and implement a training program for the C/R >

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The NRC inspectors verified that the course had been developed and taught !

to all the C/RS staff. The NRC inspectors noted that the CNS training department had added to its staff an instructor with experience in BWR ,

l nuclear power plant chemistry / radiochemistry at the termination of the 1 l General Electric contrac )

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The NRC inspectors reviewed selected CNS training department procedure The licensee's program for qualification and training of CNS C/RS staff 1s i described in a draft procedure Training Program Description (TPD)-511, ;

" Chemistry Technician ~fraining Program," which was developed using the results of a recently completed chemistry task analysis-to reflect chemistry program requirements to meet Inscitute of Nuclear Power Operations (INP0)

accreditation criteri It was noted that the procedure-did not outline a chemistry / radiochemistry requalification progra The chemistry /radiochem-istry training instructor was developing course objectives and lesson plans for teaching the che.istry technician job tasks outlined in the chemistry technician training procedure. A review of the chemistry training lesson plans indicated only one had been drafted in the official format at the time of the inspectio The licensee was in the process of applying to INP0 for accreditation in the chemistry / radiochemistry training are ,

l Since a written, approved training and requalification program had not yet l been completed, Open Item 298/8227-03 will remain open pending the licensee's j completion and implementation of an approved program and a review by the i NRC during a future inspectio ;

No violations or deviations were identifie j i

7. Chemistry / Radiochemistry Program l

The NRC inspectors reviewed the licensee's chemistry / radiochemistry program to determine compliance with the commitments in Chapters IV and X of the ;

USAR, the requirements in Section 3/4.6 of the TS, and C/RS procedure '

The NRC inspector's review of the chemistry / radiochemistry program found I that the licensee had approved administrative procedures, surveillance i

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procedures, chemical control procedures, sampling procedures, instrument calibration and performance check procedures, and analytical procedures. A review of selected procedures revised since the previous NRC inspection in September 1984, chemistry logs, and analytical data indicated that the C/RS had established a chemistry / radiochemistry program to meet the requirements of the USAR and TS and provide chemistry control of plant systems during-all phases of plant operatio During the review, the NRC inspectors made the following observations: The licensee had-not developed a procedure for inventory and control of laboratory chemicals and reagents, The licensee had not written a procedure for trending chemical and radiochemical data and water chemistry parameters are not being plotted and trende The NRC inspectors verified that the chemistry / radiochemistry laboratory instruments and chemistry process instrumentation had been calibrated according to procedures and a quality control program was being implemente CNS participates in the U.S. Environmental Protection Agency (EPA)

crosscheck program and has implemented an internal laboratory analytical accuracy assessment program using spiked samples of both non-radiological and radiological chemical components to verify performance of chemistry technicians on analytical procedures. The NRC inspectors reviewed the EPA crosscheck results and the results of the internal laboratory assessment program for 1984 and 198 No violations or deviations were identifie . Facilities and Equipment The NRC inspectors inspected the facilities and equipment / supplies used by the C/RS staff. The following facilities were inspected: chemistry / radio-chemistry laboratory, radiochemistry counting room, various chemistry sampling panels, and PASS operating panel. The laboratory was equipped with the necessary chemicals, reagents, standards, labware, and analytical instrumentation to perform the required analytical procedures. The NRC inspectors noted that a new Dionex ion chromatograph system had been i installed since the previous NRC inspection of this area. The chemistry /

radiochemistry facilities and analytical instrumentation appeared to be adequate to perform routine chemistry / radiochemistry requirements to support plant operation even though crowded conditions still exist in the laboratory are No violations or deviations were identifie . 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 6.3.7.0 in the T E h - ~ - - - - - --

