IR 05000456/1986051

Insp Repts 50-456/86-51 & 50-457/86-39 on 860917-19 & 22-23. No Violations or Deviations Noted.Major Areas Inspected: Chemistry/Radiochemistry Program,Including Water Chemistry Control, Procedures,Facilities & Mgt Control

ML20215F941
Person / Time
Site:	Braidwood
Issue date:	10/09/1986
From:	Holtzman R, Oestmann M, Schumacher M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20215F905	List: IR 05000456/1986051 ML20215F901
References
50-456-86-51, 50-457-86-39, NUDOCS 8610160426
Download: ML20215F941 (13)

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U.S.- NUCLEAR REGULATORY COMISSION

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REGION III'

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Reports No. 50-456/86051(DRSS); 50-457/86039(DRSS)

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' Docket Nos. 50-456; 50-457 ' Licenses No. CPPR-132; CPPR-133

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Licensee: Commonwealth Edison Company ,

Post Office Box 767

. Chicago, IL 60690 Facility Name: Braidwood Nuclear Power Station, Units 1 and 2 Inspection Conducted: September 17-19 and 22-23, 1986 Telephone conversation on September 24 and 29, 1986 ,

' Inspectors: .' . Ho zman /

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! 9/]c m!M.J.Oestmann$ Date f i Approved By: ief

Radiological Effluents and Date

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Chemistry Section r

l Inspection Summary

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Inspection on September 17-19 and 22-23, 24 and 29, 1986 (Reports

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No. 50-456/86051(DR55); No. 50-457/86029(DR551)

Areas Inspected: Routine announced inspection of: (1) chemistry / radiochemistry i

- program, including water chemistry control, procedures, facilities, management controls, training and qualifications, quality assurance and quality control;

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(2) Confirmatory Measurements Program, including discussions of results of a

? spiked sample of a liquid; and (3) actions taken on previous open items, i: Results: No violations or deviations were identifie t

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DETAILS- Persons Contacte '1L. E. Davis, Assistant Superintendent, Technical Services, Braidwood (Bwd)

10. W. Schroeder,- Services Superintendent, Bwd 1P. L. Barnes,. Superintendent, Regulatory Assurance, Bwd 1J. K. Jasnosz, Engineer, Regulatory Assurance, Bwd 1L. M. Kline, Regulatory Assurance, Bwd 1P. A. Boyle, Regulatory Assurance, Bwd R. E. Aker, Radiation-Chemistry Supervisor, Bwd 1M. J. Anderson, Station Chemist, Bwd ll. Johnson-Hester, Engineer, Quality Assurance, Bwd 2J. Burns, General Chemist, Bwd R. F. Rysner, Chemistry Engineering Assistant, Bwd R. Vebras, Unit Chemist, Bwd J. McIntyre, Laboratory. Foreman, Bwd L. A. Literski, Emergency Planning (GSEP) Coordinator, Bwd M. Sweeney, Rad-Chem Technician (RCT), Bwd D. Southcomb, RCT, Bwd W. Lloyd, Chemistry Engineering Assistant, Bwd 1T. Tongue, NRC Senior Resident Inspector The inspectors also interviewed several other licensee personnel during the course of the inspection, including chemistry, health physics, and training personne Denotes those present at the plant exit-interviews on September 23, 198 Telephone discussion held on September 29, 198 . Licensee Action on Previous Inspection Findings (0 pen) Open Item (50-456/81-xx-01): NRC to collect water samples from Braidwood city wells and wells from the Thelma Corbin Farm in-Wilmington, Illinois after the Braidwood Station is in operatio No change in status from the previous inspection has occurred. This item will remain open until samples are collected and analyzed after the plant becomes operational, (Closed) Open Item (50-456/84-03-01; 50-457/84-03-01):

Establishment and implementation of generic and site specific training programs for Radiation Chemistry Technicians (RCTs). The inspectors reviewed the progress made in implementing RCT training programs. Twenty-nine RCTs have completed the generic training program presented at the Braidwood Production Training Center and twenty-eight have completed their qualifications / certifications for on-the-job (0JT) training. This completes the licensee's commitment to have about 29 RCTs certified by FLOL. One RCT of the 29 is on leav ' Recently, 11 new RCTs have been hired and are receiving their generic training at the Production Training Center. They are also doing some OJT work at the plant, but they will not be fully qualified for six to nine more month The inspectors confirmed that, since the last inspection, the 28

