IR 05000456/1990022
| ML20024F883 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 12/18/1990 |
| From: | Holtzman R, Schumacher M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20024F873 | List: |
| References | |
| 50-456-90-22, 50-457-90-24, NUDOCS 9012270090 | |
| Download: ML20024F883 (14) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION III
Report Nos. 50-456/90022(CRSS); 50-457/90024(DRSS)
Docket Nos. 50-456; 50-457 License Nos. NPF-72; NPF-77 Licensee: Commonwealth Edison Company Opus West III 1400 Opus Place Downers Grove, IL 60515 Facility Name: Braidwood Nuclear Power Station, Units 1 and 2 Inspection At: Braidwood Site, Braceville, JL Inspection Conducted:
Novenb9r26-December 3,1990(On-site)
December 10, 1990 (Telephone. discussions)
R.B.?Mbnos Inspector:
R. B. Holtynan
_/ 2//8'/90 Da te k,C.Mkyro+. A l%$chnd Approved By:
M. C. Sdhumac 'er, Chief -
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/'b / l'ho Radiological Controls and Da'te '
Chemistry Section Inspection Sununary
- _ Inspection on November 26-December 3, 1990 (Report Nos. 50-456/90022(DRSS);
50-457/90024(DR55))_
_ Routine announced inspection of the chemistr Areas Inspected:
including (1) procedures, organization, and training (IP 84750)y program,; (2) primary
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and secondary systems water quality control programs (IP 84750);(3) quality assurance / quality control program in the laboratory (IP 84750);(4)
nonradiolgical confirmatory measurements (IP 84750); and (5) the Radiological Environmental Monitoring Program (REMP)(IP 84750),
Results:
The steam generator (S/G) blowdown had low levels of chloride and sulfate which were well within the EPRI guidelines. The still decreasing levels of these species indicated that the reactor systems were still being cleaned up. The process instrumentation. includes an operational in-line ion chromatographic system on S/G blowdown and another on the secondary system
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= sampling panel.-- The in-line instrumentation is computerized.
The nonradiological confirmatory measurements results were good with 30 of 33 i
l-comparisons being in agreement. The QA/QC program has been improved and it and the chemistry sample date are in a computerized data base.
The sampling and measurements activ.ities of the REMP :nainly conformed to the NRC and Technical Specification requiremes.ts. However, the tritium concentration in a river surface water semple greater than the reporting level, was not reported to the Commisssion wiu.in the required 30-day time period.
One violation was l
identified.
'9012'270090 901219 PDR ADOCK 05000456
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DETAILS
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1.
Pgrsons_ Contacted fD. E. O'Brien, Technical Superintendent, Bwd
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)J.R. Petro, Chemistry Supervisor, Bwd K. G. Bartes, ONS Administrator, CECO 1. Golden, Environmental and Special Projects Supervisor, Ceco J
I. A. Boyle, GSEP Coordinator, Bwd L
3. Thacker, Radiation Protection, Bwd R
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3. Carroll, Regulatory Assurance, Bwd E
R. Kyrouac, NQP Superintendent, CECO 1'2. Vickery, Lead Chemist, Bwd G
R. Supple.. Chemist Bwd
.L P. Lau, HPES Coordinator, Regulatory Assurance, Bwd M. Sears, In Service Inspection Group Leader, Bwd J. Bollini, Chemistry Foreman, Bwd 2. McInerney, Engineering Assistant, Bwd M
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R. James, Engineering Assistant, Dwd
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IR. Kopriv6, Resident Inspector, NRC The inspector also interviewed other licensee personnel in various departments in the course of the inspection.
f*'TelephonediscussionsheldonDecember Present at the Exit Interview on December 3, 1990.
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10, 1990.
2.-
Licensee Action on Previous Inspection Findings (IP 84750)
a.
