IR 05000369/1987001
| ML20207T207 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, McGuire  |
| Issue date: | 01/27/1987 |
| From: | Kahle J, Kuzo G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20207T191 | List: |
| References | |
| 50-369-87-01, 50-369-87-1, 50-370-87-01, 50-370-87-1, NUDOCS 8703230307 | |
| Download: ML20207T207 (13) | |
Text
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. UNITED STATES f
- o NUCLEAR REGULATORY COMMISSION
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101 MARIETTA STREET N.W.
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TEB 2 41997 Report Nos.: 50-369/87-01,50-370/87-01 Licensee: Duke Power Company 422 South Church Street Charlotte, NC 28242 Docket Nos.: 50-369, 50-370 License Nos.: NPF-9, NPF-17 Facility Name: McGuire Nuclear Station Inspection Conducted: January 5-9, 1987 Inspector:
tynt b bo M hm N G.B.Kuzg Date(Signed Accompanying Personnel:
G. Froemsdorf J. Kahle b[db[tb
/ Jt 7/R 7 Approved by:
J.fB.
ahle, Section Chief
'Date' Signed Emer ncy Preparedness and Radiological tection Branch Division of Radiation Safety and Safeguards SUMMARY Scope:
This routine unannounced inspection involved onsite review of effluent measurement quality control and confirmatory measurements including review of the laboratory quality control program; review of procedures and instructions; review of quality control records and logs, review of the counting room facilities; and comparison of radiological verification results between the licensee and the NRC laboratory facilities.
Results:
One violation was identified - failure to conduct accurate Fe-55 analyses for liquid effluent measurements.
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REPORT DETAILS 1.
Persons Contacted Licensee Employees
- T. L. McConnell, Station Manager
- B. H. Hamilton, Technical Services, Superintendent J. W. Foster, Station Health Physicist
- W. F. Byrum, Health Physics Coordinator L. K. Criminger, Health Physics Specialist
- C. D. Martinec, Junior Health Physicist
- E. O. McCraw, Compliance Engineer
- N. G. Atherton, Compliance, Associate Chemist
- R. E. Sorber, Health Physicist, General Office
- M. J. Geer, Health Physicist, General Office Other licensee employees contacted included technicians and office personnel.
NRC Resident Inspectors
- W. T. Orders
'S. F. Guenther
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on January 12, 1987, with those persons indicated in Paragraph 1 above.
One violation concerning inadequate Fe-55 analyses (Paragraph 8.b) was discussed.
Licensee management representatives acknowledged the inspector's comments and expressed no contrary opinions.
The licensee did not identify as proprietary any of the material provided to or reviewed by the inspector during this inspection.
3.
Licensee Action on Previous Enforcement Matters (Closed)URI 50-369,-370/86-32-06:
Licensee capability to perform accurate Fe-55 analyses.
The inspector reviewed the most recent Fe-55 verification sample results and discussed previous concerns regarding this item.
These findings are documented as a potential violation in Paragraph 8.b of this report.
4.
Laboratory Quality Control Program (84725)
The inspector reviewed selected portions of the effluent measurements Quality Assurance (QA) program with cognizant licensee representatives and determined that organizational structure and program management had not
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changed since a previous inspection (IE 50-369/83-34,50-370/83-52).
The inspector noted that program implementation met the general guidance of Regulatory Guide 4.15, " Quality Assurance for Radiological Monitoring Programs," with respect to the radioactive effluent measurements program.
No violations or deviations were identified.
5.
Audits (84725)
Technical Specification (TS) 6.5.2.9 states audits of unit activities shall be performed under the cognizance of the Nuclear Safety Review Board (NSRB)
encompassing conformance of unit operation to provisions contained with the TSs and applicable license conditions at least once per 12 months; the Radiological Environmental Monitoring Program and the results thereof at least once per 12 months; the offsite Dose Calculation Manual and implementing procedure at least once per 24 months; and the performance of activities required by the Quality Assurance Program for effluent and environmental monitoring at least once per 12 months.
The inspector reviewed the following audit report, Departmental Audit NP-86-5(MC), dated March 21,1986.
