ML20205B401
| ML20205B401 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 03/16/1987 |
| From: | Murray B, Nicholas J, Wise R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20205B372 | List: |
| References | |
| 50-458-87-03, 50-458-87-3, NUDOCS 8703270601 | |
| Download: ML20205B401 (18) | |
See also: IR 05000458/1987003
Text
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APPENDIX B
U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report:
50-458/87-03
License:
Docket:
50-458L
Licensee: Gulf States Utilities (GSU)
P. O. Box 220
St. Francisville, Louisiana 70775
Facility Name:
River Bend Station (RBS)
Inspection At:
River Bend Station, St. Francisville, Louisiana
Inspection Conducted:
February 9-13, 1987
Inspectors:
J[Ad7
JfjB. Nicholas, Sedior Radiation Specialist
Date
Mcilities Radiological Protection Section
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/K
&
r/a/tr
R. Wise, Radiation Specialist, Facilities
Date
Radiological Protection Section
C(
c
Approved:
U $bkl
NlbObf
$/lb/B
B. Murray, Chief, Faci ities Radiological
Date'
Protection Section
Inspection Summary
Inspection Conducted February 9-13, 1987 (Report 50-458/87-03
Areas Inspected:
Routine, unannounced inspection of the licensee's water
chemistry and radiochemistry programs, including:
review of organization and
management controls, staffing and staff qualifications, training program,
procedures, facilities and equipment, quality assurance (QA) program of water
chemistry and radiochemistry activities, postaccident sampling system (PASS),
quality control of analytical measurements, and water chemistry and
radiochemistry confirmatory measurements.
8703270601 870324
ADOCK 05000458
G
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Results: 'Within the areas inspected, one violation was. identified.(failure-to
ensure the capability to obtain and analyze postaccident samples, paragraph 5).
One unresolved item was identified (failure to conduct training,
paragraph 6). .No deviations were identified.
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DETAILS
1.
Persons Contacted
GSU
'*D. H. Barrow, Director, GSU
- W. J. Cahill, Jr.
Senior Vice President, GSU
- J. C. Deddens, Senior Vice President, RBS Nuclear Group
- T. F. Plunkett, Plant Manager
- D. L. Andrews, Director, Nuclear Training
- R. J. Backen, Acting Supervisor, Operations QA
- J. E. Booker, Manager, Oversight
T. D. Burnett, Plant Chemist
- J. L. Burton, Supervisor, Independent Safety Engineering Group
- E. M. Cargill, Supervisor, Radiological Programs
- J. W. Cook, Lead Environmental Analyst, Licensing
'K. C. Coffey, Nuclear Chemistry Technician
- L. A. England, Supervisor, Licensing
- K. J. Gladrosich, Supervisor, Operations Quality Control (QC)
- D. R. Gipson, Director, Quality Services
- E. R. Grant, Director, Nuclear Licensing
- J. R. Hamilton, Director, Design Engineering
R. P. Hebert, QA Engineer
- K. C.'Hodges,' Supervisor, QA Engineering
- R. E. Horn, Nuclear ~ Training Coordinator - Technical
- G. R. Kimmell, Supervisor, Operations QA
- R. J. King, Supervisor, Nuclear Licensing
F. Kral, Nuclear Chemistry Technician
G. D. Lipham, Chemistry Foreman
A. S. Maryman, Nuclear Chemistry Technician
- I. M. Malik,' Supervisor, Quality Systems
- J. H. McQuirter,' Licensing Engineer
- T. O. Maffitt, QA Engineer-
- C. L. Nash, Chemistry Supervisor
- V. J. Normand, Supervisor, Administrative Services
- W.-H. Odell, Manager, Administration
E. R. Oswood, Lead Senior QA Engineer
- J. J. Pruitt, Director, Management Systems
E. T. Rochelle, Lead Chemist
- M. F. Sankovich, Manager, Engineering
C. S. Scott, Plant Chemist
J. E. Spivey, QA Engineer
- R. B. Stafford, Director, Quality Operations
- D. Williamson, Operations Supervisor
W. K. Woodcox, Chemistry Foreman
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Others
- D. D. Chamberlain, NRC Senior Resident Inspector
- G. A. Pick, NRC Reactor Engineer, Region IV
- R. C. Stewart, NRC Reactor Inspector, Region IV
- Denotes those present during the exit briefing on February 13, 1987.