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The NRC inspectors inspected the areas in the plant where the PASS hardware is installe 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 water and containment atmosphere following a reactor incident. The licensee had completed semi-l annual PASS operator training for four C/RS staff as part of their shift qualificatio The newly hired C/RS technician will receive PASS operator training during the next semi-annual PASS requalification training in April 1986. The licensee had established an instrument calibration and maintenance / operability program for PASS in compliance with TS requirement The NRC inspectors reviewed the semi-annual surveillance test results and in-line instrument calibration and quality control records for 1984 and 198 The NRC inspectors made the following observation which was discussed with the licensee at the exit briefing as an item which could improve PASS operability testing. The semi-annual PASS operability and in-line instrument calibration check does not include any testing of valves or sample collection devices associated with the sampling of containment atmosphere. The NRC inspectors were concerned that this part of the PASS was not being routinely tested. The licensee agreed at the exit briefing to evaluate the need for containment atmosphere sample testing and take corrective action as necessar The licensee demonstrated PASS operability by collecting diluted grab samples of reactor water and containment atmosphere. The licensee demonstrated the in-line pH and conductivity instruments during the collection of the reactor water sample. The NRC inspectors noted that the pH meter malfunctioned during the demonstration. The licensee issued a work order to repair the pH meter and place it back in service. The NRC inspectors determined that the licensee's procedures and analytical sensitivities of chemistry and radiochemistry parameters were consistent with PASS requirement No violations or deviations were identifie . 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 13 in the USAR, requirements in Section 6.2 in the TS, and QA manual procedure The NRC inspectors reviewed the QA department organization, selected QA audit and surveillance procedures, audit and surveillance schedules for 1985 and 1986, QA auditor qualifications, and audit and surveillance report Audit and surveillance reports generated from QA activities during 1985 in the areas of chemistry / radiochemistry, chemistry personnel training, chemistry instrument calibration and quality control, chemistry sample control, radiochemistry analyses, and chemistry laboratory conditions were reviewed to ensure thoroughness of program evaluation and timely follow-up of audit finding The NRC inspectors found that the audit and surveillance plans and checklists were comprehensive and that the responses and corrective actions to audit findings were timely and in accordance with

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procedur It was noted that the chemistry / radiochemistry audits and surveillances were being conducted by qualified QA staff knowledgeable in chemistry / radiochemistry activities at a nuclear power facilit No violations or deviations were identifie . 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 6.3 in the T The NRC inspectors found the type and quantity of radiological analytical instrumentation in the radiochemistry counting room adequate to perform the required analyses specified 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, quality control charts, and other documentation of instrument performance. Data for the period July 1984 through February 1986 were reviewed. The licensee's records were in order and the data were presented according to procedure No violations or deviations were identifie . Analytical Measurements Confirmatory Measurements Confirmatory measurements were performed on the following samples in I the Region IV mobile laboratory at CNS during the inspection: l

(1) Elevated Release Point Particulate Filter (2) Elevated Release Point Charcoal Cartridge (3) Reactor Water Sample (4) Off Gas Sample (5) Liquid Floor Drain Storage Tank Sample (6) Condensate Demineralizer Effluent Tritium Sample The confirmatory measurements test 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

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in 10 CFR Part 20, Appendix B, Table II, and above the Lower Limit of Detection (LLD) for stack samples. Stack charcoal cartridge and stack particulate filter comparisons are based on established LLDs for total activity per sampl Attachment 1 contains the criteria used to compare result Attachment 2 lists the LLDs for stack sample Results The licensee maintains two germanium-lithium (GeLi) detectors connected to a Canberra gamma spectrometer system. Both detectors are used for routine isotopic analysis of radioactive samples to demonstrate l

compliance with TS and regulatory requirements. The C/RS maintains i detector (1) and the health physics section maintains detector (2).

