IR 05000456/1990005
| ML20006E975 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 02/13/1990 |
| From: | House J, Januska A, Schumacher M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20006E974 | List: |
| References | |
| 50-456-90-05, 50-456-90-5, 50-457-90-05, 50-457-90-5, NUDOCS 9002270016 | |
| Download: ML20006E975 (9) | |
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b-U.S. NUCLEAR REGULATORY COMMISSION
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REGION III
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' Reports No. 50-456/90005(DRSS); 50-457/90005(ORSS)
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. Docket Nos. 50-456; 50-457'
Licensee:
Commonwealth Edison Company i
Post Office Box 767
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- Chicago', IL 60690 Facil'fty Name: Braidwood' Nuclear Power Station, Units 1 and 2 Inspection At: Braidwood Site, Bracev111e, Illinois l
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. Inspection Conducted: January 22-25, February 5. and 6,1990 jf/hw cA'f Inspectors:
A. G. Januska
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a//r/76 J. E. House
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Date 9lfktwnuh Approved By: M C. Schumacher, Chief
Radiological Controls and Date Chemistry Section i
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Inspection Summary
- Inspection on January 22-25, February 5 and 6, 1990 (Reports
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No. 50-456/90005(DRSS); No. 50-457/90005(DRSS))
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' Areas Inspected:
doutine announced inspection of confirmatory x.
,~,aents
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review of an open item (IP 92701) and a violation (IP 92702);
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audits.and surveillances; implementation of-the quality assurance and.
confirmatory measurements programs and postaccident sample analyses (IP 84750).
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Results:
Laboratory quality assurance was good. The postaccident sampling system is'being exercised daily during the collection of routine primary-coolant-samples, however, there-is no routine QC program being implemented.
Confirmatory measurement-analytical results with the NRC continue to be.
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_ good' In addition,.crosscheck results with an independent contractor for 1989
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yi were perfect.
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No violations or deviations were identified.
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k DETAILS 1.
Persons Contacted e
S. Brant, ChemTech.
- J. Burns, Lead Chemist
'#*E._ Carroll, Regulatory Assurance
- S. Hopewell, Nuclear Chemistry Supervisor, G.O.
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- R. James, Counting Room /HRSS
- D. Miller, Regulatory Assurance Supervisor
- D. O'Brien, Technical Superintendent
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- J. Petko, Chemistry Supervisor
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- R. Querio, Station-Manager E. Spevak, Auditor
- G. Vickery, Chemist
- T. Tongue, Senior Resident Inspector, NRC
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- Present at the Exit Meeting on January 25, 1990
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- Telephone conversations on February 5 and 6, 1990
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Licensee Action on Previous Inspection Findings (IP 92701,927021 a.
[ Closed) Violation (50-456/88017-01;50-457/88017-01):
Four germanium detectors used to demonstrate compliance with the Braidwood Technical Specifications were improperly calibrated using non-certified radioactive sources on five different occasions. The detectors were recalibrated on July 13, 1989 with valid standards.
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The accuracy of the recalibrations is substantiated by the agreements achieved for the comparisons-made during this inspection. The (
inspector examined BwCP 523-18 " Empirical Fit Efficiency Calibration of-AAIS-Germanium Detectors" which includes prohibitions on the use of expired. sources and non-certified sources for calibration purposes.
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The inspector also-saw Braidwood General Surveillance File Listing
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which contains an annual requirement to direct the timely replacement of_ expiring sources. The listing also references BwD 523-18.
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(Closed) Open' Item (50-456/88017-02; 50-457/88017-02):
Licensee to complete calibrations of routine geometries on the PARAPS, verify library contents and review analytical algorithms to assure they are proper and that they work. Appropriate calibrations have been-E completed. ' A review of the library used during the inspection and
.of the algorithms has been completed.
The comparisons made during
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the sample split portion of the -inspection indicate that these reviews were done properly.
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Confirmatory Neasurement (IP 84750)
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Sample Split Five samples (containment charcoal, crud filter, gas, reactor coolant and liquid) were analyzed for gamma emitting isotopes by the licensee and in the Region III Mobile Laboratory on site.
