IR 05000254/1987003

Safety Insp Repts 50-254/87-03 & 50-265/87-03 on 870126- 0209.No Violations or Deviations Identified.Major Areas Inspected:Confirmatory Measurement Program,Radiological Environ Monitoring Program & Violation 86018-02

ML20211N084
Person / Time
Site:	Quad Cities
Issue date:	02/18/1987
From:	Januska A, Schumacher M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20211N033	List: IR 05000254/1987003 ML20211N028
References
50-254-87-03, 50-254-87-3, 50-265-87-03, 50-265-87-3, NUDOCS 8702270438
Download: ML20211N084 (12)

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I U.S. NUCLEAR REGULATORY COMISSION l

l REGION III Reports No. 50-254/87003(DRSS);50-265/87003(DRSS)

Docket Nos. 50-254;.50-265 Licenses No. DPR-29; DPR-30 Licensee: Commonwealth Edison Company Post Office Box 767 Chicago, IL 60690 Facility Name: Quad Cities Nuclear Power Station, Units 1 and 2 Inspection At: QuadCitiesSite,Cordova, Illinois Inspection Conducted: January 26-30, 1987; Telephone Conversations: . February 2, 3, 5, and 9, 1987 Inspector:

./5hwkV A. E Januska M / 2 Date

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Approved By: M. C. Schumacher, Chief 7 Radiological Effluents and Date Chemistry Section I,nspection Summary Inspection on January 26-30, February 2, 3, 5, and 9, 1987 (Reports No. 50-254/8/003(DR55); 50-265/8/003(DR55))

Areas inspected: Routine announced inspection of (1) the confirmatory measurements sam

)rogram Region III Mo)ile Laboratory, including (2) ple split and cnsite analysis with thethe radiological e program, (3) violation 86018-02, and (4) open items identified during previous inspection Results: No violations or deviations were identifie .

B70219 N0**l & 05000254

PDR j i

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DETAILS 1. Persons Contacted 1N. Kalivianakis, Ceco Division, Vice President 1R. Bax, Station Manager 1D. Gibson, QA Superintendent 1R. Robey, Services Superintendent 14J. Sirovy, Rad-Chem Supervisor 1M. Kooi, Regulatory Assurance Supervisor 124P. Behrens, Lead Chemist 1S. Willoughby, QA Inspector R. Hebeler, Laboratory Foreman J. Jacobson, Rad-Chem Technician M. Schulman, Rad-Chem Technician 3V. Neels, General Instructor 1A. Morrongiello, NRC Resident Inspector 1 Denotes those present at exit interview on January 30, 198 Participated in telephone discussion on February 2 and 3, 198 Participated in telephone discussion on February 5, 198 Participated in telephone discussion on February 9, 198 . Licensee Action on Previous Inspecticn Findings (Closed) Open Item (50-254/85006-02; 50-265/85006-02) Training of licensee personnel in water chemistry centrol. Revision 1 of the Nuclear Stations Division Directive NSDD-S17 dated August 26 1986 requiresacomprehensivecontinuingawarenessprogramforall personnel involved in the Water Chemit < Control Program. The Production Training Department developea and issued the " Introduction to the Company BWR Chemistry Control Program," (Revision 0) approved January 13, 1987, targeted for personnel involved in Water Chemistry Control. Training on the Water Chemistry Control Program will be presented as part of initial training for new Rad-Chem technicians and incorporated into training for supervision new to this progra (Closed) Open Item (50-254/85006-04; 50-265/85006-04) Full

implementation of the licensee's water chemistry control program will be examine The licensee has identified needed modifications to plant water systems, sampling systems and in-line monitors and has developed a program and schedules for completion of these modifications in an effort to enhance the Water Chemistry Control Progra (0 pen) Open Item (50-254/85006-06; 50-265/85006-06) Licensee plans to upgrade process instrumentation. In-line process monitors to continuously monitor chemical parameters in different plant components and systems have been scheduled for replacement or initial installation for both units. Unit 1 is scheduled for completion in early 1988 and Unit 2 tentatively contingent on the scheduled to start refueling outage modifications schedule. Thesein mid will be1988,ined exam during subsequent inspection sp- -=-- ---