l The analytical results from both detectors were compared with the NRC results, as well as with each other. The licensee performed the tritium analysis on their Beckman LS-100 liquid scintillation counting system. The individual sample analyses and comparison of analytical results of the confirmatory .aeasurements are tabulated in Attachment The licensee's gamma isotopic results from the listed samples in Attachment 3 showed 86 percent agreement with the NRC analyses based on 68 agreement results out of 79 total results compared. The C/RS results showed 88 percent agreement and the health physics section results showed 83 percent agreement with the NRC analysis result The 88 percent agreement results between the licensee and NRC are below the value that would be expected for an effective radiochemistry progra The normally expected agreement would be greater than 90 percent. The comparative measurements results were discussed with-the licensee during the exit briefing on March 7, 1986. The licensee stated that their radiochemistry program would be reviewed in an attempt to improve their measurement capabilities. The licensee's tritium result on the condensate demineralizer effluent sample was in agreement with the NRC analysis resul Confirmatory measurements were performed by the licensee on a liquid unknown sample prepared by the Radiological Environmental Sciences Laboratory (RESL) in Idaho Falls, Idaho, using known nuclide concen-trations of 895r, 90Sr, 3H, 137Cs, and 80Co. The licensee' analytical results were compared to the known sample activities and the results of the comparisons are presented in Attachment 3, sample 7. The licensee's results were in agreement with the certified activities for l 895r, 9 Sr, ta7Cs, and 80Co in the sample. The analytical result for tritium was in disagreemen ;

No violations or deviations were identifie i

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j 13. Whole Body Counting System l

The NRC inspectors reviewed the licensee's whole body counting system (WBCS)

l to determine compliance with 10 CFR Part 20.10 The NRC inspectors reviewed the health physics procedures which provide guidance in the operation, calibration, and quality control of the WBC The licensee's calibration program and quality control program for the WBCS were reviewed. The licensee's quality control program appeared to meet industry standard The NRC inspectors supplied the licensee with a whole body counting phantom to perform confirmatory measurements in their shadow shield style WBC The counting arrangements were essentially the same as those discussed in NRC Inspection Report 50-298/84-19. The results of the body positioning test and the comparison of the analytical result 3 of the confirmatory measurements against the standard activities are tabulated in Attachment The results of the organ burden activity measurements were approximately the same as experienced during the tests performed during the NRC inspection conducted in September 198 No violations or deviations were identifie . Exit Briefing The NRC inspectors met with the NRC resident inspector and licensee representatives identified in paragraph 1 of this report at the conclusion of the inspection on March 7, 1986. The lead NRC inspector 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 agreed to review the NRC inspectors' observations listed in paragraph .

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J ATTACHMENT 1

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. 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 '

requirement .

] In these criteria, the judgement limits vary in relation to the comparison of the resolutio ^L" 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 value RESOLUTION AGREEMENT RATIO

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

16 - 50 0.75 - 1.33

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51 - 200 0.80 - 1.25

>200 0.85 - 1.18

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The above criteria are applied to the following ahalyses:

(1) Gamma Spectrometr (2) Tritium analyses of liquid sample ,

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, (3) Iodine on adsorber (4) as5r and SOSr determination (5) Gross Beta where samples are counted on the same date using the same reference nuclid .

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ATTACHMEN1 2

LLD's for Nuclides on Particulate and Charcoal filters

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Nuclide LLD (uCi/ sample)

52Cr 1.0E-04 5*Mn 1.5E-05

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ssCo 1.5E-05 seFe 3.0E-05

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s7CO 2.0E-05 soCo 3.0E-05 esZn 3.0E-05 seSr 1.0E-05-y

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80Sr 2.0E-07 182I 2.0E-05

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184Cs 2.0E-05 137Cs 2.0E-05

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240Ba 2.0E-05 24'La 4.0E-05 141Ce 2.0E-05 244Ce 1.0E-04

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ATTACHMENT 3 Confirmatory Measurements Results 1. Elevated Release Point Particulate Filter (Sampled 08:15 CST, March 3, 1986)

NPPD NPPD Results NRC Results NPPD/NRC Comparison Nuclide De (uCi/ sample) (uCi/ sample) Ratio Decision ssCo (1) 6.6711.58E-05 5.87 0.97E-05 1.14 Agreement (2) 4.94 0.73E-05 0.84 Agreement