.(Closed) Open Item Nos. (50-456/88026-02; 50-457/88026-02):
Licensee to provide a report on the effects of the secondary system chemistry excursion on the steam generators. The-licensee had previously completed the eddy-current examin6 tion of the S/G tubes in Unit 1.3 and repor ted the absence of hideout return attributed to this excursion.
The inspector reviewed a preliminary report (Steam Generator' Frimary Services, March 27-April 8,1990) on a recently j
completed 100% eddy-current test on the Unit 2 S/G tubes.
Two-damaged tubes in Generator C were plugged.
The licensee attributed the wear on-these tubes to contact with entivibration bars (AVB) and nor.e to the chemistry excursion. The testing is completed arid a final report is due :in April 1991.
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b.
(Closed) Violation-(50-456/89024-01;-50-457/89024-01): The licensee failed to include the results of analyses of all radiological environmental radiation measurements and samples in the-Annual Radiological Environmental Program Reports (REMP)-for 1987 and 1988, contrary to Technical Specification 6.9.1.6.
The licensee corrected these deficiencies by adding the results of the analyses to these and the 1989 reports.
The corporate-procedure controlling the issuance I
Region III Inspection Report Nos. (50-456/90005;50-457/90005)
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of this report Ep-ADMIN-7, " Review and distribution of NRC submittals," Revision 2, March 19, 1990, was modified to require that the report be approved by Braidwood arior to issue and that all of the environmental monitor results >e included in the report.
c.
(Closed) Open Item Nos. (50-456/90005-01;50-457/90005-01): The licensee analyzed a split sample for gross beta. H-3, Fe-55, Sr-89 and Sr-90 and submitted the results to Region 111 for comparison with those from the NRC Reference Laboratory, the Radiological Environmental Sciences Leoboratory (RESL) in Idaho.
The results are presented in Table 1 with the comparison criteria in Attachment 1.
In five comparisons the licensee has two agreements and one disageement; two of the results were not compared due to very low activities, below the required LLDs, in the sample.
The low value for the gross beta measurement appears to be due to the laboratory's loss of the sample prepared immediately af ter collection. and the necessity of preparing a new one several weeks later.
The licensee agreed analyze the Sr nuclides and the gross' beta on a spiked sample to be supplied by RESL.
This will be followed under new Open Item Nos.(50-456/90322-01;50-477/90024-01).
d.
(Closed) Licensee tracking item AIR #456-225-90-00300. The licensee implemented a plotting system of performance check results for the laboratory instrumentation QA/QC program. This program was developed and implemented using the computerized database system for laboratory data.
-3.-
ManagementControls,,0rganization,andTraining(IP84750j The management structure of the Chemistry Dgpartment was modified somewhat since the previous inspection in this area, and the organization appears to have stabilized. The Department is headed by the Chemistry Supervisor, who reports to the Technical Superintendent. The Lead Chemist, QC Chemist, Waste Products Coordinator, and two Laboratory Foremen report to the Supervisor; three chemists / chemical engineers and five Chemistry Engineering Assistants report to the Lead Chemist. While the latter is new to the position, he is an experienced unit chemist at this plant and elsewhere.
The QC Chemist is a newly implemented position.
Fourteen of the 18 Chemistry Technicians (CT) are "A" grade and qualified under ANSI N18.1, 1971.
Four other "B" grade cts have recently started. training.
The academic training;of the cts has improved;'most of the older cts are taking college courses and the "B" grade ones have associates degrees, or equivalent. Currently, the cts are scheduled from 0500 - 2400 hrs.during the week and from 0700 - 1900 hrs on weekends.
No violations or deviations were identified.
14.
Water Chemistry Control Program (IP 84750)
The inspector reviewed a' pects of the water chemistry control program.
s In-line process monitors have been upgraded; they provide data from the secondary water systems, including condensate, feedwater and main steam.
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The various parameters are tracked by strip chart recorders on the panels and Dataloggers loc 6ted in the laboratory area.
The data are sampled, processed and archived on a computer, which can then be easily retrieved and processed, as desired.