The NRC inspectors also interviewed several other 58S employees during the
inspection.
2.
Follow-up on Previous Inspection Finding
(Closed) Violation (458/8605-01): Failure to Maintain Calibration Records
- This item involved the failure to maintain the required instrument
calibration data and records for the gas partitioner prior to performing
hydrogen analyses of the offgas hyr.cogen recombiner effluent. The NRC
inspector reviewed the licensee'F Corrective actions including revisions
to Chemistry Section Procedures CSP-0100, " Chemical / Radiochemical Technical
Specifications Surveillances," Revision 2, dated March 24, 1986, and
CSP-0206, " Operation of the *cisher Gas Partitioner Model 1200," Revision 1,
dated February 12, 1986.
The NRC inspector also reviewed documentation of
calibrations performed or, the gas partitioner prior to use for hydrogen
analyses during 1986 apJ found the calibrations performed and recorded in
accordance with appro',ed procedures.
This violation is considered closed.
3.
Follow-up on Licen<,ee Event Report
(Closed) License.e Event Report (458/86-046): Missed Technical Specification
Requirement on Fuel Building Radiation Monitor - This item involved the
wide range gas monitor on the fuel building exhaust stack being inoperable
for greater than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> without an alternate means of stack sampling and
monitoring in service.
Auxiliary sampling equipment for particulates and
iodines was not placed in service within the 8-hour time period and the
release was not suspended.
The NRC inspector reviewed the monitoring
conditions of the fuel building exhaust stack and the reasons for the
licene,ee event report.
The NRC inspector also reviewed the licensee's
corrective actions, including the Condition Report 86-0726 and the
revision to Chemistry Operating Procedure C0P-0046, " Sampling Gaseous
Ef/luents via the Wide Range Gas Monitors," Revision 5, dated January 27,
1987.
This item is considered closed.
4.
Program Areas Inspected
The following program areas were inspected.
Unless otherwise noted, the
inspection was completed and identified no violations, deviations,
unresolved items, or open items.
Notations after a specific inspection
item are used to identify the following:
I = item was not inspected or
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was only partially inspected and may require further review and evaluation
during the current inspection cycle, V = violation, D = deviation,
U = unresolved item, and 0 = open item.
Inspection Procedure
Inspection Requirements
83722
Plant Chemistry:
Organization and
Management Controls (Minimum / Basic)
02.01 - Organization
02.02 - Staffing
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02.03 - Chemistry Supervisor
02.04 - Identification and Correction of
Weaknesses
02.05 - Audits and Appraisals
83522
Plant Chemistry:
Organization and
Management Controls (Preoperational and
Supplemental)
02.01 - Organization, Responsibilities,
and Authorities
02.02 - Staffing
02.03 - Identification and Correction
of Weaknesses
02.04 - Audits and Appraisals
02.05 - Communication to Employees
02.06 - Documentation and Implementation
83723
Plant Chemistry:
Training and
Qualifications (Minimum / Basic)
02.01 - Responsibilities
02.02 - New Personnel
02.03 - Audits and Appraisals
83523
Plant Chemistry:
Training and
Qualifications (Preoperational and
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Supplemental)
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02.01 - Training and Qualifications
Program
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02.02 - Education and Experience
02.03 - Adequacy
84725
Quality Assurance and Confirmatory
Measurements For In-Plant Radiochemical
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Analysis (Minimum / Basic)
02.01 - Audits and Appraisals
02.02 - Changes
02.03 - Confirmatory Measurements
02.04 - Postaccident Sample Analysis-V
(see paragraph 5)
02.05 - Implementation of the Quality
Assurance Program
02.06 - Contractor Activities
84525
('uality Assurance and Confirmatory
Measurements For In-Plant Radiochemical
Analysis (Preoperational and
Supplemental)
02.01 - Facilities, Equipment, and
Supplies
02.02 - Procedures
02.03 - Confirmatory Measurements
02.04 - Postaccident Sample Analysis-U
(see paragraph 5)
02.05 - Quality Assurance Program
02.06 - Contractor Activities
79701
Light Water Reactor Water Chemistry