'RCTs have met the radiochemistry qualification requirements by having had training in handling radioactive sources, and in operating the Canberra alpha-beta counters and the AAIS gamma spectrometers. This

. item is close ' (0 pen) Open Item (50-456/86017-01; 50-457/86015-01): Licensee to install three additional air samplers in the field by 5% powe The three air samplers were installed on July 26, 1986. The-

~ inspector observed during a tour of the samplers, that the three stations were operating and had been calibrated on a prescribed schedule. No leakage of air into the intake trains after the filters was observed. However, the Tygon tubing that prevents recirculation of exhaust air into the intake, had not been installed on the pump exhaust. This item will remain open, pending installation of the tubin (0 pen) Open Item (50-456/86017-02; 50-457/86015-02): Collection of samples and operation and calibration of in-line monitors for secondary chemistry control and testing of condensate polishers and

. makeup demineralizer (MUD) syste The inspectors: observed the-steam generator (SG) blowdown sampling system in the hot laboratory and the secondary water sampling system in the turbine buildin Licensee representatives stated that both sampling systems were l operable and used during the intergrated hot-functional (IHF)-

tests. Because the secondary side had no water, the inspectors could not observe their operability. The inspectors also observed'

the polishers and the MUD system and confirmed that the MUD system was operational. In-line monitors, such as those for sodium,

-dissolved oxygen, silica, and conductivity were functional and calibrated. The polishers were not operational due to lack of water on the secondary side. This item will remain open, for examination of the systems and the operability of in-line monitors and sample panel prior to criticalit (0 pen) Open Item (50-456/86037-01; 50-457/86029-01): Licensee to develop acceptance limits for the RCT performance tests. The licensee set limits on the RCT performance tests at 20% pass-fall limits for the analyses of a 25 ppb chloride standard and a 100 ppb fluoride standard by specific ion probes, and 3% for the titration boron (1000 ppm standard). As only six RCTs had been tested at the time of this inspection, this item will remain open pending further testing of the RCT's prior to criticality (Section 8).

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. (0 pen) Open Item (50-456/86037-02; 50-457/86029-02): Comparison

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of corporate interlaboratory comparison of non-radiological

, analyses. Preliminary results were available for 10 elements

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s in a 300 ppm boron solution matrix. Iron, copper, silica and sulfate deviated from the known values by less than 8%, while Al, Mg, Ca, C1, F and Na differed by more than 16% (16-75%).

The completed comparison will be reviewed in a subsequent inspectio (Closed) Open Item (50-456/86037-03; 50-457/86029-03): Licensee to implement regular performance checks and quality control charts for the Ge detectors and liquid scintillation counters (LSC). The licensee has implemented the regular performance checks and control charts for the calibrated counters (two Ge detectors, two LSCs and three Canberra alpha-beta counters). The performance check log sheets are being revised and a licensee representative agreed to make further changes to improve their usefulness by adding the mean count rate of the check sources, the counting times, and source identification. A comments column will also be added so that changes in the system can be tracked, e.g, repairs, changes in source count rates, and changes in gas cylinders. Control limits on

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the system are based on 2-sigma (counting statistics) variation from the mean values. This is consistent with the AAIS system which

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removes the counter from service based on this control limit. The representative also agreed to increase the counting times of the check sources on the alpha-beta counters to obtain more than 10,000 count This will reduce the counting uncertainties to less than 1%. The expected source count rate will be derived from the previous month's data, rather than 40 to 50 repeat counts taken at the beginning of the month. The changes will be followed with the Open Item under Section (0 pen) Open Item (50-456/86037-04; 50-457/86029-04): The licensee will determine gamma, H-3, Sr-89, Sr-90 and Fe-55 activities in a RESL spiked sample in various geometries and report the results to Region III. The licensee analyzed a second spiked liquid RESL sample in various geometries used in the laboratory, the 14-ml vial, a one-liter bottle and a 450-ml Marinelli beake Comparisons of the licensee's results with those of the NRC are presented in Table 1, and the acceptance criteria are given in Attachment 1. The Sr-89, Sr-90, and Fe-55 values are from the licensee's off-site contractor determined in the previous RESL sampl The licensee laboratory obtained 13 agreements in 13 comparison Additional counts done in duplicate and on different counters were also in agreement. However, for the one-liter sample geometry the ratio for Co-60 was near the upper limit for agreement due to all three Co-60 values being higher than the RESL value. One of the values taken by itself, would be a disagreement. Since the other licensee values were in close agreement, this indicates a possible calibration error in the high energy region. The licensee representative agreed to look into this discrepanc __ - - _ _ _ - - -_. -. - ._