This system has improved data processing and expanded storage facilities.
The plant has an in-line Dionex lon Chromatograph on the steam generator blowdown (S/G BD) for continuous monitoring of chemistry parameters, and a similar system on the secondary system sampling panel.
The licensee is reviewing implementation of the latter system because the extremely low analyte concentrations make analysis difficult.
An extensive set of trend charts for water quality is mairitained by the laboratory with daily data.
In response to previous NRC concerns, the previously.glemented trend charts that cover longer-term operations than licensee im The term is based mainly on the current fuel cycle. A review of selected data showed that plant water quality appears to be good and generally improving.
The plant presently operates the condensate polishers only to shorten the cleanup time, mainly at startup.
This type of operation appears not to affect water quality, and may, overall, actually improve it.
Sulfate concentrations have decreased, and the probability of chemistry excursions due to polisher-bed breakthrough is lessened.
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The water quality control programs appear to be satisfactory and well run.
No violations or deviations were identified.
5.
Implementation of the Chemistry program (Ip 84750)
The inspector reviewed the chemistry programs, including physical facilities and laboratory operations. Houskeeping was good and bench space was adequate for the analyses performed.
The laboratories were well equipped. A PC-controlled Perkin-Elmer Model 5100 Zeeman Effect Atomic Absorption Spectrophotometer (AAS) is now operational and has replaced the P-E Model 5000-flame and furnace AAS.
The chemistry and QC results are maintained on a computerized database, it produces a hardcopy record periodically as a permanent record.
The licensee is planning to gradually change over to another, more versatile database, which has recently been installed as part of the Corporate-wide database.
Overall, the laboratory appeared.to be adequate for the proper operation of the plant and to be operating satisfactorily.
No violations or deviations were identified.
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6.
Lonradiolooicol Confirmatory Measurements (IP 84750)
The inspector submitted chemistry samples to the licensee for analysis as part of a program to evaluate the laboratory's capabilities to monitor nonradiological chemistry parameters in various plant systems with respect to various Technical Specification and other regulatory and administrative requirements. These samples had been prepared and standardized for the NRC by the Safety and Environmental Protection Division of Brookhaven National Laboratory (BNL). The samples were analyzed by the licensee using routine methods and equipment.
Licensee personnel made one dilution of each sample as necessary to bring the concentrations within the ranges normally analyzed by the laboratory, and run in triplicate'in a manner similar to that of routine samples.
The results are presented in Table 2 and the criteria for agreement at the end of the Table. These criteria are derived from the BNL results of the present samples and the relative standard deviations (RSD) derived from the results of the 1986 interlaboratory comparisons from the various plants in the study (Table 2.1, NUREG/CR-5422). The acceptance criteria were that the licensee's value should be within +2 SD of the BNL value for agreement and between 2 and 3 SD for a "condTtional agreement".
The licensee determined the concentrations of 11 analytes at three concentrations each. Thirty of_ the 33: initial comparisons were agreements. The disagreements were in the low-level silica and the low-and high-level ammonia.
The silica was high, indicating high levels in the dilution water, an ef fect apparently not compensated by the blank.
The ammonia analyses as a group indicate a contamination or a calibration problem, since the biases appear to decrease with increasing concentra-tion.
Licensee and inspector reviews of these problems have not yet resolved them. They will be reviewed in subsequent routine inspections Overall, the results of the analyses were good.
No violations or: deviations were identified.
7.-
Implementation'of the QA/QC Program in the Laboratory (IP 84750)
The' inspector reviewed the. chemistry laboratory quality assurance program as specified by Nuclear Stations Chemistry Quality Control Program, Revision 8. July 16,.1990 (N0 Directive N00-CY.7),.the licensee maintains statistically-based control charts on which the mean values and +2 standard deviations (SD) are plotted from the computerized database.