Control and Chemical Analysis (Basic)
02.01 - Audits and Appraisals
02.02 - Changes
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02.03 - Implementation of the Water
Chemistry Control Program
02.04 - Implementation of the Quality
Assurance Program for. Chemical
Measurements
79501
Light Water Reactor Water Chemistry
Control and Chemical Analysis
(Preoperational and Supplemental)
02.01 - Establishment of a Water
Chemistry Control Program-I
02.02 - Implementation of the Water
Chemistry Control Program-I
02.03 - Water Sampling
02.04 - Chemistry Measurements:
Facilities and Equipment
02.05 - Establishment of a Quality
Assurance Program for Chemical
Measurements-I
02.06 - Implementation of a Quality
Assurance Program for Chemical
Measurements-I
02.07 - Laboratory Safety
79502
Plant Systems Affecting Plant Water
Chemistry (Preoperational and
Supplemental)
,
-02.01 - Audits and Appraisals
02.02 - Primary and Secondary Water
Systems-I
02.03 - Auxiliary Water Systems-I
02.04 - Demineralizers-I
5.
Violation
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84725, Item 02.04 - Postaccident Sample Analysis
Technical Specification 6.8.4(c) requires that a program be established,
implemented, and maintained which will ensure the capability to obtain and
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analyze reactor coolant, radioactive iodines and particulates in gaseous
effluents, and containment atmosphere samples, under accident conditions.
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The program shall include training of personnel, procedures for sampling
and analysis, and provisions for maintenance of sampling and analysis
equipment.
Chemistry Section Procedure CSP-0150, " Chemistry Surveillance
of the Postaccident Sampling System," Revision 1, dated January 2, 1986,
requires that a monthly surveillance of the PASS be performed to ensure the
capability to obtain and analyze postaccident samples of reactor water and
containment atmosphere.
Contrary to the above, On February 12, 1987, the
NRC inspectors reviewed the results of the monthly surveillance tests
attempted on the PASS and found that since the initial demonstration of
PASS operability on November 10, 1985, prior to exceeding 5 percent power,
none of the monthly surveillance tests throughout 1986 had been completed
successfully to demonstrate the capability of the PASS to obtain and
analyze reactor water and containment atmosphere postaccident samples.
On
February 12, 1987, the NRC inspectors requested that the licensee
demonstrate the operability of the PASS under simulated accident conditions.
The attempt to operate the PASS was unsuccessful due to equipment
malfunction. The failure to establish, implement, and maintain a program
to ensure the capability to obtain and analyze reactor water and
containment atmosphere postaccident samples is an apparent violation of
Technical Specification 6.8.4(c).
(458/8703-01)
6.
Unresolved Item
84525, Item 02.04 - Postaccident Sample Analysis
Technical Specification 6.8.4(c) requires that a program be established and
implemented to provide training to personnel on the operation of the PASS.
The licensee's Chemistry Section Procedure CSP-003, " Chemistry Personnel
Qualifications," Revision 2, dated January 30, 1986, states in
paragraph 6.5.4 that continuing training of chemistry personnel shall
include annual PASS retraining.
Contrary to the above, the NRC inspectors
determined on February 12, 1987, that the licensee had not conducted annual
requalification training on the PASS for the nuclear chemistry technicians
since the initial training conducted in August 1985.
The failure to
conduct the required annual requalification training is considered a
pntential violation.
Since this matter is related to training, it is not
classified as a violation, but is considered to be an unresolved item in
accordance with the Commission Policy Statement on Training and
Qualification of Nuclear Power Plant Personnel (50 FR 11147 dated March 30,
1985).
(458/8703-02)
7.
Exit Briefing
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The NRC inspectors met with the NRC senior resident inspector and the
licensee representatives denoted in paragraph 1 at the conclusion of the
inspection on February 13, 1987.
The lead NRC inspector summarized the
scope of the inspection and discussed the inspection findings and the
results of the confirmatory measurements.
