ML16154A691
| ML16154A691 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 10/20/1994 |
| From: | Decker T, David Jones NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML16154A690 | List: |
| References | |
| 50-269-94-30, 50-270-94-30, NUDOCS 9411070114 | |
| Download: ML16154A691 (13) | |
See also: IR 05000269/1994030
Text
REG&~
~
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA STREET, N.W., SUITE 2900
ATLANTA, GEORGIA 30323-0199
October 21,
1994
Report Nos.: 50-269/94-30, 50-270/94-30, and 50-287/94-30
Licensee:
Duke Power Company
422 South Church Street
Charlotte, NC 28242
Docket Nos.:
50-269, 50-270,
and 50-287
and DPR-55
Facility Name: Oconee 1, 2, and 3
Inspection Conducted: September 20-21, 1994
I
n s p e c t o r :
D
S g d
D.
-
.
-,,e~esDate
Sign'ed
Accompanied by: D. A. Kasnicki
Approved by:
A
6
T. R. Decker,.Chief
Date Si§ned
Radiological Effluents and Chemistry Section
Radiological Protection and Emergency Preparedness Branch
Division of Radiation Safety and Safeguards
SUMMARY
Scope:
This routine, announced inspection was conducted in the area of confirmatory
measurements. Subsequent to this inspection, the licensee's annual
radiological environmental report for 1993 was reviewed and the results of
that review are documented in this report.
Results:
No violations or deviations were identified.
The licensee demonstrated adequate capability to quantify radionuclide
concentrations in various matrices normally encountered in nuclear power plant
operations (Paragraph 2).
The licensee's radiological environmental monitoring program was effectively
implemented. The program requirements for sampling, analysis, and reporting
were met. Dose estimates calculated from environmental monitoring program data
.
were in
reasonable agreement with dose estimates calculated from effluent data
and were within 40 CFR 190 dose limits. The program results for 1993 indicated
9411070114 941021
PDR ADOCK 05000269
G
- I
2
that there was no significant radiological impact on the health and safety of
the general public resulting from plant operations (Paragraph 3).
The results of the licensee's participation in the EPA's interlaboratory
crosscheck program indicated that an effective quality assurance program had
been maintained for the analysis of environmental samples (Paragraph 4).
The licensee's radiological environmental monitoring program data were
comparable to the State of South Carolina's Department of Health and
Environmental Control independent environmental monitoring program data
(Paragraph 5).
REPORT DETAILS
1.
Persons Contacted
Licensee Employees
D. Berkshire, Senior Scientist, Radiation Protection
- B. Dolan, Manager, Safety Assurance
- J. Hampton, Vice President
G. Hamrick, Manager, Chemistry
- E. Lampe, Scientist, Radiation Protection
tB. Pursley, Scientist, Radiation Protection
t*J. Smith, Licensing Coordinator, Regulatory Compliance
tS. Spear, General Supervisor, Radiation Protection
Other licensee employees contacted included engineers, technicians, and
office personnel.
Nuclear Regulatory Commission
- P. Harmon, Senior Resident Inspector
L. Keller, Resident Inspector
tK. Poertner, Resident Inspector
tAttended entrance interview
- Attended exit interview
2.
Confirmatory Measurements (84750)
10 CFR 20.1501 required the licensee to perform surveys as necessary to
evaluate the extent of radiation levels, the concentrations or
quantities of radioactive material, and the potential radiological
hazards that could be present.
In an effort to evaluate the licensee's analytical capabilities, samples
of Unit 2 and Unit 3 reactor coolant, Unit 3 containment atmosphere, and
liquid radwaste were collected and analyzed for radionuclide
concentrations by the licensee and the NRC Region II mobile laboratory.
A particulate filter and a silver zeolite cartridge were also collected
and analyzed. The inspector accompanied licensee personnel during the
collection of the above samples and determined by direct observation
that the samples were collected in accordance with the licensee's
sampling procedures. The reactor coolant samples were analyzed on three
of the licensee's gamma spectroscopic systems and each of the other
samples were analyzed on each of the licensee's six gamma spectroscopic
systems. The licensee's analytical results were compared to the results
obtained by the NRC mobile laboratory. A total of 147 comparisons of
analytical results were made. The purpose of these measurement
comparisons was to verify the licensee's capability to accurately detect
and identify gamma emitting radionuclides and to quantify their
2
concentrations. Attachment I provides a comparison of the licensee's
results to the NRC's results for each sample. Attachment 2 provides the
criteria for assessing the agreement between the analytical results.