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The Sr-89 and Sr-90 values were in disagreemen Since we were unable to ascertain the cause, the licensee agreed to submit a portion of the second RESL sample to the contractor for further i analyses. This will be reviewed in a subsequent inspectio (0 pen) Open Item (50-456/86037-05; 50-457/86029-05): High Radiation Sampling System (HRSS) to be operational for supplying routine primary coolant samples by FLOL. This system was completed and tested during the Intergrated Hot Functional test However,

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subsequent modifications were made and operability could not be demonstrated because of lack of water in the system. This system

- c.an not supply samples until the reactor coolant system (RCS) is '

pressurized. The licensee stated that prior to this stage, the RCS will be sampled from alternative points, such as in the RHR syste This item will remain open pending demonstration of the operability of the alternative sampling points and of the HRSS prior to criticalit . Organization and Staffing The inspectors reviewed the management controls and organization of the Radiation-Chemistry Department and found that the organization remains unchanged since the previous inspections.1,2 The chemistry group lost ,

a chemist who is being replaced by a chemistry consultant with four years of chemistry experience at Byron. He will start the first part of October and remain until ccmmercial operation of Unit 2. The licensee's Corporate Technical Center will also supply staff members with special ex)ertise, such as ability to work with the AAIS gamma spectrometers and otler counting equipment prior to FLOL. Eleven new RCTs have been added to the Radiation-Chemistry Department within the last two month No violations or deviations were identifie . Training and Qualifications The inspectors reviewed the progress of training of the RCTs and their qualifications to perform the necessary chemistry /radicchemistry operations in the laboratory as discussed in previous inspections 3,4 and also in Section 2f of this repor Twenty-eight RCTs have recently completed their qualification cards.

l 1 Inspection Reports No. (50-456/85017; 50-457/86015)

2 Inspection Reports No. (50-456/86037; 50-457/86029) ,

3 Inspection Reports No. (50-456/86017; 50-457/86015)

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4 Inspection Reports No. (50-456/86037; 50-457/86029)

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.3 A licensee representative stated that 14 RCTs have met the ANSI /ANS

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3.1-1978 requirements and that at least one ASNI qualified RCT and an ANSI qualified foreman will be on each shift. This complement should be '

, sufficierit to meet the needs for having qualified personnel on all shifts during FLOL and operation. The remaining RCTs are working towards >

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completing their.OJT~ work and gaining the required experience toward !

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becoming ANSI qualified. .The progress of their training to become ANSI qualified will be reviewed in future inspection. This item is

.- not required for FLOL (0 pen Item 50-456/86051-01; 50-457/86039-01).

During review of selected qualification cards, the inspectors noted that certain~ tasks for collecting samples from different plant systems, such as from'the High Radiation Sampling System (HRSS), were waived,

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since it was impossible to complete these tasks with no water in the systems. This item was discussed with licensee representatives prior to and during the exit meeting. The licensee agreed to inform the inspectors when these systems would be available for sampling and training and when the RCTs would be ready to d nonstrate-their capabilities to properly handle and collect simulated radioactive samples and to perform the required analyses, so that their operations can be observed by the

. inspectors. -This item is to be examined in a future inspection prior

to criticalit (0 pen Item 50-456/86051-02; 50-457/86039-02) ,

No violations or deviations were identifie . Radiological Environmental Monitoring Program (REMP)

The inspector, in addition to examining the new air samplers (Section 2C),

examined two other air sanplers. The licensee has been collecting 1 atmospheric iodine by charcoal absorbers since May 1986. All the samplers-observed were operable and no leakage of the filter trains was observe Each air sampler had a calibration card stating that it had been

. calibrated using a Rotameter flowmeter on a prescribed monthly frequenc The thermoluminescent dosimeters were also placed properly. The entire REMP is fully operationa No violations or deviations were identifie . Water Chemistry Control Program

No changes in the licensee's water chemistry control program as I described in a previous inspection 5 have occurred. The licensee has procedures in place, such as BwCP PD-4 "Braidwood Station Secondary Water Chemistry Control," Revision 0, approved by the

.Braidwood On-Site Review Board (OSRB) on February 22, 1985, which meet-the requirements for secondary water chemistry in the licensee's proposed Technical Specification 6.8. Inspection Reports No. (50-456/86017; 50-457/86015).