Independent controls are in use and these data are used in preparing control charts. The inspector noted concerns that even with the computerized system, the control. limits on the charts were not calculated very frequently. This resulted in the limits not representing the data well. Licensee representatives agreed to determine these limits at more reasonable intervals (after the collection of about 100, or so points, depending on the frequency of analysis). Progress in this will be followed in subsequent routine chemistry inspections.
The licensee has a QA/QC program for in-line instrumentation based on corporate NOD directive NOD-CY.8," Nuclear Operations In-line Chemistry
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Instruments Quality Control Program," Revision 1, July 1,1988, in which the various instruments are checked against standards or laboratory
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analyses biweekly.
Control limits are based on the suggested INPO values
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of chemistry good practices.
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-No violations or deviations were identified.
8.
Radiological Environmental Monitoring Program (REMP) (IP 84750)
The inspector reviewed the REMP, including the 1989 Annual Environmental Report and the most recently available 1990 monthly environmental report which contains the cumulative individual measurements for 1990.
These reports appeared to comply with the Technical Specification requirements for the REMP. All of the required samples were collected and analyzed, except as noted in the report, and a perusal of the results showed them to be reasonable and acceptable.
A water sampling station was added in January 1990 at the new Wilmington public water intake facility, which is about four miles downstream from the plant circulating water blowdown (80) discharge point on the Kankakee River. The inspector examined the environmental air sampling stations around the plant and checked the nine systems for operability, and leakage. All appeared to be running and the six systems tested had good
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vacuum and flowrates and they had calibration tags.
However, the licensee appeared not to comply with the reporting require-ments of T/S 3/4.12.1.b that a special report be sent to the Conunission
.when the concentration in a quarterly composite sample attributable to plant effluents exceeds the reporting levels Itsted in T/S Table 3.12-2.
Thus, in the third quarter of 1989, the Annual REMP Report (page 165)
showed a tritium concentration in a quarterly upstream surface water sample of the Kankakee River of 38,670 pCi/ liter versus a reporting level is 20,000 pCi/ liter for a drinking water pathway, _or 30,000
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pCi/ liter otherwise. The downstream sample showed an activity of
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600 pCi/ liter.
These. samples were quarterly composites from monthly
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composites of weekly collections. Analyses made on the still-available
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upstream monthly composites showed values of 100,000, 250, and < 200 pCi/ liter in July, August and-September, respectively.
They were listed in the Annual Report and the elevated' levels were noted in the discussion of.the data.
The failure to follow this Technical Specification is a violation of NRC requirements (Violation 50-456/90022-02;50-457/90024-02).
The inspector's review of some typical radioactive release data indicated L that the reported levels are reasonable and that the-H,3 concentrations in the effluents were within the required T/S limits at the outfall to the' river.- Several safety features are built into the system to monitor-
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the activity and to prevent excessive radioactivity levels in the BD,
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including a composite sampler in the BD stream about 200 feet above the outfall, and two automatically-operated isolation valves, one activated by a high-radiation level monitor and the other by low BD flow.
The general procedure for the releases consists of Chemistry determining the radioactivity levels in the liquid radwaste tank, after which the contents are released into the circulating water BD stream to the river
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at a-rate calculated to maintain the radioactivity concentrations below the limits of 10 CFR Part 20, Appendix B, Table II, Column 2.
The release should be well mixed with the BD by the time it travels five miles to the outfall to the river. The inspector and licensee representatives With a tank concentration of 1x10.MC1/mi (ypic;l release parameters.pCi/ liter), a release estimated the expected H-3 levels based on t 1x10 rate of 400 gal / min and a BD flowrate of 11,500 gal / min, the
concentration would peak at about 3.5x10 pCi/ liter, well below the T/S
limit of 3x10 pCi/ liter.
If two tanks are released daily, each taking an hour, the mean daily levels expected in the compositor would then be about 30,000 pCi/ liter. This estimate is consistent with the results reviewed by the inspector, which are fairly constant.
No extreme values were noted in either the tank or in the compositor analyses.