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6 Co (1) 3.8310.41E-04 2.3710.16E-04 1.61 Agreement (2) 2.6110.23E-04 1.10 Agreement 91Sr (1) 1.2710.14E-03 1.24 .08E-03 1.03 Agreement (2) 1.2110.09E-03 0.98 Agreement 91*Y (1) 5.5810.32E-02 6.9510.24E-02 0.80 Agreement (2) 7.0010.32E-01 1 Disagreement 137Cs (1) 3.6910.32E-04 2.9710.14E-04 1.24 Agreement (2) 3.2510.20E-04 1.10 Agreement 139Ba (1) NotIdentifig M 1.1310.04E-02 -

Disagreement (2) <3.39E-03 - -

No Comparison 14 Ba (1) 1.16t0.09E-03 1.1110.06E-03 1.05 Agreement (2) 1.0710.05E-03 0.97 Agreement 140La (1) 7.5710.61E-04 7.0610.33E-04 1.07 Agreement (2) 7.61 0.37E-04 1.08 Agreement 1/ Isotopic peak was present in the spectral data; however, the nuclide was not identified by the licensee because it was not included in the isotope library routinely used for analysis of this typ / Isotopic activity had decayed to below lower limit of detectability at the time of the licensee's analysis; therefore, no formal compariso . Elevated Release Point Charcoal Cartridge (Sampled 08:15 CST, March 3, 1986)

NPPD NPPD Results NRC Results NPPD/NRC Comparison Nuclide De (uCi/ sample) (uCi/ sample) Ratio Decision 1311 (1) 2.3410.02E-01 2.5510.002E-1 0.92 Agreement (2) 2.0310.01E-01 0.80 Disagreement 1321 (1) 3.0610.15E-03 2.8210.20E-03 1.08 Agreement (2) 2.65-10.47E-03 0.94 Agreement

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l 133I (1) 6.27t0.04E-02 6.5510.02E-02 0.96 Agreement 1 (2) 5.7810.04E-02 0.88 Agreement 135I (1) 2.6510.06E-02 2.90 0.05E-02 0.92 Agreement !

(2) 2.3010.07E-02 0.80 Agreement 3. Reactor Water Sample (Sampled 09:40 CST, March 4, 1986) )

NPPD NPPD Results NRC Results NPPD/NRC Comparison Nuclide De (uCi/ml) (uCi/ml) Ratio Decision 24Na (1) 8.9510.17E-04 8.3210.12E-04 1.08 Agreement (2) 8.3110.21E-04 1.00 Agreement 52Cr (1) 4.4310.11E-03 4.0810.06E-03 1.09 Agreement (2) 4.4510.15E-03 1.09 Agreement 54Mn (1) 2.0910.09E-04 2.53 0.07E-04 0.83 Agreement (2) 2.1510.10E-04 0.85 Agreement 56Mn (1) 5.0710.11E-03 4.8210.08E-03 1.05 Agreement (2) 4.6310.17E-03 0.96 Agreement 58C0 (1) 2.9310.10E-04 2.8110.07E-04 1.05 Agreement (2) 2.6710.09E-04 0.95 Agreement 60C0 (1) 2.0910.10E-04 2.0810.07E-04 1.01 Agreement (2) 2.1110.10E-04 1.01 Agreement 91Sr (1) 4.9910.36E-04 5.3510.22E-04 0.93 Agreement (2) 5.3910.34E-04 1.01 Agreement 92Sr (1) 1.5010.03E-03 1.3810.02E-03 1.09 Agreement (2) 1.3810.04E-03 1.00 Agreement 91*Y (1) 1.8210.19E-03 1.5210.03E-03 1.20 Agreement (2) 7.1210.33E-03 4.68 Disagreement 95Nb (1) 9.4115.17E-06 9.6814.00E-06 0.97 No Comparison (2) <9.06E-06 -

No Comparison -

99Mo (1) 4.0210.05E-03 2.0910.33E-04 1 Disagreementh (2) 3.4310.07E-03 1 Disagreement -