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This program was.first implemented during the integrated hot functional tests. The full implementation of the licensee's secondary water chemistry control program will be examined in subsequent inspections when the plant becomes operationa '

No' violations or deviations were identifie . Implementation of' the Chemistry and Radiochemistry Program 4 The inspectors reviewed the progress in implementing the primary and - '

secondary chemistry programs since the previous inspections.6 The ,

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licensee has begun to do some radiochemistry in the laboratory. This '

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entails tritium analysis from a liquid spiked sample provided to the licensee by the NRC Reference Laboratory. The RCTs are gaining some experience in handling and working with radioactive samples. Much more, radiochemistry work will be~done as the plant progresses toward operatio , ,

The inspector observed several'RCTs collect samples from the boric acid storage tank (BAST) and the batch tank and determine boron using

, an automatic titrator. The RCTs appeared knowledgeable and.followed the correct procedures for this analysis. The RCTs also did performance

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i checks of the procedure through analysis of different standard sample ; No problems were noted during collection and analysis of the samples or on the data log sheets for-the boron analysi The inspectors also observed a chemist demonstrate the operation of the new Becunan Plasma Spectrometer for boron and other metal analyses.

Eventually the RCT's will be using this instrument for routine analyses after training is completed. This training is not required by FLOL.

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The RCTs have already received training on the Perkin Elmer Model 5000 Atomic Absorption Spectrophotometer which is used for the same purpose.

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The counting room equipment has rema!ned essentially unchanged since the previous inspection.7 Regular performance checks have been t instituted for all the counters, except for the two uncalibrated Ge

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detectors (scheduled for calibration in October 1986). The results of.these checks are maintained on log sheets transferred to a personal computer data set and plotted monthly on control charts. The charts

can be viewed on the computer screen.or printed at anytime. This area is progressing, Dut, as it has only recently been instituted, the data

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are limited. Progress in this area will continue to be followed under Open Items No. (50-456/86051-03; 50-457/86039-03).

i Im)lementation of the QA/QC Program in the Chemistry and Radiochemistry La) oratories

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• The inspectors reviewed the progress of the chemistry and radiochemistry-QA/QC program described in the previous report.s The nonradiological

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,~ QA/QC program includes instrumental performance checks on the analyses of

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-chloride and fluoride (specific ion probes), high level boron (automatic i- titrator), and silica and hydrazine (spectrophotometric). The results of the performance standards are tabulated and graphed, along with the

control limit The charts have been very useful in helping to resolve various. problem The variabilities of the fluoride and. chloride results

improved since the last report, but they still appear-to be high, t

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, ., . especially those~for chloride. The fluoride results were biased low at about 90% 'of the known standard valu Part of the difficulties with  :

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graduated. cylinders, for the standardization of the specific ion electrodes

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at procedural steps where accurate volumes should be known, as in

, Procedures BwCP 120-1,.." Fluoride Determination," Revision 3, September 11, 1986, and BwCP 123-2, " Low-Level Chloride Determination (Orion 901),"

Revi.sion 2, September 11, 1986. The licensee representative agreed to ,

look into this concern. Additional uncertainties may be introduced by l

not drying the reagent prior to preparation of the chloride standard

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(BwCP 800-35, "100 ppm Chloride Standard Preparation," Revision 0, September 23, 1985), unlike that required by the standard procedure, ASTM D 512-81, " Chloride Ion in Wate .

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Analytical control limits have been established at 20% fractional

variation for the various analyses. For high level boron the limits were

set at 3% of the standard value. However, most of the performance check-values for boron were within 1% of the standar ~

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The licensee has continued the performance check program with the RCTs 1 with unknowns for the analyses of boron, low-level chloride, and low-level  !

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fluoride. Those for silica and hydrazine have been dropped so that the i licensee can concentrate on the development of analyses required by

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Technical Specifications. Acceptance limits have been established at-4 3% for the boron analysis and 20% for the chloride and fluoride analyses, j respectively. Only six additional RCTs have been tested under this .

t L, program since the previous inspection.8 The baron results were generally within the control limits; the fluoride tests required one retest, but those for chloride were highly variable and required five retests for the t six RCT Subsequent data and the licensee's efforts to improve these results will be reviewed during a subsequent inspection under the open

' item discussed in Section 2 The station also participates in the corporate interlaboratory comparison program'for non-radiological analyses in a primary reactor coolant and

, secondary system matrice The first intercomparison showed wide

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deviation from the known values in the sample. The results from the e

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second comparison have not been compared to those from the other plants, but the precision within the laboratory appears to have been improved, along with the comparisons of the mean values with those of the

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unknowns. This will be reviewed in a subsequent inspection under the open item discussed in Section 2f.

