IR 05000456/1987046
| ML20235A326 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 01/04/1988 |
| From: | Holtzman R, Schumacher M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20235A313 | List: |
| References | |
| 50-456-87-46, 50-457-87-47, NUDOCS 8801120200 | |
| Download: ML20235A326 (7) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION III
l Reports No.
50-456/87046(DRSS); 50-457/87047(DRSS)
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Docket Nos.
50-456; 50-457 Licenses No. NPF-59; CPPR-133 Licensee:
Commonwealth Edison Company Post Office Box 767 Chicago, IL 60690 Facility Name:
Braidwood Nuclear Power Station, Units 1 and 2 Inspection At:
Braidwood Site, Braceville, Illinois Inspection Conducted:
December 7, 16, and 17, 1987 (On-site)
December 21, 1987 (Telephone discussion)
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Inspector:
R. B. Ho zman Oat 6
/.AYbt!'un Approved By:
. C. Schumacher, Chief YN Radiological Effluents and Date Chemistry Section Inspection Summary Inspection on December 7, 16,,and 17, 1987, and a Telephone Discussion on December 21, 1987 (Report Nos.' 50-456/87046(DRSS); 50-457/87047(DRSS))
Areas Inspected: Routine, announced inspection of:
(1) the chemistry program, including procedures, organization, and training; (2) primary and secondary systems water quality control programs; and (3) progress in the development of quality assurance / quality control program in the laboratory.
Results:
No violations or deviations were identified.
8801120200 880106 PDR ADOCK 05000456 G
PDR'
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DETAILS
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Persons Contacted D. E. O'Brien, Services Superintendent, Bwd 2L. E. Davis, Assistant Superintendent-Technical Services, Bwd 1R. E. Aker, Radiation-Chemistry Supervisor, Bwd 1 Takaki, Regulatory Assurance, Bwd 1J. B. Cronin, Station Chemist, Bwd 2R. C. Bedford, Regulatory Assurance, Bwd 2E. W. Carroll, Regulatory Assurance, Bwd W. E. Lloyd, Chemistry Engineering Assistant, Bwd J. Bates, Chemist, Bwd G. Vickery, Chemist, Bwd R. F. Rysner, Chemistry Engineering Assistant, Bwd 2R. H. James, Chemistry Engineering Assistant, Bwd J. McLenighan, RCT 2M. C. Schumacher, Section Chief, NRC 2T. M. Tongue, Senior Resident Inspector, NRC The inspectors also interviewed other licensee personnel in various departments in the course of the inspection.
1 Denotes those present at the plant exit interview on December 17, 1987.
2 Denotes telephone discussion held on December 21, 1987.
2.
Licensee Action on Previous Inspection Findings a.
(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 operation.
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, b.
(0 pen) Open Item (50-456/87008-01; 50-457/07007-01):
The licensee agreed to analyze a spiked sample from RESL for Fe-55 and report the results to Region III. The licensee presented the result of a sample containing Fe-55 that had been analyzed by a contractor (TMA, Eberline).
Table i shows the licensee's value to be 30% greater than that from the NRC reference laboratory (RESL).
This represents a disagreement based on the acceptance criteria in Attachment 1.
The exact cause of the disagreement was not ascertained.
The contractor had used an x-ray spectrometric technique. Incomplete chemical separation and insufficient resolution of the x-ray spectrometer may have contributed some Mn-54 x-rays to the Fe-55 peaks.
The licensee is checking on this and will have another sample analyzed, probably by another laboratory.
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c.
(Closed) Open Item 50-457/87035-02:
To demonstrate the operation and collection of routine RCS samples from.the Unit 2 HRSS and from alternative local sampling points, the HRSS was pressurized by the operation of RHR pumps, and a RCT demonstrated the drawing of water from the HRSS for a routine RCS sample.
Further, the inspector observed the local sampling points for the pump discharges on the A and B RHR trains and the availability of sample water from the B train, which was the one then operating.
These local points appear to be suitable for RCS sample collection in the absence of the HRSS sampling point.
d.
(0 pen) Open Item 50-455/87035-01:
For the Unit 2 secondary system sampling panel, the licensee will demonstrate the collection of samples and the calibrations of the in-line instruments prior to reaching-the 5% power level.
The sampling system has been completed and was used during the Integrated Hot Functional (IHF) tests.
The system has been cleaned up and appeared to be ready to operate.
However, calibrations can not be completed and operability can not be demonstrated until steam is available.
The licensee is to demonstrate these prior to reaching the 5% power level.
e.
(Closed) Open Item (50-456/87037-03; 50-457/87037-03):
The licensee will complete the laboratory QA/QC program for chemical analyses by November 1987.
The licensee has largely completed the program with final approval of the procedure revisions for the various analyses and reagent preparation.
Quality control charts have been prepared for most of the analytical procedures, including those for the the ion chromatography (IC), boron titrations, lithium by atomic absorption spectrophotometry (AAS), silica and hydrazine by UV/vis spectrometry, and ammonia by specific ion electrode.