Given the above estimates, it appears that under certain circumstances, the BD plume in the river could reach the upstream sampling point with high concentrations of tritium, especially at time of low river flow, since this sampling point is only about 200 yards above the outfall and it is near the lake makeup water intake. Moreover,theconcegtrations are very time sensitive, varying-from / 200 to more than 5x10 pCi/ liter; the high levels at certain times indicate that the collector sampled near the time of a high concentration level. The presence of H-3 in both the upstream and downstream samples was not unique; they were reported at least once per year from 1987, although not at levels requiring special reports.
The inspector stated his concerns that the licensee did not more thoroughly investigate and document the circumstance of these releases when first discovered to determine possible safety significance.
One violation was identified.
9.
Audits and Appraisals (IP 84750_);
The inspector reviewed the most recent audits of the REMP and chemistry laboratory by the corporate Nuclear Quality Programs (NQP). The Environmental Protection Audit No. 20-90-16', July 20, 1990, reviewed radioactive effluents, aspects of the REMP, including the ODCM, and comparison of the annual REMP report against the T/S requirements.
The review was detailed, although it missed the above noncompliance.
The NQP Chemistry audit No. 20-90-14, October 29,1990, had two Findings relating to the requirements of the Corporate Quality Assurance Manual:
-a.
The calibration certificates of two sets of Class "S" analytical balance weights that make them NBS-traceable, appeared to-have had the last digit of certification dates altered from "1985" to "1986."
b.
One set of weights had no identification, such as serial numbers, that could-be associated with the respective certificate and were, thus not considered to be NBS-traceable.
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These weights were used as monthly performance checks on the laboratory balances and not considered to be safety related.
Independently, a vendor calibrated the balances with his own NBS-traceable weights semiannually.
After these findings, the licensee checked the balances with NBS-traceable weights from another plant, and had the balances recalibrated by the vendor.
The licensee made an extensive investigation of the faulty records,.
including interviews of the persons who used the weights and certificates, and verified the actual dates from vendor ano other records. The source of the problem or motivation for the changes was not found, other than that the Corporate QA manual requires recertification every five years, which with the original 1985 date on. the certificates would fall in 1990.
Licensee personnel involved were apprised of the seriousness of falsification of records, including informing them of NRC Information Notice 89-18, Supplement 1, " Criminal prosecution of crimes committed by suppliers of Nuclear Products or Services." The content of the Notice was posted on the plant bulletin boards, training has been presented to management groups, and is planned for the other employees.
Both sets of weights were taken out of service and new ones ordered.
in the future the licensee is committed to keep such certificates in the QA files. The NQP is starting an extensive series of audits to look for-such faulty records. These findings are violations of NRC requirements, but are not cited under the provisions of NRC Enforcement Policy V.G.1 (53 FR 40019(1988)).- The completion of these corrective actions will be followed in subsequent routine inspection in this area under Open Item Nos. 50-456/90022-03; 50-457/90024-03.
The inspector's review of this matter supported the licensee's conclusion concerning.the improbability of resolving the apparent falsification issue.
The NQP Department has. implemented a performance-based auditing system in which the audit questions are explained in great detail to give the auditor a better idea about what to look for.
More emphasis will be placed on observation of performance, and less on documentation.
No violations or deviations were identified.
9.
Open Items Open items are matters which have-been discussed with the licensee,.which will be reviewed further by the inspector, and which involve some action on the part of the NRC or licensee, or both. Two open items were disclosed during the inspection in Sections 2 and 8.
10.
Exit Interview The scope and findings of the inspection were reviewed with licensee representatives (Section 1) at the conclusion of the inspection on December 3, 1990. The inspector discussed the Open Items in Section 2 and the improvements in the quality assurance / quality control program, including improvements made in the chemistry parameter trend charts. The computerized plotting of the QC charts was completed, but some inspector concerns on their maintenance were noted. The chemistry audit tnt found
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the altered records was discussed.