Comparisons were made on combinations of the licensee's five normally used count room detectors and the Post Accident Radionuclide Analysis Portable System (PARAPS).
Results of.the ample comparisons are given in Table 1; the comparison criteria a-2 given in Attachment 1.
The licensee achieved 79 agreements out of 81 comparisons.
Charcoal filter, crud (primary coolant filter) and reactor coolant sample analyses resulted in all agreements.
A liquid waste sample analyzed resulted in a nonconservative disagreement for Cs-137 on detector 29-TP-30 after having achieved a nonconservative agreement on detector 26-PK-20.
Independent analyses of simulated liquid standards by both the licensee and the inspector resulted in agreements for this nuclide. Although no reason for the disagreement was found, sample settling or plateout is suspected as the cause. A portion of the liquid waste sample will be analyzed for gross alpha, gross beta, H-3, Sr-89, Sr-90 and Fe-55 by the license and the results reported to Region III for comparison with an analysis on a split of the same sample by the NRC Reference Laboratory (0 pen Item 50-456/90005-01; 50-457/90005 01).
Xe-131m in a waste gas decay tank sample was a disagreement on detector 22-P-01W but an agreement on detector 25-P-142, the second analysis of the same sample.
Examination of the licensee's data indicated that the nuclide energy was not present.
The Xe-131m peak is 2 key from the Kr-88 peak and was most probably masked by this shorter lived nuclide on the initial analysis of the sample. This sample is atypical of a release analysis because the decay tank was on line and contained gaseous nuclides not normally present in a release sample, b.
Audits The inspectors reviewed audit QAA-20-89-02 and surveillances QAS-20-09-25, -49, -65, and -114 and discussed Chemistry training and experience with a Lead Auditor who conducted the surveillances.
The audit dealt with implementation of the Quality Assurance Program in the area of chemistry while the surveillances covered laboratory
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sampling and requirements, analyses and analytical procedures, QA programs and counting room techniques. There were no findings associated with the subject matter of this inspection. The surveillances were for the most part performance oriented.
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Qual hy Assurance The inspectors reviewed the radioactivity measurements laboratory quality assurance program including physical facilities and laboratory operations.
Housekeeping was generally good; laboratory and counting room work space was adequate. A ChemTech observed during sample acquisition and preparation for the inspectors was noted as having very good laboratory technique.
The licensee participates in an intercomparison cross-check program with an outside vendor. The inspectors examined the 1989 results and found all agreements. Daily implementation of the instrument quality control program was examined. Tests were run as required, the results recorded and computer based trend charts generated.
No violations of deviations were identified.
A.
Post Accident Sampling (IP 84750)
The inspectors discussed the High Radiation Sampling System (HRSS)
and its operation with the licensee representative assigned the responsibility for the system.
He has had this additional responsibility for approximately nine months and appeared very knowledgeable of the system.
A reactor coolant sample is collected daily for radiochemical analysis. Nonradiological parameters are not measured and no QC program exists for the inline monitors. The inspectors discussed the desirability of routine testing, and calibrating'of inline analytical equipment.
The lice.me acknowledged the inspector s remarks and issued Nuclear Tracking Iten, 31-225-90-004 whicii committed developing by February 5,1990, an action plan with milestones and dates for completion and implementation of a calibration and QC program for these monitors. The inspector reviewed this plan on February 5,1990, and discussed with the licensee on February 6,1990.
The licensee's progress on this matter will be followed in subsequent inspections (0pei. Item 50-456/90005-02; 50-457/90005-02).
No violations or deviations were identified.
5.
Open Items Open items are matters which have been discussed with the licensee, which will be reviewed further by the inspectors, and which involve some action on the part of the NRC or licensee, or both. An open item disclosed during the inspection is discussed in Sections 3 and 4.
6.
Exit Interview The scope and findings of the inspection were reviewed with licensee representatives (Section 1) at the conclusion of the inspection on January 25, 1990. The inspectors discussed the following in detail:
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preliminary confirmatory measurements results
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auditor and ChemTech performance.