The inspector noted that the radiological measurements program area was audited against applicable sections of the Technical Specifications, approved plant operating procedures and manuals, and Regulatory Guides.
Audits addressed both technical concerns, quality assurance issues, and surveillance requirements regarding the radiochemical effluent measurements program.
The inspector noted that identified issues concerning the effluent measurements program were adequately reviewed and appropriate corrective actions completed in a timely manner.
No violations or deviations were identified.
6.
Procedures (84725)
Technical Specification 6.8.1 requires written precedures to be established, implemented and maintained covering the applicable procedures recommended in
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Appendix "A" of Regulatory Guide 1.33, Rev. 2, February 1978; and the t
Quality Assurance Program for effluent and environmental monitoring.
The inspector reviewed selected portions of the following procedures:
a.
McGuire Health Physics Manual Section 8, HP Routines - Gaseous Sampling, 10/13/86.
b.
HP-0-B-1001-10, Quality Assurance for ND6600 Gamma-Ray Spectroscopy System,3/28/86, c.
HP-0-B-1001-19, Calibration and Quality Assurance for the ND 6600 Gamma-Ray Spectroscopy System, 9/25/86.
d.
HP-0-B-1001-20, Calibration, Quality Assurance & Parameters for Set-up for Beckman LS-5800 Series Liquid Scintillation Counter, 4/15/86 l
e.
HP-0-B-1003-07, Preparation of Count Room Standards, 7/2/86.
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. HP-0-B-1003-03, Radioactive Gaseous Waste Releases (GWR), 8/22/86.
g.
PT-08-4600-19 Radioactive Gaseous Effluent Sampling and Analysis Frequency,8/22/86.
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h'.
PT-08-4600-18, Radioactive Liquid Effluent Sampling and Analysis I
Frequency,10/1/86.
The inspector.noted that procedures were being reviewed and approved in accordance with established procedures.
Procedures were reviewed and i
specific items discussed with cognizant licensee representatives as follow.
Technical Specification compliance with lower limit of detection' limits (LLD) for radiological measurements.
The licensee has procedural controls to ensure compliance with TS LLD requirements for liquid and
gaseous effluents.
- Licensee actions to routinely correct for pressure differential between main gaseous effluent stream and offline sampling systems.
Licensee procedures correct for pressure differential during sampling of
- gaseous effluent streams.
No violations or deviations were identified.
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7.
Records (84725)
a.
The inspector reviewed selected portions of the following records:
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(1) Beckman 1800 Liquid Scintillation Counter Nos. MCHHPS-26470 and 26552 Quality Control Logs for January 1986 - January 1987
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including:
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1.
H-3, C-14 Daily Performance & Background Data Sheets 11.
Perfonnance Graphs
iii.
Quench Curve Coefficients and Quench Limits
iv.
Efficiency Value Determinations i
v.
Tritium & Gross Beta Calibration Verification vi.
Equipment Status Logs l
(2) Tennelec LB-5100 Automatic Proportional Counter (Detector
No. 26012) and Tencelec Automatic GM Counter (Detector no. 26354)
Log Book Records for December 1985 - January 1987 including:
i.
Daily Performance & Background Checks
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11.
Performance Graph iii.
Check Source Data Sheet iv.
Efficiency & Monthly Performance Determination v.
Voltage Plateau Charts i
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(3) Gamma Spectroscopy Detector (System Nos. A-26537, B-26456, C-26471
& D-26404) Quality Control Logs for December 1986 - January 1987 including:
1.
Daily Performance Logs 11.
Performance Graph 111.
Monthly Performance Worksheet iv.
Energy Calibration and Energy Resolution Checks (4) 1986 Calibration Verification Records including Intralaboratory Cross Check Worksheets and Gas Percent Difference Worksheets.
(5) 1986 Efficiency Calibration Data for Gamma Spectroscopy System Nos. A, B, C, and D including the following geometries:
12 cc Gas Vial,100 cc Gas Bomb, 4400 cc Gas Marinelli, 50 ml Bottle, 3500 ml Marinelli, 47 m Particulate Filter, and Face-loaded Charcoal Cartridge.