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d .- (Closed) Violation (50-254/86018-02 50-265/86018-02). Failure to follow a written procedur The licensee issued QCP 600-9

'! Determination of Sodium Pentaborate,"' Revision 10,- dated January 1987, in which Section F.5.a was changed to allow the use of 0.10N standard hydrochloric acid ampules or oven dried and desiccate potassium acid phthalate (KAP) to prepare a certified standard

.for standardizing sodium hydroxide. The option will assure that '

a certified standard is available and.the procedure requirement me (Closed) Open Item (50-254/86018-03; 50-265/86018-03)' Incorporate

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use of quality control check samples and duplicate sample measurements

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when analyzing for sodium pentaborate. The licensee has revise QCP 600-S4, " Standby Liquid Control Tank Sodium Pentaborate,'! the check list ~ for QCP 600-9, " Determination of Sodium Pentaborate,"

to require that (1) a control check sample, supplied by chemistr supervision, is analyzed with each batch (normally two samples) yand~

be within ten percent of the known sample value, and (2) duplicate

' measurements of each sample are run for the "ml of Na0H used in titration, percent boron in solution and percent sodium pentaborate."

These.results'are reported in the appropriate spaces on QCP 600-S (0 pen) Open Item (50-254/86018-04; 50-265/86018-04) Resolve high variability in RC[ results of Cr analyses by atomic absorptio The licensee has found that Cr absorption is either suppressed or enhanced depending on the fuel: air. ratio. Perkin-Elmer literature

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states'that suppression of Cr absorption is attributable to the presence of Fe and Ni. The licensee will continue to study the problem in an attempt to determine an optimum fuel: air ratio and the effect of.the presence of Fe and N . (Closed) Open Item (50-254/86018-05; 50-265/86018-05) Track and-correct nonstatistical behavior of the alpha-beta counters. The licensee investigated.the cause of acceptable but-high values noted on control charts. The licensee uses shallow and deep planchet

' holders for these counter Re)lacement deep planchet holders were found to be of a different dept 1 than the original holders. When used for QC checks, the shallower of the two produced higher readin The licensee has standardized on one depth deep, planchet holder Planchets continue to be checked for contamination weekl (0 pen) Open Item (50-254/86018-06; 50-265/86018-06) Analyze radwaste sample for beta emitters and report results to Region III. Results of the sample comparisons are listed in Table 2; comparison crit n ia are given in Attachment 1. The two nonconservative disagreements, gross-beta and Fe-55 were discussed with the licensee. The licensee stated that replicate portions of the sample used for the gross beta-determination were pre)ared for counting by the licensee immediately after collection and tie activities measured were statistically the sam The Fe-55 analysis was performed by a contractor and sample split, plate out or analytical technique could have contributed to the disagreemen The inspector noted that nonconservative disagreements s 3

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with the NRC for-gross beta and Fe-55 occurred in the third quarters

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of 1985 and 1986 with first quarter results being in agreement. In- ,

addition to the NRC comparisons, purchased spiked' samples and an EPA sample _ analyzed by the contractor in 1986 resulted in disagreements'

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for Sr-89, Sr-90_and Fe-55. The licensee brought this-to the attention of the Radiochemistry Services Group in October-of- 1986.* -

A new contractor has been awarded the contract-for 198 The inspector provided a sample container.and~ requested that another sample of the River Water Discharge Tank be collected and portions sent to the' NRC's Reference Laboratory, counted for gross beta by the licensee and for Fe-55 by the licensee's contractor, and the results reported to Region III. As' Table 4.8-3, " Radioactive Liquid Waste Sampling and Analysis Program," requires analyses for Fe-55 for quarterly grab samples of continuous-releases and for quarterly composites of-batch releases, and owing:to the nonconservative-comparisons, the licensee was also asked to review liquid release data for the periods where the nonconservative-disagreements occurred to assess the impact on ' effluents reporte , Confirmatory Measurements