99"Tc (1) 5.0910.07E 4.8810.01E-03 1.04 Agreement 1 (2) <1.54E-05p3 No Comparison 131I (1) 2.5910.95E-05 2.7610.44E-05 0.94 Agreement (2) 3.6910.60E-05 1.34 Agreement

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l 132I (1) 9.2310.24E-04 8.80 0.18E-04 1.05 Agreement (2) 8.7610.30E-04 1.00 Agreement

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133I (1) 3.4710.12E-04 3.0810.06E-04 1.13 Agreement i (2) 3.2410.13E-04 1.05 Agreement i 134I (1) 2.3510.39E-03 2.4710.06E-03 0.95 Agreement

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(2) 3.7810.06E-02 15.30 Disagreement 135I (1) 8.1510.44E-04 8.3910.30E-04 0.97 Agreement (2) 9.2910.45E-04 1.11 Agreement i

j 139Ba (1) 1.7910.09E 1.7010.05E-03 1.05 Agreement (2) <2.00E-04p3 No Comparison

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-1/ Nuclide concentration determined by the NRC was less than 10 percent l of the isotopic value stated in 10 CFR Part 20, Appendix B, Table II; j therefore, no comparison was made.

l 2/ The licensee calculated the isotopic activity using an abundance

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factor for the 140.5 kev energy line of 3.8 percent while the NRC calculated the isotopic activity using abundance factor for the same

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energy line of 90.9 percent. Upon recalculation of the licensee's j isotopic data using the energy line abundance of 90.9 percent, which I was used by the NRC mobile laboratory, the licensee's results were in agreemen / Isotopic peak was present in the special data; however, the' licensee's peak confidence level for peak identification had been established so as not to allow analysis of nuclides at sensitivity levels equal to i '

10 percent of the isotopic values stated in 10 CFR Part 20, Appendix B, Table II, Column 2.

I Off Gas Sample  :

, (Sampled 15:28 CST, March 3, 1986) l NPPD NPPD Results NRC Results NPPD/NRC Comparison ,

Nuclide De (uCi/cc) (uCi/cc) Ratio Decision l

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m i as Kr (1) 4.2910.14E-02 3.1810.03E-02 1.35 _ Disagreement 87Kr (1) 1.3210.05E-01 1.4210.01E-01 0.93 Agreement 88Kr (1) 8.7010.40E-02 1.0610.01E-01 0.82 Agreement l l

13 axe (1) 2.2410.23E-02 2.1210.06E-02 1.06 Agreement 185"Xe (1) 4.2010.12E-01 4.2410.04E-01 0.99 Agreement issXe (1) 1.5310.02E-01 1.7410.01E-01 0.88 Agreement iasXe (1) 3.4510.68E+00 1.5010.02E+00 2.30 Disagreement

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5. Liquid Floor Drain Storage Tank Sample (Sampled 10:10 CST, March 4, 1986)

NPPD NPPD Results NRC Results NPPD/NRC Comparison Nuclide De (uCi/ml) (uCi/ml) Ratio Decision 24Na (1) 1.9910.30E-06 1.4610.15E-06 1.36 Agreement (2) 2.5610.25E-06 1.74 Disagreement 51Cr (1) 6.4213.45E-06 7.1911.28E-06 0.89 Agreement (2) 6.67tl.92E-06 0.93 Agreement 54Mn (1) 1.1810.07E-05 1.1210.03E-05 1.05 Agreement (2) 1.1310.05E-05 1.01 Agreement ssCo (1) 3.2910.58E-06 2.65 0.25E-06 1.24 Agreement (2) 2.0610.38E-06 0.78 Agreement GoCo (1) 1.5110.02E-04 1.3810.01E-04 1.10 Agreement (2) 1.4510.02E-04 1.06 Agreement 12sSb (1) 8.4110.19E-05 Not Identified M -