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the post' accident sampling system
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During-the exit interview, the inspectors discussed the likely informational content of the inspection report with regard to documents p
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or processes reviewed by the inspectors during ti
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representatives did not identify any such documents or processes as
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proprieta ry..
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Attachments:
'1. ; Table 1, Confirmatory Measurements D
Program Results, -1st Quarter 1990
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2. - Attachment :1, Criteria for Comparing
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Analytical Measurements L
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I TABLE 1 r
U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT CONFIRMATORY MEAEUREMENTS PROGRAM
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i FACILITY: BRAIDWOOD FOR THE 1GT QUARTER OF 1990
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SAMPLE-NUCLIDE NRC VAL. NRC ERR,- LICsYAL.
LYC. ERR.
RATIO RESOL. RESULT CHARCOAL BR-82 5.22E-11 1.55E-12 4.305-1)
1.50E-12 0.82 33.7 A
28-TP-30 I-131 1.55E-11 6.17E-13 1.40E-11 1.10E-12 0.90 25.1 A
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I-133 2.77E-11 1.50E-12 2.40E-31 2.30E-12 0.87 18.5-A GAS A-41 2.40E-04 1.11E-05 2,102-04 2.00E-05 0.88 21.6 A
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22-P-01W KR-85M 8.19E-05 2.75E-06 8.20E*05 6.30E-06 1.00 29.8 A
KR-88 1.06E-04 8.62E-06 9.30E-05 1.20E-05 0.88 12.3 A
XE-131M 1.29E-04 2.94E-05 0.00E400 0.00E400 4.4 D
XE-133 1.70E-02 4.01E-05 1.70E-02 0,00E+00 1.00 423.9 A
XE-133M 1.57E-04 1.78E-05 1.50E-04 2,20E-05 0.96 8.8 A
l XE-135 9.63E-04 7.24E-06 1.00E-03 7.00E-05 1.04 133.0 A
CHARCOAL BR-82 4.88E-11 1.42E-12 4<61E+11 3.28E-12 0.94 34.4 A
'PARAPS I-131 1.33E-11 5.36E-13 1.38E-11 6.06E-13 1.04 24.8 A
I-133 2.64E-11 1.04E-12 2.74E-11 1.10E-12 1.04 25.4 A
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GAS AR-41 2.40E-04 1.11E-05 2.20E-04 2.10E-05 0.92 21.6 A
25-P-142 KR-85M 8.19E-05 2.75E-06 8.10E-05 6.00E-06 0.99 29.8 A
KR-88 1.06E-04 8.62E-06 9.40E-05 1.00E-05 0.89 12.3 A
XE-131H 1.29E-04 2.94E-05 1.50E-04 4.50E-05 1.16 4.4
~A XE-133 1.70E-02 4.01E-05 1.60E-02 0.00E+00 0.94 423.9 A
XE-133M 1.57E-04 1.78E-05 1'.50E-04 2.00E-05 0.96 8.8 A
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XE-135 9.63E-04 7.24E-06 9.40E-04 6.40E-05 0.98 133.0 A
LIQUID HN-54 9.32E-07 7.33E-08 7.70E-07 8.70E-08 0.83 12.7 A
WASTE CO-58 1.07E-05 1.74E-07 9.70E-06 8.10E-07 0.91 61.5 A
26-PK-20 C0-60 2.43E-06 1.03E-07 2.10E-06 1.40E-07 0.86 23.6 A
NB-95 3.99E-07 5.27E-08 4.70E-07 0.00E+00 1.18 7.6 A-SB-124 4.17E-07 8.78E-08 3.40E-07 7.40E-08 0.82 4.7 A
SB-125 6.73E-06-2.56E-07 6.20E-06 5.60E-07 0.92 26.3 A
j CS-134 4.59E-07 8.27E-08 5.20E-07 7.60E-08 1.13 5.6 A
y CS-137 8.35E-07 6.94E-08 6.10E-07 7.90E-00 0.73 12.0 A
PRIMARY' NA-24 5.99E-04 2.33E-05 5.30E-04 4.70E-05 0.88 25.7 A
COOLANT W-187 6,29E-04 1.18E-04 5.40E-04 4.50E-05 0.86 5.3 A
28-TP-30 I-131 1.66E-04 3.11E-05 1.90E-04 2.30E-05 1.14 5.3 A
I-132 3.70E-03 5.95E-05 3.30E-03 1.70E-04 0.89 62.2 A
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SAMPLE NUCLIDE NRC VAL. NRC ERR.