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Six samples-(air particulate, charcoal river discharge tank, gas, reactor coolant, and a spiked air particulate),were analyzed for gamma emitting

' isotopes by the licensee and in the Region III Mobile Laboratory onsit Results of the sample comparisons are listed-in Table 1. The licensee achieved 88 agreements out of 90 comparison In order to check-backup'and emergency gamma spectroscopy systems, the

. licensee was asked to analyze samples using both nnrmal counting room detectors and the Post Accident Radionuclide Analysis Portable System (PARAPS).

As no particulate nuclides were quantifiable, a spiked air particulate sample, belonging to the licensee was counted-on Detectors 3 and 4 and compared as if a real sample. An off gas sample was counted on .

Detectors 1 and 2 and a River Discharge Tank sample on Detectors 3 -

and 4 No disagreements resulted from these sample A charcoal cartridge was counted on Detector 1 and PARAPS with one

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disagreement for As-76. As-76 and Sr-91 have energies that are 4 kev . ,

apart. In examining the activity reported for both nuclides on both of

, the licensee's detectors, it appears from the ratio for Sr-91 on the '

PARAPS that it did not resolve the two energies as did Detector 1 and the

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NRC detectors but attributed the total activity to Sr-91. As little as -

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4E-04uCi subtracted from the licensee's Sr-91 value, adjusted for the differences in abundance and half-life attributed to as-76 would result

in an agreement and remain an agreement for Sr-91.

i-l * Inspection Reports No. 254/86018; No 265/86018

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A sample of primary coolant resulted in six disagreements out of 17 comparisons, a resample four disagreements out of 16 comparisons and a final filtered, resample five disagreements out of 16 comparisons on the PARAPS and all agreements on Detector The licensee later discovered that in starting the PARAPS for these comparisons the wrong clock time was entered which affected the short lived nuclides. A recalculation changed four disagreements to agreements. No reason for the lone disagreement, Ba-139 was. obvious. The licensee discussed this event with the RCT . Radiological Environmental Monitoring Program (REMP)

The inspector accompanied a licensee re)resentative during a normal scheduled weekly inspection of the sout1 meteorological tower and onsite environmental radiological monitoring stations 1, 2, and 3. Equipment was checked for operability with key parameters recorded on procedural checklists. Calibration tags for monitoring station equipment were up-to-date and equipment functiona The inspector examined an audit of Teledyne Isotopes, the licensee's environmental contractor, dated October 16, 1985, conducted to verify the implementation of the contractor's QA Manual and Specification No significant findings were identified although the audit remains open pending the development of a procedure to document software verificatio The 1986 audit was delayed and is scheduled for the first quarter of 198 The inspector also examined surveillances of the REMP performed in 1986 lementation of the REMP for 1985 and January which throughverified June of (1)

1986the imp (2) that the recuirements of Table 4.8-4 and and the ODCM were me Samples were verifiec to have been collected and analyzed no increase asinrequired;ty activi appears attributable to the operation of theonly a sma plan . Exit Interview The inspector reviewed the scope and findings of the inspection with licensee representatives denoted in Section 1 on January 30, 1987. The inspector discussed the problem encountered with the PARAP Further discussions took placo in telephone conversations on the following dates:

• February 2,1987 - the licensee explained the reason for the disagreement of the PARAPS results for the primary coolant analyses (Section3),

• February 3 and 4, 1987 - the inspector requested further information regarding Open Item 85006-02, (Section 2.a) and

• February 9,1987 - the inspector requested informa+' n regarding Open Item 86018-06, discussed further sampling ana lyses for gross beta and Fe-55 and requested a review of liq effluent release results to assess any impact on results repoi d (Section 2.b).