As indicated in Attachment 1, a total of twelve slight disagreements
were noted for three short lived radionuclides in reactor coolant and
containment atmosphere but in general, there was very good agreement
between the licensee's and the NRC's analytical results.
Based on the above comparisons, it was concluded that the licensee had
demonstrated adequate capability to quantify radionuclide concentrations
in various matrices normally encountered in nuclear power plant
operations.
No violations or deviations were identified.
3.
Radiological Environmental Monitoring Program (84750)
Technical Specification (TS) 6.4.7 required the licensee to establish,
implement, and maintain a program to monitor the radiation and
radionuclides in the environs of the plant as described in Chapter 16 of
the Final Safety Analysis Report (FSAR). The sampling locations, types
of samples or measurements, sampling frequency, types and frequency of
sample analysis, reporting levels, and analytical lower limits of
detection (LLDs) were specified in FSAR section 16.11-6. TS 6.6.1.5 and
FSAR section 16.11-10 delineated the requirements for submitting, the
submittal dates, and the content of the Annual Radiological
Environmental Operating Reports. The reports were required to be
submitted prior to May 1 of each year and to provide an assessment of
the observed impact on the environment resulting from plant operations
during the previous calendar year.
Subsequent to this inspection, the inspector reviewed the licensee's
1993 Annual Radiological Environmental Operating Report and the results
of that review are included herein. The report was submitted on
April 25, 1994, and included the following: a description of the
program, a summary and discussion of the results for each exposure
pathway, analysis of trends and comparisons with previous years and
preoperational studies, and an assessment of the impact on the
environment resulting from plant operations. The report also included
the results of the Land Use Census and the results of the
Interlaboratory Comparison Program.
Dose estimates calculated from environmental monitoring program data
were in reasonable agreement with dose estimates calculated from
effluent data and were within 40 CFR 190 dose limits. The reports
summary section indicated that the contribution to the environmental
radioactivity resulting from plant operations was small and had no
significant radiological impact on the health and safety of the general
public.
3
Based on the above review, it was concluded that the licensee had
complied with the sampling, analytical, and reporting program
requirements and that the radiological environmental monitoring program
had been effectively implemented.
No violations or deviations were identified.
4.
Environmental Monitoring Quality Assurance Program (84750)
TS 6.4.7.c and FSAR section 16.11-6 required the licensee to participate
in an interlaboratory comparison program and to include a summary of the
program results in the Annual Radiological Environmental Operating
Report. The licensee's report for 1993 provided a summary of the results
from the licensee's participation in the Environmental Protection
Agency's (EPA's) Environmental Monitoring Systems Laboratory
Intercomparison Program. The report also included descriptions of the
various types of samples analyzed and the analyses performed, and an
evaluation of the analytical results. A total of 27 samples were
analyzed, none of which exceeded the EPA control limits.
Based on the licensee's overall performance in the EPA crosscheck
program, it was concluded that an effective quality assurance program
had been maintained for analysis of environmental samples.
No violations or deviations were identified.
5.
State Radiological Environmental Monitoring (84750)
The State of South Carolina's Department of Health and Environmental
Control (DHEC), by contract with the NRC, independently monitors the
concentrations of radioactivity in the environs of the licensee's
facility and provides an annual report of the results from the
monitoring program. The inspector reviewed the DHEC for 1993 and noted
that there were no anomalies between the DHEC's program data and the
licensee's program data. The range of radioactivity concentrations
observed by the DHEC were comparable to the licensee's data.
6.
Exit Interview
The inspection scope and results were summarized on September 21, 1994,
with those persons indicated in Paragraph 1. The inspector described the
areas inspected and discussed in detail the inspection results listed
above. No dissenting comments were received from the licensee.
Proprietary information is not contained in this report.