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ATTACHMENT 1
Analytical Measurements
1.
Chemistry Confirmatory Measurements
During the inspection, standard chemical solutions were submitted to the
licensee for analysis.
The standard solutions were prepared by the
Brookhaven National Laboratory, Safety and Environmental Protection
Division, for the NRC.
The standards were analyzed by the licensee using
routine methods and equipment.
The analysis of chemical standards is used
to verify the licensee's capability to monitor chemical parameters in
various plant systems with respect to Technical Specification requirements
and other industry standards.
In addition, the analysis of standards is
<
used to evaluate tha licensee's analytical procedures with respect to
accuracy and precision.
The results of the measurements comparison are listed in Attachment 2.
Attachment 3 contains the criteria used to compare results.
The
licensee's analytical results indicated that six of the seven results were
in agreement.
All standards were analyzed in triplicate.
2.
Radiological Confirmatory Measurements
Confirmatory measurements were performed on the following standards and
samples in the Region IV mobile laboratory at River Bend Station during
the inspection:
a.
Reector Coolant Liquid (1 liter Marinelli)
b.
Gas Sample (15 cc Off Gas Vial)
c.
Particulate Filter Standard (21478-109)
d.
Charcoal Cartridge Standard (21420-109)
e.
Liquid Waste Sample (1 liter Marinelli)
f.
Tritium Sample
The confirmatory measurements tests consisted of comparing measurements
made by the licensee and the NRC mobile laboratory.
The NRC's mobile
laboratory measurements are referenced to the National Bureau of Standards
by laboratory intercomparisons.
Confirmatory measurements are made only
for those nuclides identified by the NRC as being present in concentrations
greater than 10 percent of the respective isotopic values for liquid and
gas concentrations as stated in 10 CFR Part 20, Appendix B, Table II.
Attachment 5 contains the criteria used to compare results.
At the time of the inspection, the licensee utilized three detectors in
chemistry for comparison with the NRC results.
The licensee performed the
tritium analysis on their liquid scintillation counting system.
The
individual sample analyses and comparison of analytical results of the
radiological confirmatory measurements are tabulated in Attachment 4.
The
licensee's gamma isotopic results from the listed samples in Attachment 4
showed 96 percent agreement with the NRC analysis results.
The licensee's
tritium result was in agreement with the NRC analysis result.
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Confirmatory measurements were performed by the licensee on liquid samples
prepared by the Radiological Environmental Sciences Laboratory (RESL) in
The Itcensee's analytical results were compared to
the known sample activities and the results of the comparisons are
presented in Attachment 4, Sample 7.
The licensee's results were in
86 percent agreement for sample 7 analyzed in 1986.
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ATTACHMENT 2
Chemistry Confirmatory Measurements Results
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RBS Results NRC Results
RBS/NRC
Comparison
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Chemical Parameter
(ppb)
(ppb)
Ratio
Decision
146.214.6
153.014.0
0.9610.04
Agreement
157.619.6
147.014.2
1.0710.07
Agreement
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145.212.1
-143.018.0
1.0210.06
Agreement
140.712.3
14516.0
0.9710.04
Agreement
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Silica
20.610.3
21.811.4
0.9510.06
Agreement
11.9810.16
12.0511.55
0.9910.13
Agreement
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Sulfate
11.8410.37
10.0010.45
1.1810.06
Disgreement
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NOTE:
All licensee analyses were run at least in triplicate.
The analyses
were repeat analyses of one dilution and the uncertainty is an estimate of the
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instrument precision.
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ATTACHMENT 3
Criteria For Comparing Analytical Measurements
This attachment provides criteria for comparing results of capability tests.
In these. criteria the judgement limits are based on the uncertainty of the
ratio of the licensee's value to the NRC value.
The following steps are
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performed:
(1) the ratio'of the licensee's value to the NRC value is computed
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Licensee Value
(ratio =
NRC Value
);
(2) the uncertainty of the ratio is propagated.1
If the absolute value of one minus the ratio is less than or equal to twice the
ratio uncertainty, the results are in agreement.