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During the exit interview, the inspector discussed the likely informational content of the inspection report with regard to documents or processes reviewed.by the' inspector during the inspection. Licensee representatives did not identify any such documents as proprietar Attachments:

1. Table 1, Confirmatory Measurements Program Results,FirstQuarter1987 Table 2, Confirmatory Measurements Program Results, Fourth Quarter 1986 Attachment 1, Criteria for Comparing Analytical Results

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TABLE 1 U S NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT CONFIRMATORY MEASUREMENTS PROGRAM FACILITY: QUAD FOR THE 1 OUARTER OF 1987 l

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L'I CENSEE: NPC-

~ SAMPLE ISOTOPE RESULT ERROR RESULT ERROR RATIO REG T C FILTER NA-24 A

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4.3E-02 4.5E-04 4.0E-02 0.0E-01 9.4E-01 9.5E 01 AS-76 7.1E-04 1.3E-04 6.7E-04 0.0E-01 9.4E-01 5.3E 00 A bCT i CO-60 6.6E-04 1.1E-04 3.3E-04 0.0E-01 5.OE-01 6.2E 00 A I-131 9.2E-03 1.4E-04 8.6E-03 0.0E-01 9.4E-01 6.6E 01 A I-133 1.9E-02 2.1E-04 1.8E-02 0.0E-01 9.7E-01 8.8E 01 A SR-91 1.4E-03 2.0E-04 1.2E-03 0.0E-01 8.5E-01 7.1E 00 A MO-99 3.2E-03 5.4E-04 2.7E-03 0.0E-01 8.5E-01 5.9E 00 A LA-140 6.0E-04 1.0E-04 5.2E-04 0.0E-01 8.6E-01 5.9E 00 A OFF GAS KR-85M 1.7E-03 2.7E-05 1.4E-03 0.OE-01 8.1E-01 6.4E 01 A 7)er f KR-87 8.8E-03 1.1E-04 8.6E-03 0.0E-01 9.8E-01 8.0E 01 A KR-88 5.5E-03 6.9E-05 5.6E-03 0.0E-01 1.0E 00 8.0E 01 A XE-133 6.4E-04 2.4E-05 5.5E-04 0.0E-01 3.6E-Ot 2.7E 01 A XE-135 8.2E-03 3.3E-05 7.8E-03 0.0E-01 9.5E-01 2.5E 02 A XE-135M 5.6E-02 5.0E-03 5.1E-02 0.0E-01 9.1E-01 1.1E 01 A XE-138 2.2E-01 1.6E-02 2.3E-01 0.0E-01 1.1E 00 1.3E 01 A C FILTER NA-24 4.3E-02 4.5E-04 4.2E-02 0.0E-01 9.8E-01 9.5E Ot A AS-76 7.1E-04 1.3E-04 0.0E-01 0.0E-01 0.0E-01 5.3E 00 D PA R A PS CO-60 6.6E-04 1.1E-04 5.7E-04 0.0E-01 8.6E-01 6.2E 00 A I-131 9.2E-03 1.4E-04 1.0E-02 0.0E-01 1.1E 00 6.6E 01 A I-133 1.9E-02 2.1E-04 2.0E-02 0.0E-01 1.1E 00 8.8E 01 A SR-91 1.4E-03 2.0E-04 1.8E-03 0.0E-01 1.3E 00 7.1E 00 A MO-99 3.2E-03 5.4E-04 2.4E-03 0.0E-01 7.6E-01 5.9E 00 A LA-140 6.0E-04 1.0E-04 6.9E-04 0.OE-01 1.1E 00 5.9E 00 A OFF GAS KR-85M 1.7E-03 2.7E-05 1.4E-03 0.0E-01 8.1E-01 6.4E 01 A lb E7- A KR-87 8.8E-03 1.1E-04 1.0E-02 0.0E-01 1.1E 00 8.0E 01 A KR-88 5.5E-03 6.9E-05 6.0E-03 0.0E-01 1.1E 00 8.0E 01 A XE-133 6.4E-04 2.4E-05 4.9E-04 0.0E-01 7.7E-01 2.7E 01 A XE-135 8.2E-03 3.3E-05 8.0E-03 0.0E-01 9.8E-01 2.5E 02 A XE-135M 5.6E-02 5.0E-03 5.5E-02 0.0E-01 9.8E-01 1.1E 01 A T TEST RESULTS:

A= AGREEMENT D= DISAGREEMENT o= CRITERIA RELAXED N=NO COMPARISON

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. TABLE 1 U S NU^ LEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT CONFIRMATORY MEASUREMENTS PROGRAM FACILITY: QUAD FOR THE 1 QUARTER OF 1987

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LICENSEE *--- ---LICENSEE NRC----

SAMPLE ISOTOPE RESULT ERROR RESULT ERROR RATIO RES T G F GAS XE-138 2.2E-01 1.6E-02 2.4E-01 0.0E-01 1.1E'00 1.3E 01 A F SPIKED CO-57 2.8E-02 1.7E-04 2.7E-02 0.0E-01 9.6E-01 1.7E 02 A bFF3 .CO-60 3.2E-02 4.2E-04 3.4E-02 0.0E-01 1.1E 00 7.5E 01 A HG-203 1.6E-02 2.1E-04 1.8E-02 0.0E-01 1.1E 00 7.8E 01 A Y-88 4.4E-02 5.8E-04 4.5E-02 0.0E-01 1.0E 00 7.6E 01 A CD-109 1.2E 00 5.5E-03 1.2E 00 0.0E-01 9.8E-01 2.2E 02 'A SN-113 3.3E-02 3.6E-04 3.9E-02 0.0E-01 1.2E 00 9.2E 01 A 1 CS-137 4.9E-02- 5.0E-04 5.6E-02 0.0E-01 1.1E 00 9.9E 01 A CE-139 1.9E-02 1.7E-04 2.2E-02 0.0E-01 1.1E 00 1.1E 02 A PRIMARY NA-24 1.2E-02 7.4E-05 1.1E-02 0.0E-01 9.4E-01 1.6E 02 A bf;" 3 CR-51 6.1E-03 1.5E-04 6.6E-03 0.0E-01 1.1E 00 4.0E 01 A MN-54 9.9E-05 1.3E-05 1.1E-04 0.0E-01 1.1E 00 7.4E 00 A MN-56 2.9E-03 1.'3E-04 2.2E-03 0.0E-01 7.6E-01 2.2E 01 A CO-58 2.0E-04 2.1E-05 1.7E-04 0.0E-01 8.6E-01 9.2E 00 A CO-60 2.7E-04 1.8E-05 2.4E-04 0.0E-01 8.9E-01 1.5E 01 A AS-76 4.8E-04 3.9E-05 4.7E-04 0.0E-01 0.9E-01 1.2E 01 A I-131 -1.3E-04 1.5E-05 1.4E-04 0.0E-01 1.15 00 8.5E 00 A I-132 5.0E-03 1.6E-04 4.9E-03 0.0E-01 9.85-01 3.2E 01 A I-133 2.0E-03 2.6E-05 2.0E-03- 0.0E-01 1.0E 00 7.6E 01 A I-134 2.1E-02 3.3E-03 1.8E-02 0.0E-01 8.6E-01 6.4E 00 A I-135 5.0E-03 1.6E-04 4.3E-03 0.0E-01 8.7E-01 3.1E 01 A SR-91 2.0E-03 1.2E-04 2.1E-03 0.0E-01 1.0E 00 1.7E 01 A SR-92 7.5E-03 1.4E-03 8.2E-03 0.0E-01 1.1E 00 5.2E 00 A