ATTACHMENT 1
COMPARISON OF NRC AND OCONEE ANALYTICAL RESULTS
September 20-21, 1994
Type of Sample: Reactor Coolant (Unit 2)
Sample Container: NRC
50 ml bottle
Oconee
50 ml bottle (different geometry)
Radio-
Licensee's
Reso
nuclide
Value
NRC Value
lution Ratio
Comparison
Detector #3
CS-134
3.71E-03
4.09E-03 +- 2.90E-04
14
0.91
Agree
8.36E-03
6.71E-03 +- 6.14E-04
11
1.24
Agree
1-131
6.63E-02
7.25E-02 +- 9.97E-04
73
0.91
Agree
1-132
1.06E-01
1.51E-01 +- 3.35E-03
45
0.70
Agree
1-133
1.37E-01
1.46E-01 +- 1.89E-03
77
0.94
Agree
1-134
1.38E-01
2.71E-01 +- 4.91E-03
55
0.51
Disagree
1-135
1.27E-01
1.49E-01 +- 3.99E-03
37
0.85
Agree
Detector #4
CS-134
5.30E-03
4.09E-03 +- 2.90E-04
14
1.30
Agree
6.71E-03
6.71E-03 +- 6.14E-04
11
1.00
Agree
1-131
6.14E-02
7.25E-02 +- 9.97E-04
73
0.85
Agree
1-132
1.00E-01
1.51E-01 +- 3.35E-03
45
0.66
Disagree
1-133
1.34E-01
1.46E-01 +- 1.89E-03
77
0.92
Agree
1-134
8.02E-02
2.71E-01 +- 4.91E-03
55
0.30
Disagree
1-135
1.25E-01
1.49E-01 +- 3.99E-03
37
0.84
Agree
Detector #6
CS-134
3.66E-03
4.09E-03 +- 2.90E-04
14
0.89
Agree
5.79E-03
6.71E-03 +- 6.14E-04
11
0.71
Agree
1-131
6.13E-02
7.25E-02 +- 9.97E-04
73
0.84
Agree
1-132
1.11E-01
1.51E-01 +- 3.35E-03
45
0.74
Disagree
1-133
1.39E-01
1.46E-01 +- 1.89E-03
77
0.95
Agree
1-134
1.13E-01
2.71E-01 +- 4.91E-03
55
0.42
Disagree
1-135
1.16E-01
1.49E-01 +- 3.99E-03
37
0.78
Agree
ATTACHMENT 1 (Continued)
Type of Sample: Reactor Coolant (Unit 3)
Sample Container: NRC
50 ml bottle
Oconee
50 ml bottle (different geometry)
Radio-
Licensee's
Reso
nuclide
Value
NRC Value
lution Ratio
Comparison
Detector #3
CS-134
5.11E-03
6.66E-03 +- 4.65E-04
14
0.77
Agree
2.34E-02
1.93E-02 +- 1.19E-03
16
1.21
Agree
1-131
1.01E-01
9.77E-02 +- 1.28E-03
76
1.03
Agree
1-132
2.OOE-01
2.55E-01 +- 5.03E-03
51
0.78
Agree
1-133
1.92E-01
1.77E-01 +- 2.95E-03
60
1.08
Agree
1-134
2.41E-01
4.34E-01 +- 7.22E-03
76
0.55
Disagree
1-135
2.OOE-01
2.15E-01 +- 5.60E-03
38
0.93
Agree
NA-24
1.62E-02
1.56E-02 +- 1.16E-03
13
1.04
Agree
Detector #4
CS-134
5.02E-03
6.66E-03 +- 4.65E-04
14
0.75
Agree
2.15E-02
1.93E-02 +- 1.19E-03
16
1.11
Agree
1-131
9.52E-02
9.77E-02 +- 1.28E-03
76
0.97
Agree
1-132
2.10E-01
2.55E-01 +- 5.03E-03
51
0.82
Agree
1-133
1.78E-01
1.77E-01 +- 2.95E-03
60
1.01
Agree
1-134
2.30E-01
4.34E-01 +- 7.22E-03
76
0.53
Disagree
1-135
2.11E-01
2.15E-01 +- 5.60E-03
38
0.98
Agree
NA-24
1.77E-02
1.56E-02 +- 1.16E-03"
13
1.13
Agree
Detector #6
CS-134
6.69E-03
6.66E-03 +- 4.65E-04
14
1.00
Agree
1.90E-02
1.93E-02 +-
1.19E-03
16
0.98
Agree
1-131
9.03E-02
9.77E-02 +- 1.28E-03
76
0.92
Agree
1-132
1.94E-01
2.55E-01 +- 5.03E-03
51
0.76
Disagree
1-133
1.72E-01
1.77E-01 +- 2.95E-03
60
0.97
Agree
1-134
2.45E-01
4.34E-01 +- 7.22E-03
76
0.56
Disagree
1-135
1.96E-01
2.15E-01 +- 5.60E-03
38
0.91
Agree
NA-24
1.71E-02
1.56E-02 +- 1.16E-03
13
1.09
Agree
ATTACHMENT 1 (Continued)
Type of Sample: Containment Atmosphere (Unit 3)