LIC. VAL.
LIC. ERR.
RATIO RESOL. RESULT
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I-133 2.01E-03 2.93E-05 1.80E-03 0.00E400 0.90 68.6 A
I-134 6.52E-03 2.50E-04 5.00E-03 3.50E-04 0.77 26.1 A
I-135 4.08E-03 1.29E-04 3.70E-03 1.70E-04 0.91 31.6 A
RB-88 3.28E-01 4.42E-02 3.00E-01 0.00E+00 0.91 7.4 A
CS-134 6.85E-05 1.41E-05 6.40E-05 6.20E-06 0.93 4.9 A
CS-137 8.51E-05 1.80E-05 6.50E-05 7.60E-06 0.76 4.7 A
CS-138 8.68E-03 1.03E-03 8.30E-03 8.20E-04 0.96 8.4 A
CRUD CR-51 7.24E-05 2.53E-06 6.80E-05 6.30E-06 0.94 28.6 A
FILTER MN-54 2.87E-06 2.25E-07 2.90E-06 3.20E-07 1.01 12.8 A
22-P-01W MN-56 7.52E-05 2.47E-06 7.90E-05 8.70E-06 1.05 30.4 A
FE-59 1.89E-06 4.08E-07 1.70E-06 2.40E-07 0.90 4.6 A
CO-57 3.37E-07 9.40E-08 0.00E+00 0.00E+00 3.6 N
CO-58 1.06E-04 8.45E-07 1.10E-04 9.00E-06 1.04 125.4 A
CO-60 6.11E-06 2.82E-07 6.00E-06 4.10E-06 0.98 21.7 A
W-187 7.46E-06 1.34E-06 5.50E-06 8.30E-06 0.74 5.6 A
I-131 7.83E-07 2.66E-07 0.00E+00 0.00E+00 2.9 N
I-133 1.84E-06 4.11E-07 2.50E-06 0.00E+00 1.36 4.5 A
ZR-95 2.06E-05 5.83E-07 2.00E-05 1.80E-06 0.97 35.3 A
ZR-97 6.33E-05 8.25E-07 6.90E-05 0.00E+00 1.09 76.7 A
NB-95 1.02E-05 3.28E-07 1.10E-05 9.00E-07 1.08 31.1 A
SN-113 1.49E-06 3.78E-07 9.70E-07 3.04E-07 0.65 3.9 N
SB-122 1.35E-06 4.63E-07 1.60E-06 0.00E+00 1.19 2.9 N
TE-132 3.99E-07 1.33E-07 0.00E+00 0.00E+00 3.0 N
CE-144 6.98E-06 8.03E-07 6.90E-06 0.00E+00 0.99 8.7 A
PRIMARY NA-24 5.85E-04 2.28E-05 5.00E-04 5.70E-05 0.85 25.7 A
COOLANT W-187 5.47E-04 1.07E-04 5.10E-04 4.50E-05 0.93 5.1 A
26-PK-20 I-131 1.51E-04 2.73E-05 1.70E-04 2.30E-05 1.13 5.5 A
1-132 3.68E-03 8.25E-05 3.30E-03 1.60E-04 0.90 44.6 A
I-133 2.05E-03 2.83E-05 1.80E-03 1.70E-04 0.88 72.4 A
I-134 6.91E-03 3.67E-04 5.50E-03 5.00E-04 0.80 18.8 A
I-135 4.00E-03 1.26E-04 3.50E-03 1.50E-04 0.88 31.7 A
RB-88 1.61E+00 2.98E-01 1.60E+00 0.00E+00 0.99 5.4 A
CS-134 7.81E-05 1.30E-05 6.10E-05 6.30E-06 0.78 6.0 A
CS-137 7.65E-05 1.56E-05 6.30E-05 8.50E-06 0.82 4.9 A
CRUD CR-51 7.24E-05 2.53E-06 6.54E-05 3.21E-06 0.90 28.6 A
FILTER MN-54 2.87E-06 2.25E-07 2.94E-06 2.52E-07 1.02 12.8 A
PARAPS MN-56 7.52E-05 2.47E-06 8.76E-05 1.22E-06 1.16 30.4 A
FE-59 1.89E-06 4.08E-07 2.61E-06 4.26E-07 1.38 4.6 A
CO-57 3.37E-07 9.40E-08 3.50E-07 1.11E-07 1.04 3.6 N
CO-58 1.06E-04 8.45E-07 1.13E-04 9.12E-07 1.07 125.4 A
CO-60 6.11E-06 2.82E-07 5.88E-06 3.36E-07 0.96 21.7 A
W-187 7.46E-06 1.34E-06 6.61E-06 0.00E+00 0.89 5.6 A
I-131 7.83E-07 2.66E-07 5.54E-07 0.00E+00 0.71 2.9 N