Licensee representat' 's noted the extensive investigation that was made and the corrective 3sures instituted. The possible violation in the REMP due to not submitting a special report was discussed along with possible corrective actions.
Prior to this interview a detailed discussion was held with the corporate supervisor of the REMP.
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 or processes as proprietary.
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Attachments:
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Table 1, Radiological Confirmatory Measurements Program, Split Sample Comparison,. lst Quarter 1990 2.
Attachment 1, Criteria for Comprison of Radiological Results 2.
Table 2, Nonradiological Confirmatory Measurements
' Results, November 26-December 3,1990
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TABLE 1 U.S. NUCLEAR REGULATORY COMMISSION
REGION III
CONFIRMA10RY MEASUREMENTS PROGRAM SPLIT SAMPLE FACILITY: Braidwood 1st QUARTER 1990 SAMPLE NUCLIDE NRC VAL. NRC ERR.
LIC. VAL.
LIC. ERR.
RATIO RESOL. RESULT-RADWASTE H-3 3.57E-02 5.00E-04 3.48E-02 1.70E-03 0.97 71.4 A
SPLIT FE-55 1.26E-05 1.00E-07 1.25E-05 6.20E-07 0.99 126.0 A
SR-89 0'.00E+00 7.00E-09 <3E-9 0.0 N
SR-90 2.00E-09 3.00E-09 4.9E 10
- 0. 7 N
Gross B 8.20E-06 4.00E-07 5.51E-05 5.50E-06 6.72 20.5
TEST RESULTS:
A= AGREEMENT.
D= DISAGREEMENT
- = CRITERIA RELAXED N=N0 COMPARISON 06-Dec-90 c.
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TABLE 2 Nonradiological Confirmatory Measurements Results
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Braidwood Nuclear Power Station November 26 - December 3, 1990
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Analyte Method Conen ggggg Acceptance Ranges Result 1 2RSD 1~3RSD EP5 Fluoride A IC
1.071 0.875-1.125 0.813-1.187 A
B
1.038 0.875-1.125 0.813-1.187 A
C
1.047 0.875-1.125 0.813-1.187 A
0.973 0.933-1.067 0.900-1.100 A
B
0.987 0.917-1.081 0.879-1.121 A
C-
1.018 0.926-1.074 0.895-1.105 A
Sulfate.
A IC
1.021 0.895-1.105 0.842-1.158 A
t B
1.008 0.895-1.105 0.868-1.132 A
C
'1.027 0.900-1.100- 0.867-1.133 A
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Iron G
AA/FL
'800-0.915 0.904-1.096 0.854-1.146 A
H'
1500
'0.912 0.903-1.097 0.857-1.143 A
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2000.
0.966 0.903-1.097 0.855-1.145 A
Copper LG AA/FL
1.015- 0~.904-1.095 0.859-1.141 A
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'180 0.970 0.904-1.096 0.857-1.143 A
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It 250-0.9970 0.904-1.096-0.857-1.143 A-
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Sodium 4L AA/FU 2-0.941-0.863-1.137 0.784-1.216 A
K
'4 1.010 0.859-1.141 0.788-1.~212 A
L
0.978 0.862-1.138~ -0.789-1.211 A
t Lithium ~
J-AA/FL 500.
1.0481 0.950-1.050 - 0.925-1.075 A
K.