(ll-ratiol 5 2 uncertainty)
Z= X, then Sz2 = Sx2+
2
V
F
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(From:
Bevington, P.R., Data Reduction and Error Analysis fer the Physical
Sciences, McGraw-Hill, New York, 1969)
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' ATTACHMENT 4
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, RADIOLOGICAL CONFIRMATORY' MEASUREMENTS RESULTS
1. - ' Reactor Coolant Liquid-(1 Liter Marinelli Beaker)
'(Sampled 08:40, CST, February .10, 1987)
RBS Results.
NRC' Results'-
RBS/NRC
-. Comparison
Nuclide
(uCi/ml)
(uCi/ml)
Ratioi
. Decision
24Na
6.48810.385 E-4.
6.41110.118E-4
1.01
. Agreement
5.85710.'353 E-4
0.91
Agreement
6.-15610.368 E-4
0.96
Agreement
s Cr.
1.18710.098 E-3-
1.22010.068E-3
0.97
Agreement
~
Not Identified
Disagreement
1.13810.089 E-3
0.93'
Agreement
99Mo
5.425i0.380 E-4
5.03910.329 E-4
1.08
Agreement
5.00610.386 E-4
0.99
Agreement
5.13510.360 E-4
1.02
Agreement
tosRh
6.15810.507 E-4
6.32610.353 E-4
0.97
Agreement
5.97910,526 E-4
0.95
Agreement-
5.94010.467 E-4
0.94
Agreement
'122Sb
6.99110.071 E-5
7.37510.536 E-5
0.95
Agreement
6.22910.069 E-5
0.84
Agreement-
5.02110.069 E-5
0.68
Agreement
187W
1.44510.139 E-4
1.48010.238 E-4
0.98
Agreement
1.24510.015 E-4
0.84
Agreement
-1.33010.131 E-4
0.90
Agreement
98"Tc
,3.69710.292 E-3
4.25010.018 E-3
0.87
Agreement
'3.42910.269 E-3
0.81
Disagreement.
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3.55810.283 E-3
0.84
Disagreement
13&I
2.27110.063 E-5
3.25710.666 E-5
0.70
. Agreement
2.19510.068 E-5
0.67
Agreement
1.98710.058 E-5
0.61
Agreement
132I
4.51610.170 E-4
4.65710.127 E-4
0.97
Agreement
4.34410.157 E-4
0.93
Agreement
4.63710.167 E-4
0.94
Agreement
133I
2.87810.188 E-4
2.94910.058 E-4
0.98
Agreement
2.72810.184 E-4
0.93
Agreement
2.85910.184 E-4
0.97
Agreement
1341
1.02610.036 E-3
1.05010.038 E-3
0.98
Agreement
9.82210.302 E-4
0.94
Agreement
9.64310.386 E-4
0.92
Agreement
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135I
'5.72610.202 E-4
6.27310.224 E-4
0.91
Agreement
5.21910.200 E-4
0.83
Agreement
5.54310.201 E-4
0.88
Agreement
2.
Off Gas Sample (15 cc Off Gas Vial)
(Sampled 10:29, CST, February 11,1987)
RBS Results
NRC Results
RBS/NRC
Comparison
Nuclide
(uCi/cc)
(uCi/cc)
Ratio
Decision
41Ar
7.14512.444 E-5
5.74411.283 E-5
1.24
Agreement
7.61812.384 E-5
1.33
Agreement
8.48812.521 E-5
1.48
Agreement
85"Kr
1.69710.171 E-4
1.67410.066 E-4
1.01
Agreement
1.50910.202 E-4
0.90
Agreement
1.66110.159 E-4
0.99
Agreement
87Kr
9.83010.912 E-4
1.15310.034 E-3
0.85
Agreement
9.52510.912 E-4
0.83
Agreement
9.98110.946 E-4
0.87
Agreement
88Kr
6.38510.613 E-4
6.03910.333 E-4
1.06
Agreement
7.23310.846 E-4
1.20
Agreement
5.75310.542 E-4
0.95
Agreement
185"Xe
3.57410.468 E-3
2.92610.090 E-3
1.22
Agreement
3.36710.337 E-3
1.15
Agreement
3.34710.643.E-3
1.14
Agreement
135Xe
5.19810.461 E-4
5.27310.122 E-4
0.99
Agreement
4.47310.433 E-4
0.85
Agreement
4.86010.428 E-4
0.92
Agreeement
138Xe
1.54210.104 E-2
1.25010.049 E-2
1.23
Agreement
1.38310.059 E-2
1.11
Agreement
1.33310.155 E-2
1.07
Agreement
3.