(6)
1986 Standard Radionuclide Source Certificates (7) 1986 Interstation Cross Check Program Results, for the following analyses:
1.
Gamma in Water, Charcoal Cartridge ii.
Body Burden Analyses iii.
Alpha / Beta Swipes (8) 1986 Gas Decay Tank Release Reports Results of the record review were discussed with cognizant licensee representatives as noted in Paragraph 7.a-b.
b.
Following the previous NRC Confirmatory Measurement Inspection at MNS (Inspection Report No. 50-369/85-17 and 50-370/85-18) licensee representatives reviewed and recalibrated gaseous effluent geometries.
Use of these recalibrated geometries resulted in improved agreement between the licensee and NRC split sample results for gaseous effluent
- neasurements during this present inspection (Paragraph 8.a).
c.
The inspector discussed the use of liquid scintillation counting quench corrections with cognizant licensee representatives.
Licensee personnel appeared knowledgeable and understood the bases for quench corrections.
Licensee methodology was consistent with accepted industry practices.
No violations or deviations were identified.
8.
Confirmatory Measurements (84725)
a.
During the inspection, reactor coolant and selected liquid and gaseous plant effluent process streams were sampled and the resultant sample
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matrices analyzed for radionuclide concentrations using licensee and NRC Region II Laboratory gamma-ray spectroscopy systems.
The purpose of these comparative measurements was to verify the licensee's capability to measure radionuclides accurately in various plant systems.
Analyses were conducted utilizing as many of the licensee's gama spectroscopy systems as practicable.
Sample types and counting geometries included the following:
reactor coolant system (RCS) sample
- 50 ml bottle; liquid waste - 3500 ml marinelli; and gaseous waste -
12 cc vial, 100 cc gas bomb and 4400 cc marinelli.
Spiked particulate filter and charcoal cartridge sample types were provided for analyses in lieu of licensee samples which did not have sufficient levels of activity for analy(sis. Attachment 1) with the acceptance criteria listed in Comparison of licensee and NRC results are listed in Table 1 Attachment 2.
In general, results were in agreement for the various effluent samples split and analyzed by the licensee and NRC. Only the 100 cc bomb Waste Gas Decay Tank sample analyzed using(biased)
Gamma Spectroscopy System B, indicated a possible inaccurate measurement, three of five nuclide values being in disagreement.
From discussion with cognizant licensee representatives and review of licensee waste gas release records the inspector noted that this detector was not used for gaseous effluent analyses.
The inspector suggested that the use of Gamma Spectroscopy System B for 100 cc gas geometry analyses should be administratively prevented until gas recalibrations can be conducted.
There were no additional comments regarding the onsite gamma spectroscopy analyses.
b.
The inspector noted that the licensee was provided with a simulated liquid waste sample by the NRC contract laboratory in September 1986 and was requested to complete radiochemical analyses for H-3, Fe-55, Sr-89, and Sr-90 concentrations.
Comparison of licensee and NRC results are listed in Table 2 (Attachment 1) with the acceptance criteria listed in Attachment 2.
Results were in agreement for H-3 and Sr-90 analyses and disagreement for Fe-55 and Sr-89 analyses.
The inspector noted that both the Fe-55 and Sr analyses are conducted by a licensee approved vendor laboratory.
Furthermore, Fe-55 results for NRC required verification analyses conducted by the vendor laboratory since 1985 have been in disagreement with known values (four samples, reported concentrations ranging from approximately 30 to 60 percent above the known values).
The inspector noted that DPC corporate licensee personnel conducted a technical review of the vendor laboratory radiochemistry methodology in October 1985.
The review detailed procedural inaccuracies regarding spiked Fe-55 samples and concerns regarding background estimates for analyses of low level samples.
The inspector noted that this licensee review and vendor corrective actions regarding the inaccurate measurements have failed to adequately correct the observed bias.
10 CFR 20.201(b) requires the licensee to conduct adequate surveys for radioactive effluents necessary to demonstrate compliance with release limits and to evaluate the extent of radiation hazards that may be present.