1300 1.038 0.950'1.050-0.925-1.075
.A
l L-1500-
-1.038 0.950-1.050' -0.-925-1.075 A
Ammonis-M IC 100 1.295 0.902-1.098 0.856-1.147
LN
~400 0.907 0.-902-1.098 0.856-1.147 A
600
'0.794 '0.902-1.098 0.856-1.147-
Hydrazine P Spec 110 1.004 0.922-l'.078-0.888-1.118 A
Q 400 0.981 0.922-1.078 0.888-1.118-A R-800 0.982 0.922-1.078 0.888-1.118 A
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TABLE 2 Nonradiological Confirmatory Neasurements Results Draidy. cod Nuclear Power Station
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November 26 - December 3, 1990
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Analyte Method Concn Ratio Acceptance Fanges Result 1 2RSD 1 3RSD ppb Fluoride A
3 1.071 0.875-1.125 0.813-1.187 A
B
1.038 0.875-1.125 0.813-1.187 A
C
1.047 0.875-1.125 0.813-1.187 A
0.973 0.933-1.067 0.900-1.100 A
B
0.987 0.917-1.081 0.879-1.121 A
C
1.018 0.926-1.074 0.895-1.105 A
Sulfate A
1.021 0.895-1.105 0.842-1.150 A
B
1.008 0.895-1.105 0.868-1.132 A
C
1.027 0.900-1.100 0.867-1.133 A
LIron G
AA/FL 800 0.915 0.904-1.096 0.854-1.146 A
H 1500 0.912 0.903-1.097 0.857-1.143 A
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2000 0.966 0.903-1.097 0.855-1.145 A
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l Copper L
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AA/FL
1.015 0.904-1.095 0.859-1.141 A
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H 180 0.970 0.904-1.096 0.857-1.143 A
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I 250 0.9970 0.904-1.096 0.857-1.143 A
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Sodium J
AA/FU
0.941 0.863-1.137 0.784-1.216 A
K
1.010 0.859-1.141 0.788-1.212 A
L'
8'
O.978 0.862-1.138 0.789-1.211 A
m Lithium. J AA/FL 500 1.048 0.950-1.050 0.925-1.075 A
K-1300 1.038 0.950-1.050 0.925-1.075 A
- L 1500 1.038 0.950-1.050 0.925-1.075 A
b,
'Annonia M-IC 100 1.295 0.902-1.098-0.856-1.147 D
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N-400 0.907 0.902-1.098 0.856-1.147 A
600 0.794 0.902-1.098 0.856-1.147 D
,
Hydrazine P - Spec 110 1.004 0.922-1.078 0.888-1.118 A
Q 400 0.981 0.922-1.078 0.888-1.118 A
R 800 0.982-0.922-1.078 0.888-1.118 A
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C Analyte Method Conen Ratio Acceptance Ranges Result 1 2RSD-1 3RSD
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Silica S
Spec
1.163 0.906-1.094 0.859-1.141 D
T
0.980 0.909-1.091 0.860-1.136 A
U
1.025 0.907-1.093 0.857-1.143 A
ppm Boron D
Titr 1000 0.994 0.979-1.021 0.968-1.032 A
E 3000 0.992 0.979-1.021 0.968-1.032 A
F 5000 0.981 0.979-1.021 0.968-1.032 A
1.
Methods:
Titr - Titration IC
- lon Chromatography Spec - Spectrophotometry AA/FL - Atomic absorption spectrophotometry (flame)
AA/FU - Atomic absorption spectrophotometry (furnace)
2.
Conc: Approximate concentration analyzed.
3.
Ratio of -Licensee mean value to NRC mean value.
4.
The SD in the fifth und sixth columns represents the coefficient cf variation obtained from averaging licensee data from the preceding cycle (Table 2.1 of NUREG/CR-5244). The licensee value is considered to be in agreement if it falls within the 4 2.SD range; a qualified agreement if it lies outside + 2 SD but within~+ 3 SD; and in disagreement if it is outside the 1 3 Su range.
5.
= Result:
A = Agreement: Licensee value is within 12 SDs of the NRC mean value.
A+. = Qualified agreement, licensee is between i 2 and 13 SDs of
.the NRC value.
D = Disagreement: licensee value is outside 1 3 SDs.
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ATTACHMFNT_1
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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 program.
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 acceptance.
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RESOLUTION RATIO = LICENSEE VALUE/NRC REFERENCE VALUE Agreement
<4 NO COMPARISON 4-
0.5 - 2.0 8-
0.6 - 1.66 h-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 cata sheet.
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