No Comparison (2) 7.9410.19E-05 -

No Comparison 131I (1) <6.33E-07 7.04tl.50E-07 -

No Comparison (2) 8.4812.59E-07 1.21 Agreement 134Cs (1) 1.0610.04E-05 9.9910.35E-06 1.06 Agreement (2) 9.95 0.33E-06 1.00 Agreement ta7Cs (1) 2.5810.08E-05 2.3410.04E-05 1.11 Agreement (2) 2.4610.06E-05 1.05 Agreement

140Ba (1) Not Identified _/ 3.3410.71E-06 -

Disagreement (2) 1.9410.94E-06 0.58 Agreement 1/ Nuclide was not identified by the NRC because it was not included in the NRC isotope library used for the analysis of this sample; therefore, no comparison was mad / Isotopic peak was not present in the :pectral dat . Condensate Demineralizer Effluent Tritium Sample (Sampled 10:00 CST, March 6, 1986)

NPPD Result NRC Result NPPD/NRC Comparison Nuclide (uCi/ml) (uCi/ml) Ratio Decision 3H 1.0810.01E-03 1.2410.07E-03 0.87 Agreement

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7. RESL Unknown Liquid Sample (Standardized 12:00 MS1, January 11, 1985)

NPPD Results NRC Results 1 NPPD/NRC Comparison Nuclide (uCi/ml) (uCi/ml) Ratio Decision 3H 3.0010.20E-05 4.2810.09E-05 0.70 Disagreement 895r 1.8810.02E 04 1.8010.06E-04 1.04 Agreement 90Sr 1.6510.05E-OL 1.98 0.08E-05 0.83 Agreement 137Cs 9.78 0.06E-0's 8.93 0.18E-06 1.10 Agreement GoCo 9.5310.73E )6 7.9810.16E-06 1.19 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 Standard i l

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ATTACHMENT 4 Whole Body Counting System Confirmatory Measurements

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1. Positioning Verification Test NRC Whole Body Phantom With 5 Percent Lung Burden Standard

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

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NPPD Result NPPD Result NPPD Result Standard

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Nuclide Test (1) Test (2) Test (3) Average Deviation I 60Co 0.656 0.650 0.659 0.655 0.004

2. Analytical Measurements

j Lung Test i NRC Whole Body Phantom With Various Lung Organ Burden Activities of j Cobalt-60 NPPD Results NRC Results* NPPD/NRC Test N % MP0B (uCi) (uCi) Ratio i 4 5% 0.657 0.500 1.31 i

5 50% 4.226 5.000 0.85

6 100% No Result 1! 10.000 -

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The WBCS failed due to excessive system dead time.

k i Thyroid Test

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NRC Whole Body Phantom With Various Thyroid Organ Burden Activities of Barium-133 as Mock Iodine-131

, NPPD Results NRC Results* NPPD/NRC

] Test N % MP08 (uCi) (uCi) Ratio

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7 5% 0.053 0.036 1.47 8 50% 0.489 0.350 1.40 9 200% 1.633 1.400 1.17 Lung and Thyroid Scan a

NRC Whole Body Phantom With Various Combinations of Lung and Thyroid Organ Burden Activities of Cobalt-60 in the Lungs and Barium-133 as Mock Iodine-131 in the Thyroid NPPD Results NRC Results* NPPD/NRC l Test N Nuclide % MPOB (uC1) (uC1) Ratio i

10 13aBa 200% 1.531 1.400 1.09 l SOCo 10% 0.608 1.000 1.22

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1 2 11 133Ba 5% No Result 1 0.036 -

80Co 5% 0.671 0.500 1.34 j 1/ The 80Co activity masked the 133Ba activity; therefore, the WBCS

was unable to analyze a 5 percent organ burden of 181I as " mock

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iodine" in the thyroid in the presence of a 5 percent organ

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burden of 80C0 in the lungs.

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• NRC values were taken from the standard certificates supplied with the standards as prepared by a commercial vendor and j verified by the NRC_'s laboratory, RESL, in Idaho Falls, Idaho.

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