Sample Container: NRC
1250 ml Marinelli beaker
Oconee
4400 ml Marinelli beaker
Radio-
Licensee's
Reso
nuclide
Value
NRC Value
lution Ratio
Comparison
Detector #1
AR-41
1.55E-06
2.60E-06 +- 2.12E-07
12
0.60
Agree
KR-85M
1.49E-06
1.17E-06 +- 1.15E-07
19
0.68
Agree
KR-88
1.43E-06
2.37E-06 +- 2.58E-07
9
0.60
Agree
1.92E-03
2.40E-03 +- 3.97E-05
60
0.80
Agree
XE-133M
1.58E-05
1.73E-05 +- 7.18E-07
24
0.91
Agree
XE-135
2.29E-05
2.81E-05 +- 3.02E-07
93
0.81
Agree
Detector #2
AR-41
1.74E-06
2.60E-06 +- 2.12E-07
12
0.66
Agree
KR-85M
1.53E-06
2.17E-06 +- 1.15E-07
19
0.70
Agree
KR-88
1.27E-06
2.37E-06 +- 2.58E-07
9
0.53
Disagree
2.04E-03
2.40E-03 +- 3.97E-05
60
0.85
Agree
XE-133M
1.69E-05
1.73E-05 +- 7.18E-07
24
0.98
Agree
XE-135
2.48E-05
2.81E-05 +- 3.02E-07
93
0.88
Agree
Detector #3
AR-41
1.86E-06
2.60E-06 +- 2.12E-07
12
0.72
Agree
KR-85M
1.62E-06
2.17E-06 +- 1.15E-07
19
0.75
Agree
KR-88
1.27E-06
2.37E-06 +- 2.58E-07
9
0.54
Disagree
2.06E-03
2.40E-03 +- 3.97E-05
60
0.86
Agree
XE-133M
1.62E-05
1.73E-05 +- 7.18E-07
24
0.94
Agree
XE-135
2.48E-05
2.81E-05 +- 3.02E-07
93
0.88
Agree
Detector #4
AR-41
1.69E-06
2.60E-06 +- 2.12E-07
12
0.65
Agree
KR-85M
1.65E-06
2.17E-06 +- 1.15E-07
19
0.76
Agree
KR-88
1.51E-06
2.37E-06 +- 2.58E-07
9
0.64
Agree
1.95E-03
2.40E-03 +- 3.97E-05
60
0.81
Agree
XE-133M
1.61E-05
1.73E-05 +- 7.18E-07
24
0.93
Agree
XE-135
2.47E-05
2.81E-05 +- 3.02E-07
93
0.88
Agree
ATTACHMENT 1 (Continued)
Type of Sample: Containment Atmosphere (Unit 3) (Continued)
Sample Container: NRC
1250 ml Marinelli beaker
Oconee
4400 ml Marinelli beaker
Radio-
Licensee's
Reso
nuclide
Value
NRC Value
lution Ratio
Comparison
Detector #5
AR-41
1.77E-06
2.60E-06 +- 2.12E-07
12
0.68
Agree
KR-85M
1.58E-06
2.17E-06 +- 1.15E-07
19
0.73
Agree
KR-88
1.58E-06
2.37E-06 +- 2.58E-07
9
0.67
Agree
2.23E-03
2.40E-03 +- 3.97E-05
60
0.93
Agree
XE-133M
1.56E-05
1.73E-05 +- 7.18E-07
24
0.90
Agree
XE-135
2.41E-05
2.81E-05 +- 3.02E-07
93
0.86
Agree
Detector #6
AR-41
1.70E-06
2.60E-06 +- 2.12E-07
12
0.65
Agree
KR-85M
1.49E-06
2.17E-06 +- 1.15E-07
19
0.68
Agree
KR-88
1.29E-06
2.37E-06 +- 2.58E-07
9
0.54
Disagree
1.97E-03
2.40E-03 +- 3.97E-05
60
0.82
Agree
XE-133M
1.47E-05
1.73E-05 +- 7.18E-07
24
0.85
Agree
XE-135
2.29E-05
2.81E-05 +- 3.02E-07
93
0.81
Agree
ATTACHMENT 1 (Continued)
Type of Sample: Liquid Radwaste
Sample Container: NRC
1000 ml Marinelli beaker
Oconee
3500 ml Marinelli beaker
Radio-
Licensee's
Reso
nuclide
Value
NRC Value
lution Ratio
Comparison
Detector #1
AG-I1M
6.91E-07
6.49E-07 +- 9.36E-08
7
1.06
Agree
CO-58
1.10E-06
1.13E-06 +- 1.11E-07
10
0.97
Agree
1-131
2.82E-06
3.22E-06 +- 1.93E-07
17
0.88
Agree
1-133
5.66E-07
5.78E-07 +- 5.76E-08
10
0.98
Agree
Detector #2
AG-110M
7.04E-07
6.49E-07 +- 9.36E-08
7
1.08
Agree
CO-58
1.10E-06
1.13E-06 +- 1.11E-07
10
0.97
Agree
1-131
3.08E-06
3.22E-06 +- 1.93E-07
17
0.96
Agree
1-133
4.49E-07
5.78E-07 +- 5.76E-08
10
0.78
Agree
Detector #3
.