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In line with the previous commitment, the licensee has participated in a

vendor's radiological cross check program. The comparisons for eight i nuclides in a 14-ml geometry mixed gamma source were agreements (by NRC 91hjd

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4 -criteria; Attachment 1 of this Report) with a mean ratio (licensee value/ vendor value) of 1.02 for six nuclides, but substantially lower i

ratios were obtained for Ce-141 and Ce-144, 0.89 and 0.83 respectively.

These differences are probably due to the method of calibration of the

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licensee's Ge detectors with the AAIS. This is a logarithmic straight-line calibration which is not adjusted for.the decrease in efficiencies at lower

, energie These latter two euclides have the lowest energy gamma rays.in this group with peaks in the region in which the actual efficiencies are

below those derived by the AAIS. The licensee representative noted that ,

a more realistic efficiency curve has recently become available, but it has not' yet been implemented. Measurements of I-131 in a spiked charcoal

, cartridge were also in agreement with a ratio of 1.15. The H-3 ratio of .75 was a borderline agreement. Further, results of this analysis done l by.several RCTs showed a wide variability, which, if averaged, would have

lead to a disagreement. Overall this initial intercomparison appears to be adequate. The intercomparisons will be reviewed in a subsequent inspection (0 pen Item 50-456/86051-04; 50-457/86039-04).

The QC program in the laboratory has improved since the previous inspection. Licensee management appears to be very aware and supportive

of.a good QA/QC program, as represented in the chemistry procedures and program description. The rotation of the RCTs between chemistry and radiation protection groups still poses a problem with quality control, as evidenced by the high variabilities of RCT results in the chloride and

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tritium analyses. Otherwise, the staff appears to have good support from

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management in implementing their programs and in obtaining help from the corporate Technical Support-Center. The'QA/QC program will be-reviewed-in subsequent inspections under the previous Open Item in Section 2 No violations or deviations were identifie . Plant Systems Affecting Water Quality l The inspectors reviewed the status of plant systems affecting water i chemistry. During a tour of the plant, the inspectors observed the various components of the makeup demineralizer.(MUD) water treatment system and the condensate polishers. The MUD system was operational, as were the in-line monitors for conductivity, silica, sodium, and p Each monitor had been. calibrate Grab samples are also taken to measure pH, conductivity (flow-cell), dissolved and total solids, and chlorid The licensee has been able to maintain high quality makeup water to be

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within the administrative limits of those described in BwCP PD-5A1,

" Reactor Makeup Water Chemistry Specifications," Revision 2, approved by Bw0SR on February 18, 198 The inspectors also observed the five condensate polishers (CP) which were not operable since the secondary system has no water. These polishers were used during the IHF tests. The operation of the CP during the tests followed Procedure BwCP PD-5, "Braidwood Station Chemistry Hot Functional Test Programs," Revision 2, approved by Bw0SR on February 18,

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1986. The operation of the CP will be observed in subsequent inspections

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when the system is operable. Sampling of the system will be done at the Secondary Sampling Panel to verify water chemistry quality of the C Key chemical parameters will be plotted to trend operation of various components to assure that high water quality is maintaine No violations or deviations were identifie *

Licensee Internal Audits and Surveillances

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The inspectors reviewed a chemistry audit (QAA 20-86-02) and sev'eral

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surveillances (QAS 20-86-045, 047, 048, 062, 079, 098, and 115) concerning chemistry program and activities performed during 1986 to date oy the QA

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Department. All findings have been resolved and closed in a timely manner.

. One of the audit items involved reviewing the proficiency testing of the RCT This item, however, was waived and not actually performed since the auditor believed that it was not applicable at the time of the audit (January 1986) because the RCTs were still undergoing training. Because of the importance of maintaining RCT proficiency the inspectors expressed their concern that this item was waived. They discussed it with licensee representatives and at the exit interview. The licensee representative agreed that this item will be reviewed in subsequent audits. The inspectors will review this in subsequent inspections. (0 pen Item No. 50-456/86051-05; 50-457/86039-05).