MNS TS Table 4.11-1 required Fe-55 analyses of selected radioactive liquid wastes discharges.
TS 6.8.1.a required written procedures be
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established, implemented and maintained covering the applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Rarision 2, February 1978.
The inspector informed licensee representatives that the failure to conduct accurate Fe-55 analyses for liquid effluents was considered a potential violation of Technical
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Specification and 10 CFR 20.201(b) requirements.
Violation:
50-369/87-01-01. 50-370/87-01-01.
Failure to ensure actequate procedures to conduct accurate Fe-55 analyses for liquid effluent release measurements.
9.
Review of Counting Room Facilities and Staffing Changes (84725)
The inspector toured the counting room facilities and discussed changes to equipment and personnel since the previous confirmatory measurements ins action (Inspection Report No. 50-369/85-17, 50-370/85-18).
An additional qualified staff member has been assigned to the counting room to perform routine counting room analyses. New counting equipment in operation inc.tuded an additional liquid scintillation counting system.
Licensee personnel presently are training and preparing procedures for use with updated gamma spectroscopy analysis systems which will replace the present systems in the counting room at a future date.
In addition, another Alpha / Beta LB 5100 Proportional Counter should be operational in the near fu"ure.
Nc violations or deviations were identified.
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ATTACHMENT 1
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TABLE 1
RESULTS OF CAP 94A SPECTROSCOPY CONFIRMATORY MEASUREMENTS AT HCCUlRE NUCLEAR STATION, JANUARY 5-9, 1987 SAMPLE TYPE ISOT05 CONCENTRATION fuci/Uniti RESOLUTION RATIO COMPARISON (Licensee Geometry)
Licensee
.NRC Licensee /NRC (1) REACTOR COOLANT CO-58 1.23 E-3 1'24 1 0.10 E-3
0.99 Ag reement (50 ml Bottle)
1-131 6.28 E-S 6.22 1 0.14 E-3
1.01 Ag reement I-132 1.16 E-2 1.23 1 0.03 E-2
0.94 Ag reement I-133 1.44 E-2 1.56 1 0.02 E-2
0.92 Agreement
1-135 1.58 E-2 1.65 1 0.06 E-2
0.96 Ag reement Cs-134 3.71 E-4 5.95 1 0.77 E-4
0.62 Ag reement Cs-137 6.94 E-4 6.32 1 0.73 E-4
1.10 Ag reement (2) REACTOR COOLANT Co-58 1.00 E-3 1.24 1 0.10 E-3
0.81 Ag reement (50 ml Bottle)
1-131 5.43 E-3 6.22 1 0.14 E-3
0.87 Agreement 1-132 1.14 E-2 1.23 i O.03 E-2
0.93 Ag reement 1-133 1.45 E-2 1.56 1 0.02 E-2
0.93 Ag reement 1-135 1.45 E-2 1.65 1 0.06 E-2
0.88 Ag reement Cs-134 4.52 E-4 5.95 i 0.77 E-4
0.80 Ag reement (3) REACTOR COOLANT Co-58 6.34 E-4 1.24 1 0.10 E-3
0.51 Di sag reement (50 ml Bottle)
1-131 5.70 E-3 6.22 1 0.14 E-3
0.92 Ag reement 1-132 1.27 E-2 1.23 1 0.03 E-2
1.02 Agreement I-133 1.41 E-2 1.56 1 0.02 E-2
0.90 Agreement I-135 1.40 E-2 1.65 1 0.06 E-2
0.85 Ag reement Cs-134 4.66 E-4 5.95 1 0.77 E-4