AG-110M
8.14E-07
6.49E-07 +- 9.36E-08
7
1.25
Agree
CO-58
1.14E-06
1.13E-06 +- 1.11E-07
10
1.01
Agree
1-131
3.08E-06
3.22E-06 +- 1.93E-07
17
0.96
Agree
1-133
5.53E-07
5.78E-07 +- 5.76E-08
10
0.96
Agree
Detector #4
AG-110M
7.26E-07
6.49E-07 +- 9.36E-08
7
1.12
Agree
CO-58
9.04E-06
1.13E-06 +- 1.11E-07
10
0.80
Agree
1-131
3.10E-06
3.22E-06 +- 1.93E-07
17
0.96
Agree
1-133
4.69E-07
5.78E-07 +- 5.76E-08
10
0.81
Agree
Detector #5
AG-110M
5.86E-07
6.49E-07 +- 9.36E-08
7
0.90
Agree
CO-58
1.12E-06
1.13E-06 +- 1.11E-07
10
0.99
Agree
1-131
2.72E-06
3.22E-06 +- 1.93E-07
17
0.84
Agree
1-133
5.05E-07
5.78E-07 +- 5.76E-08
10
0.87
Agree
Detector#6
AG-I1M
6.73E-07
6.49E-07 +- 9.36E-08
7
1.04
Agree
CO-58
1.02E-06
1.13E-06 +- 1.11E-07
10
0.90
Agree
1-131
2.85E-06
3.22E-06 +- 1.93E-07
17
0.88
Agree
1-133
5.08E-07
5.78E-07 +- 5.76E-08
10
0.88
Agree
ATTACHMENT 1 (Continued)
Type of Sample: Particulate Filter
Radio-
Licensee's
Reso
nuclide
Value
NRC Value
lution Ratio
Comparison
Detector #1
2.82E-10
3.29E-10 +- 4.67E-11
7
0.86
Agree
1-131
5.12E-10
5.52E-10 +- 3.51E-11
16
0.93
Agree
1-133
4.34E-10
5.34E-10 +- 4.18E-11
13
0.81
Agree
Detector #2
1.98E-10
3.29E-10 +- 4.67E-11
7
0.60
Agree
1-131
4.64E-10
5.52E-10 +- 3.51E-11
16
0.84
Agree
1-133
4.14E-10
5.34E-10 +- 4.18E-11
13
0.78
Agree
Detector #3
2.08E-10
3.29E-10 +- 4.67E-11
7
0.63
Agree
1-131
4.70E-10
5.52E-10 +- 3.51E-11
16
0.85
Agree
1-133
3.35E-10
5.34E-10 +- 4.18E-11
13
0.63
Agree
Detector #4
2.82E-10
3.29E-10 +- 4.67E-11
7
0.86
Agree
1-131
4.16E-10
5.52E-10 +- 3.51E-11
16
0.75
Agree
1-133
3.78E-10
5.34E-10 +- 4.18E-11
13
0.71
Agree
Detector #5
2.35E-10
3.29E-10 +- 4.67E-11
7
0.71
Agree
1-131
4.46E-10
5.52E-10 +- 3.51E-11
16
0.81
Agree
1-133
3.99E-10
5.34E-10 +- 4.18E-11
13
0.75
Agree
Detector #6
2.33E-10
3.29E-10 +- 4.67E-11
7
0.71
Agree
1-131
4.63E-10
5.52E-10 +- 3.51E-11
16
0.84
Agree
1-133
4.34E-10
5.34E-10 +- 4.18E-11
13
0.81
Agree
ATTACHMENT I (Continued)
Type of Sample: Silver Zeolite Cartridge
Radio-
Licensee's
Reso
nuclide
Value
NRC Value
lution Ratio
Comparison
Detector #1
1-131
1.06E-08
1.06E-08 +- 1.38E-10
77
1.00
Agree
1-132
8.21E-10
7.48E-10 +- 6.46E-11
12
1.10
Agree
1-133
4.99E-09
4.74E-09 +- 1.14E-10
42
1.05
Agree
1-135
2.14E-09
1.83E-09 +- 2.04E-10
9
1.17
Agree
Detector #2
1-131
9.85E-09
1.06E-08 +- 1.38E-10
77
0.93
Agree
1-132
<2.16E-9
7.48E-10 +- 6.46E-11
12
1-133
4.80E-09
4.74E-09 +- 1.14E-10
42
1.01
Agree
1-135
1.94E-09
1.83E-09 +- 2.04E-10
9
1.06
Agree