I-133 1.84E-06 4.11E-07 2.04E-06 3.95E-07 1.11 4.5 A
ZR-95 2 06E-05 5.83E-07 2.15E-05 6.99E-07 1.04 35.3 A
ZR-97 6.33E-05 8.2SE-07 6.68E-05 3.67E-07 1.06 76.7 A
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SAMPLE NOCLIDE NRC VAL. NRC ERR.
LIC. VAL.
LIC. ERR.
RATIO RESOL. RESULT
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NB-95 1.02E-05 3.28E-07 1.10E-05 0.00E+00 1.08 31.1 A
SN-113 1.49E-06 3.87E-07 0.00E+00 0.00E+00 3.9 N
SB-122 1.35E-06 4.63E-07 1.17E-06 5.61E-07 0.87 2.9 N
TE-132 3.99E-07 1.33E-07 0.00E+00 0.00E+00 3.0 N
CE-144 6.98E-06 8.03E-07 7.59E-06 1.39E-06 1.09 8.7 A
LIQUID MH-54 9.32E-07 7.33E-08 7.70E-07 8.90E-08 0.83 12.7 A
WASTE CO-58 1.07E-05 1.74E-07 1.00E-05 9.00E-07 0.93 61.5 A
29-TP-30 C0-60 2.43E-06 1.03E-07 2.30E-06 1.50E-07 0.95 25.6 A
NB-95 3.99E-07 5.27E-08 2.90E-07 0.00E+00 0.73 7.6 A
SB-124 4.17E-07 8.78E-08 4.00E-07 7.40E-08 0.96 4.7 A
SB-125 6 73E-06 2.56E-07 6.30E-06 5.80E-07 0.94 26.3 A
CS-134 4.59E-07 8.27E-08 4.60E-07 6.80E-08 1.00 5.6 A
CS-137 8.35E-07 6.94E-08 4.90E-07 7.40E-08 0.59 12.0 D
TEST RESULTS:
A: AGREEMENT D= DISAGREEMENT
- CRITERIA RELAXED N:NO COMPARISON
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ATTAC MENT 1
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CRITERIA FOR COMPARING ANALYTICAL MEASUREMENTS
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This attachment provides criteria for cosparing results of capability tests t
and verification measurements.
The criteria are based on an empirical i
relationship which combines prior experience and the accuracy needs of this program.
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In these criteria, the judgment limits are variable in relation to the comparison
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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 rounced 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
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<4 NO COMPARISON
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0.6 - 1.66 16 - 50 0.75 - 1.33
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0.85 - 1.18
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s Some discrepancies may result from the use of different equipment, techniques,
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and for some specific nuclides.
These may be factored into the acceptance criteria and identified on the data sheet.
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