Particulate Filter Standard (21478-109)
(Standardized 09:00, CST, February 9, 1987)
RBS Results
NRC Results
RBS/NRC
Comparison
Nuclide
(uCi/ Sample)
(uCi/ Sample)
Ratio
Decision
109Cd
1.19810.101 E+0
1.11210.003 E+0
1.08
Agreement
1.24510.105 E+0
1.12
Agreement
1.16210.098 E+0
1.04
Agreement
57Co
2.86110.124 E-2
2.58510.010 E-2
1.11
Agreement
2.99410.128 E-2
1.16
Agreement
2.77710.119 E-2
1.07
Agreement
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189Ce
1.83910.122 E-2
1.74010.010 E-2
1.06
Agreement
1.92210.128.E-2
1.10
Agreement
1.84410.123 E-2
1.06
Agreement
203Hg
1.32110.104 E-2
1.38210.012 E-2
0.96
Agreement
1.35910.107 E-2
0.98
Agreement
1.30410.103 E-2
0.94
Agreement
118Sn
3.08110.165 E-2
2.90010.021 E-2
1.06
Agreement
3.21510.170 E-2
1.11
Agreement
2.98510.162 E-2
1.03
Agreement
137Cs
5.12210.252 E-2
4.63510.030 E-2
1.11
Agreement
5.13310.253 E-2
1.11
Agreement
5.03510.248 E-2
1.09
Agreement
88
3.91010.152 E-2
3.71610.030 E-2
1.05
Agreement
y
3.97510.155 E-2
1.07
Agreement
3.88510.152 E-2
1.05
Agreement
GoCo
3.11510.107 E-2
2.94210.029 E-2
1.06
Agreement
3.20610.111 E-2
1.09
Agreement
.3.16210.110 E-2
1.07
Agreement
4.
Charcoal Cartridge Standard (21420-109)
l
(Standardized 09:00, CST, February 9, 1987)
RBS Results
NRC Results
RBS/NRC
Comparison
Nuclide
(uCi/ Sample)
(uCi/ Sample)
Ratio
Decision
109Cd
1.19710.101 E+0
1.16310.003 E+0
1.03
Agreement
1.26010.106 E+0
1.08
Agreement
1.19210.101 E+0
1.03
Agreement
57C0
2.80510.123 E-2
2.63010.011 E-2
1.07
2
Agreement
3.05310.131 E-2
1.16
Agreement
2.84710.124 E-2
1.08
Agreement
139Ce
1.87510.125 E-2
1.78110.011 E-2
1.05
Agreement
.
2.02710.135 E-2
1.14
Agreement
1.86110.124 E-2
1.05
Agreement
,
20aHg
1.35910.109 E-2
1.30710.011 E-2
1.04
Agreement
1.35610.107 E-2
1.04
Agreement
1.29810.103 E-2
0.99
Agreement
113Sn
3.12310.169 E-2
2.97610.021 E-2
1.05
Agreement
3.29810.175 E-2
1.11
Agreement
3.04010.165 E-2
1.02
Agreement
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4
137Cs
5.11710.252 E-2
4.81310.029 E-2
1.06
Agreement
5.35510.264 E-2
1.11
Agreement
5.05210.250 E-2
1.05
Agreement
88y
3.95610.155 E-2
3.83910.030 E-2
1.03
Agreement
4.19410.164 E-2
1.09
Agreement
3.89310.153 E-2
1.01
Agreement
80Co
3.23310.112 E-2
3.15410.029 E-2
1.03
Agreement
3.37110.117 E-2
1.07
Agreement
3.23810.113 E-2
1.03
Agreement
5.