Detector #3
1-131
9.95E-09
1.06E-08 +- 1.38E-10
77
0.94
Agree
1-132
<2.42E-9
7.48E-10 +- 6.46E-11
12
1-133
4.69E-09
4.74E-09 +- 1.14E-10
42
0.99
Agree
1-135
2.40E-09
1.83E-09 +- 2.04E-10
9
1.31
Agree
Detector #4
1-131
1.01E-08
1.06E-08 +- 1.38E-10
77
0.95
Agree
1-132
8.49E-10
7.48E-10 +- 6.46E-11
12
1.14
Agree
1-133
4.73E-09
4.74E-09 +- 1.14E-10
42
1.00
Agree
1-135
2.23E-09
1.83E-09 +- 2.04E-10
9
1.22
Agree
Detector #5
1-131
1.OOE-08
1.06E-08 +- 1.38E-10
77
0.94
Agree
1-132
7.06E-10
7.48E-10 +- 6.46E-11
12
0.94
Agree
1-133
4.73E-09
4.74E-09 +- 1.14E-10
42
1.00
Agree
1-135
1.92E-09
1.83E-09 +- 2.04E-10
9
1.05
Agree
Detector #6
1-131
9.79E-09
1.06E-08 +- 1.38E-10
77
0.92
Agree
1-132
4.99E-10
7.48E-10 +- 6.46E-11
12
0.67
Agree
1-133
4.92E-09
4.74E-09 +- 1.14E-10
42
1.04
Agree
1-135
2.27E-09
1.83E-09 +- 2.04E-10
9
1.24
Agree
ATTACHMENT 2
CRITERIA FOR COMPARISONS OF ANALYTICAL MEASUREMENTS
This attachment provides criteria for the comparison of results of
analytical radioactivity measurements. These criteria are based on
empirical relationships which combine prior experience in comparing
radioactivity analyses, the measurement of the statistically random
process of radioactive emission, and the accuracy needs of this program.
In these criteria, the "Comparison Ratio Limits"' denoting agreement or
disagreement between licensee and NRC results are variable. This
variability is a function of the ratio of the NRC's analytical value
relative to its associated statistical and analytical uncertainty,
referred to in this program as "Resolution"2 .
For comparison purposes, a ratio between the licensee's analytical value
and the NRC's analytical value is computed for each radionuclide present
in a given sample. The computed ratios are then evaluated for agreement
or disagreement based on "Resolution." The corresponding values for
"Resolution" and the "Comparison Ratio Limits" are listed in the Table
below. Ratio values which are either above or below the "Comparison
Ratio Limits" are considered to be in disagreement, while ratio values
within or encompassed by the "Comparison Ratio Limits" are considered to
be in agreement.
TABLE
NRC Confirmatory Measurements Acceptance Criteria
Resolution vs. Comparison Ratio Limits
Comparison Ratio Limits
Resolution
for Agreement
<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
'Comparison Ratio = Licensee Value
NRC Reference Value
2Resolution = NRC Reference Value
Associated Uncertainty