Collection of control standard data has been started for the less frequently used analyses, such as metals by AAS and Direct Current Plasma spectrometry (DCP).
For other aspects of the QA program, the licensee implemented the use of dual standard reagent sets so that the control and calibration J
standards were from different sources or lots.
Multipoint calibrations were also instituted to improve the calibration accuracies on various instruments, including the AAS and IC with the fitting of linear regression curves by computer.
The calibrations appear to be linear over the concentration ranges of the analyses, as demonstrated by high correlation coefficients (>0.998).
The laboratory has acquired a new integrator that allows multipoint calibrations.
It will be installed on an IC system.
Control limits based on two standard deviations (s.d.) were calculated from initial sets of control standard data points and entered on the graphs.
Licensee representatives have not set criteria
for the recalculation of these limits, but were planning to do so on
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an approximately quarterly basis, or after the acquisition of about
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100-200 data points.
They are to be recalculated also after changes in the system, such as instrumental' repairs or reagent changes.
Schedules will be. implemented for the various analyses after more experience is acquired.
At present, the charts are hand drawn on graph paper, but the laboratory supervision is considering putting them on the computer, so that after the RCT enters the control data in the computer, the chart can be observed on the screen.
Various statistical parameters, such as standard deviations and control limits, can then be changed and observed.
These charts will be similar to, but not necessarily identical to, those in the radiological QA/QC program, as discussed in Section 3.
The laboratory supervisors.have used the control charts to solve some problems, such as the relatively large variations in control standards in the boron analysis which appeared to be caused by improper handling of the (potassium acid phthalate (KAP) used to standardize the sodium hydroxide. titrant.
The inspector suggested that by using a control chart on the titer of the NaOH, it may be shown that the titer of each batch is stabile over time and will provide support for a reduced frequency of standardization.
While this program is still under development, it is presently useful and appears to be progressing satisfactorily.
This item is considered closed and progress will be followed in the routine chemistry inspections.
3.
Implementation of the Radiochemistry QA/QC Program The inspector reviewed the development of the radiochemistry QA/QC program.
The program is required by the Corporate directive, Nuclear Stations Chemistry Quality Control Program, NSDD-25, January 1987, and implemented in the newly-revised BwCP PD-7, "Braidwood Station Chemistry QA/QC Program," Revision 3, July 14, 1987.
The licensee has developed a computer-based QC chart program for the various counting systems based on a commercial spreadsheet package.
The control source data'are entered and any part of the control chart may be displayed on a computer terminal screen along with the previous data and the control limits corrected for radioactive decay of the source.
A hardcopy is printed regularly to provide a permanent record of the data.
The availability to the laboratory personnel of the charts on the terminal allays the inspector's earlier concerns on the timeliness of the charts.1 The program is set up so-that control limits may be determined at any time from the parameters of the Chi-Squared test which must be performed at least semiannually, as required by the above Corporate directive (NSDD-25), or if changes are made to a counter.
1 Region III Inspection Reports No. 50-456/87035; 50-457/87037
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The licensee's radiochemistry QA/QC program has progressed very well and it appears to be strong.
No violations or deviations were identified.
8.
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.
No.new open items were disclosed during the course of the inspection.
9.
Exit Interview The scope and findings of the inspection were reviewed with licensee representatives (Section 1) at the conclusion of the inspection on December 17, 1987.
The discussion focused on the sampling of the Unit 2 primary and secondary systems and the quality control programs described in Sections 2 and 3.
The inspector stated the remaining open items would not impact on fuel loading.
A telephone discussion was held with Mr.. R. James on December 21, 1987, regarding the analysis of Fe-55.
Juring the exit interview, the inspector discussed the likely informational content of the inspection report with regard to documents or processes reviewed by the inspecter during the inspection.
Licensee representatives did not identify any such documents or processes as proprietary.
Attachments:
1.
Teble 1, Confirmatory Measurements Program 2.
Attachment 1, Criteria For Comparing Analytical Measurement;
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f TABLE 1 U S NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT CONFIRMATORY MEASUREMENTS PROGRAM FACILITY: BRAIDWOOD FOR THE 4 QUARTER OF 1987
NRC-------
LICENSEE----
---LICENSEE!NRC----
SAMPLE ISOTOPE RESULT ERROR RESULT ERROR RATIO RES T
L SPIKED FE-55 5.2E-05 1.OE-06 7.OE-05 7.OE-06 1.3E 00 5.2E O1 D
T TEST RESULTS:
A= AGREEMENT D= DISAGREEMENT
- = CRITERIA RELAXED N=NO 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 program.
Inthesecriteria,thejudgmentlimitsarevariableinrelationiothecomparison 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.
RESOLUTION RATIO = LICENSEE VALUE/NRC REFERENCE VALUE Agreement
<4 0.4 - 2.5 4-
0.5 - 2.0 8-
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 l
criteria and identified on the data sheet.
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