Liquid Waste Sample (1 liter Marinelli)
(Sample 07:50, CST, February 11, 1987)
RBS Results
NRC Results
RBS/NRC
Comparison
Nuclide
(uCi/ml)
(uCi/ml)
Ratio
Decision
24Na
5.85610.814 E-7
5.06510.573 E-7
1.16
Agreement
5.13610.781 E-7
1.01
Agreement
5.49410.813 E-7
1.08
Agreement
stCr
2.04410.523 E-6
2.33110.584 E-6
0.88
Agreement
2.09910.569 E-6
0.90
Agreement
1.56810.499 E-6
0.67
Agreement
54Mn
1.87610.090 E-5
1.85110.025 E-5
1.01
Agreement
1.75010.085 E-5
0.95
Agreement
1.83610.088 E-5
0.99
Agreement
58C0
2.21610.107 E-5
2.17610.025 E-5
1.02
Agreement
2.07610.101 E-5
0.95
Agreement
2.14810.105 E-5
0.99
Agreement
80Co
1.87210.074 E-5
1.81610.027 E-5
1.03
Agreement
1.81110.072 E-5
1.00
Agreement
1.78010.071 E-5
0.98
Agreement
85Zn
2.95510.298 E-6
2.67310.238 E-6
1.11
Agreement
2.40910.282 E-6
0.90
Agreement
2.66810.291 E-6
1.00
Agreement
80*Tc
9.86010.908 E-7
8.42010.539 E-7
1.17
Agreement
8.72110.830 E-7
1.04
Agreement
1.00510.096 E-6
1.19
Agreement
-
.
- -
- - - _ - . - - - - - . _ - - - - _
,
9:n o
\\
>
>
.
5
,
6.
Tritium San >1e
(Sampled Fe)ruary 11,1987)
RSS Results
NRC Results
R8S/NRC
Comparison
l
Nuclide
(uci/c)
(uci/a)
Ratio
Decision
8H
5.0010.11 E-4
5.6710.58 E-4
0.88
Agreement
7.
RESL Liquid Sample
(Standardized 12:00, MST, January 11,1986)
,
RBS Results
NRC Results
RBS/NRC
Comparison
l
Nuclide
(uCi/ml)
(uCf/ml)
Ratio
Decision
soSr
1.310.1 E-04
1.4010.04 E-04
0.93
Agreement
.
00Sr
1.510.1 E-05
1.3310.05 E-05
1.13
Agreement
_,
I
55Fe
6.310.2 E-04
8.2610.17 E-05
7.63
Disagreement
aH
1.0010.03 E-04
1.1110.02 E-04
0.90
Agreement
137Cs
2.3010.15 E-05
2.1910.07 E-05
1.05
Agreement
soCo
2.0910.10 E-05
1.9510.04 E-05
1.07
Agreement
54Mn
1.4710.10 E-05
1.3510.03 E-05
1.09
Agreement
l
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l
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!
l
i
!
!
c
'
I
' -.
- -
-
. . .
.
-.
-
.
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _
.
..
. .
.
..
.....
.
. . . . . . ..
. . . .
. . . .
o.
ATTACHMENT 5
.
Criteria for Comparina Analytical Measurements
The following are the criteria used in comparing the results of capability
tests and verification measurements. The criteria are based on an empirical
relationship established through prior experience and this program's analytical
requirements.
In these criteria, the judgement limits vary in relation to the comparison of
the resolution.
NRC VALUE
Resolution =
_
NRC UNCERTAlhiY
LICENSEE VALUE
Ratio =
NRC VALUE
Comparisons are made by first determining the resolution and then reading
across the same line to the corresponding ratio. The following table shows the
acceptance values.
!
RESOLUTION
AGREEMENT RATIO
l
!
<4
0.4 - 2.5
4-7
0.5 - 2.0
8 - 15
0.6 - 1,66
.
16 - 50
0.75 - 1.33
,
51 - 200
0.80 - 1.25
>200
0.85 - 1.18
l
The above__ criteria are applied to the following analyses:
(1) Gamma Spectrometry.
(2) Tritium analyses of Ilquid samples.
,
(3) Iodine on adsorbers.
(4) av5r and '0Sr determinations.
(5) Gross Beta where samples are counted on the same date using the same
reference nucilde.
-
-
-
-
.