Y-92 5.0E-03 4.7E-04 4.7E-03 0.0E-01 9.5E-01 1.1E Gt A ,

MO-99 4.8E-04 9.9E-05 4.4E-04 0.0E-01 9.2E-01 4.8E 00 A BA-140 2.2E-04 5.1E-05 3.0E-04 0.0E-01 1.4E 00 4.3E 00 A TC-99M 1.2E-02 3.1E-05 1.2E-02 0.0E-01 1.0E 00 3.8E 02 A BA-139 7.3E-03 9.!E-04 5.4E-03 0.0E-01 7.4E-01 8.0E 00 A

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L WASTE MN-54 4.9E-07 6.6E-08 4.8E-07 0.0E-01 9.8E-01 7.4E 00 A ( h e't 3 T TEST RESULTS:

A= AGREEMENT DeDISAGREEMENT

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TABLE 1 U S NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT CONFIRMATORY MEASUREMENTS PROGRAM FACILITY: QUAD FOR THE 1 OUARTER OF 1987

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LICENSEE---- ---LICENSEE:NRC----

SAMPLE ISOTOPE RESULT ERROR RESULT ERROR RATIO RES T

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L WASTE CO-60 4.7E-06 1.5E-07 5.4E-06 0.0E-01 1.1E 00 3.0E 01 A AG-110M 9.0E-07 6.8E-08 6.OE-07 0.0E-01 6.7E-01 1.3E 01 A CS-137 9.1E-07 8.0E-08 7.7E-07 0.OE-01 8.4E-01 1.1E 01 A F SPIKED CO-57 2.8E-02 1.7E-04 2.7E-02 0.0E-01 9.6E-01 1.7E 02 A CO-60 7.5E 01 A

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D67- 4 3.2E-02 4.2E-04 3.3E-02 0.0E-01 1.0E 00 HG-203 1.6E-02 2.1E-04 1.PE-02 0.0E-01 1.1E 00 7.8E 01 A Y-88 4.4E-02 5.8E-04 4.4E-02 0.0E-01 1.0E 00 7.6E 01 A CD-109 1.2E 00 5.4E-03 1.3E 00 0.0E-01 1.1E 00 2.2E 02 A SN-113 3.3E-02 3.6E-04 3.8E-02 0.0E-01 1.1E 00 9.?E 01 A CS-137 4.9E-02 5.0E-04 5.5E-02 0.0E-01 1.1E 00 9.9E 01 A CE-139 1.9E-02 1.7E-04 2.2E-02 0.0E-01 1.1E 00 1.1E 02 A L WASTE MN-54 4.9E-07 6.6E-08 4.5E-07 0.0E-01 9.2E-01 7.4E 00 A b gy- 4 CO-60 4.7E-06 1.5E-07 5.6E-06 0.0E-01 1.2E 00 3.0E 01 A AG-110M 9.0E-07 6.8E-08 3.0E-07 0.0E-01 8.9E-01 1.3E 01 A CS-137 9.1E-07 8.0E-08 7.6E-07 0.0E-01 8.3E-01 1.1E 01 A PRIMARY NA-24 1.1E-02 8.2E-05 9.3E-03 0.0E-01 0.77 01 1.3E 02 A CR-51 6.3E-03 2.2E-04 6.8E-03 0.0E-01 1.1E 00 2.9E 01 A PARAPS MN-56 1.3E-03 2.3E-04 7.5E-04 0.0E-01 5.8E-01 5.6E 00 A CO-58 3.2E-04 3.3E-05 2.7E-04 0.0E-01 8.4E-01 9.8E 00 A CO-60 2.3E-04 2.7E-05 2.2E-04 0.0E-01 c.7E-01 0.4E 00 A AS-76 5.3E-04 5.5E-05 4.2E-04 0.0E-01 7.GE-05 9.7E 00 A I-131 1.4E-04 2.5E-05 1.oE-04 0.0E-01 1.3E 00 5.8E 00 A I-132 4.8E-03 9.2E-05 5.5E-03 0.0E-01 1.1E 00 5.3E 01 A I-133 2.0E-03 3.3E-05 1.9E-03 0.0E-01 C.4E-01 6.1E 01 A I-134 2.1E-02 3.2E-04 2.1E-02 0.0E-01 1.0E 00 6.5E 01 A I-135 5.2E-03 1.7E-04 4.3E-03 0.0E-01 8.3E-01 3.1E 01 A SR-91 2.0E-03 1.3E-04 1.5E-03 0.0E-01 7.4E-01 1.6E 01 A SR-92 4.9E-03 9.1E-05 6.0E-03 0.0E-01 1.2E 00 5.4E 01 A MO-99 4.9E-04 1.6E-04 7.7E-04 0.0E-01 1.6E 00 3.1E 00 A