No violations or deviations were identifie . Open Items Open Items are matters that have been discussed with the licensee which will be reviewed further by the inspectors, and which involve some action by the NRC or licensee or both. Open Items are discussed in Sections 2, 4, 7, 8 and 1 . Exit Interview The inspectors reviewed the scope and findings of the inspection with licensee representatives on September 23, 198 All FLOL o now been close The licensee acknowledged the inspectors' pen and concerns items have agreed that prior to criticality to:

• Assure that the HRSS and alternate sampling points are operational for routine collection of reactor coolant samples,

• Complete analysis of the second Sr-89/Sr-90 sample for the confirmatory measurements program, and

• Assure that the secondary sample panel is functional for collecting secondary samples and that the in-line monitors are operabl Additional telephone conversations were held with licensee representatives at the corporate office on September 24, 1986 concerning the REMP air samplers and at the plant on September 29, 1986 concerning chemistry analyse .

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During the interview, the inspectors discussed the likely informational content of the inspection report with regard to documents or processes reviewed by the inspectors during the inspection. Licensee representatives did not consider the proposed content as proprietar ~

Attachments: Table 1 Confirmatory Measurements Program Criteria For Comparing

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Analytical Measurements

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TABLE 1

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U S NUCLEAR REGULATORY COMMISSION

OFFICE OF INSPECTION AND ENFORCEMENT CONFIRMATORY MEASUREMENTS PROGRAM FACILITY: BRAIDWOOD FOR-THE 3 QUARTER OF 1986-NRC= -LICENSEE LICENSEE:NRC-SAMPLE ISOTOPE RESULT ERROR RESULT ERROR RATIO RES T

'L SPIKED H-3(LSC) 9. 0E-05 2.0E-06 8.8E-05 0.0E-01 9.8E-01 4.5E 01 A Vini CS-137_ 8.2E-05 2.5E-06 8.4E-05 0.0E-01 1.0E 00 3.3E 01 A Countar 22 CO-60 7.3E-05 1.4E-06 7.5E-05 0.0E-01 1.0E 00 5.2E 01 A

'MN-54 5.0E-05 1.0E-06 5.2E-05 0.0E-01 1.0E 00 5.1E 01 A-L SPIKE 1 CS-137 8.2E-05 2.5E-06 8.7E-05 0.0E-01 1.1E 00 3.3E 01 A

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1 L Bottle CO-60(E) 7. 3E-05 . 1 . 4 E - O'6 8.9E-05 0.0E-01 1.2E 00 5.2E 01 A MN-54 '5.0E-05 1.0E-06 4.8E-05 0.0E-01 9.5E-01 5.1E-01 A L SPIKE 2 CS-137 8.2E-05 2.5E-06 8.3E-05 0.0E-01 1.0E 00 3.3E 01 A Vial.22 CO-60- 7.3E-05 1.4E-06 7.0E-05- 0.0E-01 9.6E-01 5.2E 01 A-Shelf 3 MN-54 5.0E-05 1.0E-06 5.8E-05 0.0E-01 1.1E 00 5.'1E 01 A-L~ SPIKE 3 CS-137 8.2E-05 2.5E-06 8.1E-05 .0.0E-01 9.9E-01 3.3E 01 A

- thrinelli CO-60 7.3E-05 1.4E-06 7.2E-05 0.0E-01 9.9E-01 5.2E 01 A

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450 n1 MN-534 5.0E-05 1.0E-06 5.4E-05 0.0E-01 1.1E 00 5.1E 01 A L SPIKE 4 SR-89 1.1E-04 3.0E-06 6.2E-05 6.2E-06 5.5E-01 3.8E 01 D contractor SR-90 1.1E-05 4.0E-07 7.1E-06 2.0E-07 6.6E-01 2.7E 01 D

, FE-55 6.7E-05 1.3E-06 6.6E-05 1.1E-06 9.9E-01 5.1E 01 A T TEST RESULTS

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• = CRITERIA RELAXED NANO COMPARISON

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ATTACHMENT 1 CRITERIA FOR COMPARING ANALYTICAL MEASUREMENTS

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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 sigma 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 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

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Agreement

<4 0.4 - .5 - .6 - 1.66 16 - 50 0.75 - 1.33 51 - 200 0.80 - 1.25 200 - 0.85 - 1.18 l

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Some discrepancies may result from the use of different equipment, techniques, l and for some specific nuclides. These may be factored into the acceptance criteria and identified on the data sheet.

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