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T TEST RESULTS:

A= AGREEMENT D= DISAGREEMENT

• = CRITERIA PELAXED N=NO COMPARISON

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TABLE 1 U S NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT CONFIRMATORY MEASUREMENTS PROGRAM FACILITY: QUAD FOR THE 1 QUARTER OF 1987

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LICENSEE- ---LICENSEE:NRC-SAMPLE ISOTOPE RESULT ERROR RESULT ERROR RATIO RES T PRIMARY TC-99M 1.7E-02 4.5E-05 1.8E-02 0.0E-01 1.0E 00 3.8E 02 A BA-139 6.4E-03 3.1E-04 4.0E-03 0.0E-01 6.2E-01 2.1E 01 D Y-92 8.7E-04 2.1E-04 4.6E-04 0.0E-01 5.3E-01 4.1E 00 A T TEST RESULTS:

A= AGREEMENT DoDISAGREEMENT osCRITERIA RELAXED

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TABLE 2 U S NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT CONFIRMATORY MEASUREMENTS PROGRAM FACILITY: QUAD CITIES FOR THE 4 OUARTER OF 1986

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LICENSEE---- ---LICENSEE:NRC----

SAMPLE ISOTOPE RESULT ERROR RESULT ERROR RATIO RES T L IJASTE G BETA 6.6E-06 2.0E-07 4.7E-06 5.0E-07 7.1E-01 3.3E 01 D H-3 2.5E-03 4.0E-05 2.4E-03 0.0E-01 9.6E-01 6.2E 01 A SR-89 5.5E-08 9.0E-09 9.1E-08 0.0E-01 1.6E 00 6.1E 00 A SR-90 5.2E-08 4.0E-09 3.3E-08 0.0E-01 6.3E-01 1 SE 01 A FE-55 2.0E-06 1.0E-07 1.3E-06 0.0E-01 6.5E-01 2.0E 01 D T TEST RESULTS:

AaAGREEMENT DaDISAGREEMENT o= CRITERIA RELAXED NcNO COMPARISON

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ATTACHMENT 1 CRITERIA FOR COMPARING ANALYTICAL MEASUREMENTS This attachment provides criteria for comparing results of capability tests and verification measurements. The criteria are based on an empirical relationship which combines prior experience and the accuracy needs of this progra '

In these criteria, the judgment limits are variable in relation to the comparison of the NRC's value to its associated one sigea uncertainty. As that ratio, referred to in this program as " Resolution", increases, the acceptability of a ,

licensee's measurement should be more selective. Conversely, poorer agreement l should be considered acceptable as the resolution decreases. The values in the -

ratio criteria may be rounded to fewer significant figures reported by the NRC Reference Laboratory, unless such rounding will result in a narrowed category of acceptanc RESOLUTION RATIO = LICENSEE VALUE/NRC REFERENCE VALUE Agreement

<4 0.4 - .5 - ;

8- 15 0.6 - 1.66 16 - 50 0.75 - 1.33 51 - 200 0.80 - 1.25 200 - 0.85 - 1.18 Some discrepancies may result from the use of different equipment, techniques, and for some specific nuclides. These may be factored into the acceptance criteria and identified on the data sheet.

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