0.78 Ag reement Cs-137 6.63 E-4 6.32 1 0.73 E-4
1.05 Ag reement (4) REACTOR COOLANT Co-58 8.98 E-4 1.24 1 0.10 E-3
0.80 Ag reement (50 ml Bottle)
1-131 5.96 E-3 6.22 1 0.14 E-3
0.96 Agreement 1-132 1.13 E-2 1.23 i 0.03 E-2
0.92 Ag reement 1-133 1.45 E-2 1.56 1 0.02 E-2
0.93 Agreement l-135 1.49 E-2 1.65 1 0.06 E-2
0.90 Ag reement 0s-134 3.74 E-4 5.95 1 0.77 E-4
0.63 Ag reement Cs-137 5.45 E-4 6.32 1 0.73 E-4
0.86 Ag reement (3) LlQUID WASTE l-131 1.14 E-5 1.12 1 0.02 E-5
1.02 Ag reement ( 3500 ml Ma rinell i 1-133 5.84 E-6 5.86 1 0.18 E-6
1.00 Agreement beaker)
Cs-134 2.65 E-7 2.46 1 0.36 E-7
1.01 Agreement Cs-137 2.93 E-7 2.55 1 0.52 E-7
1.18 Ag reement
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Table 1 (Cont'd)
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i SAMPLE TYPE ISOTOPE COIICEIITRATl006 f uci/Unitt RESOLUTI0ll RATIO COMPARIS0li (Liconsee Geonetry)
Liconsee EG Liconsee/IISC
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(2) LIQUID WASTE l-131 1.18 E-5 1.12 1 0.02-E-5
1.05 Agreement
1 (3500 MI Marinelli 1-133 6.22 E-6 5;86 1 0.18 E-6
1.06 Agreement Ipeaker)
Cs-134 2.49 E-7 2.46 1 0.36 E-7
1.01 Agreement i
Cs-137 3.01 E-7 2.55 1 0.52.E-7
1.18 Agreement i
(2) PARTICULATE FILTER Mn-54 2.40 E-3 2.16 1 0.18 E-3
1.11 Agreement (47 em Filter)
Co-60 2.02 E-2 1.77 1 0.04 E-2
- , 1.14 Agroceent
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Cs-137 1.56 E-2 1.35 1 0.02
,E-2.
>< 1.16 Agreement
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Co-144 4.29 E-3 3.98 1 0.39' E-3
C 1.24
. Agreement
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(3) PARTICULATE FILTER Mn-54 2.09 E-3 2.16 1 0.18 E-3 12.
0.97 Ag reement
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(47 em Filter)
Co-60 1.85 E-2 1.77 i 0.04 E-2
1.04 Agreement
i Cs-137 1.39 E-2 1.35 1 0.02 E-2
1.03 Agreement Ce-144 4.44 E-3 3.98 i 0.39 E-3
1.12 Agreement
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i (1) CHARCOAL CARTRIDGE Co-57 3.53 E-2 3.84 i 0.04 E-2
0.92 Agreement J
(Face-loaded Cartridge)
Co-60 4.56 E-2 4.98 i 0.08 E-2
0.92 Ag reement
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Y-88 9.69 E-2 1.02 1 0.02 E-1
0.95 Agreement Cd-109 1.54 E-0 1.82 1 0.01 E-0 182 0.85-Agreement i
Cs-137 5.60 E-2 5.94 i O.07 E-2
0.94 Agreement
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Ce-139 3.47 E-2 3.78 1 0.06 E-2
0.92 Ag reement
Hg-203 7.08 E-2 8.07 1 0.31 E-2
0.88 Agreement (2) CHARCOAL CARTRIDGE Co-57 3.53 E-2 3.84 1 0.04 E-2
%
0.92 Ag reement
(Face-loaded Cartridge)
Co-60 4.58 E-2 4.98 i 0.08 E-2
0.92 Agreement j
Y-88 9.58 E-2 1.02 1 0.02 E-1
0.94 Agreement
Cd-109 1.60 E-0 1.82 i O.01 E-O 182 0.88 Agreement Cs-137 5.81 E-2 5.94 1 0.07 E-2
0.98 Ag reement
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Ce-139 3.58 E-2 3.78 i 0.06 E-2
0.95 Agreement Hg-203 7.28 E-2 8.07 i O.31 E-2
0.90 Ag reement
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(3) CHARCOAL CARTRIDGE Co-57 3.37 E-2 3.84 i 0.04 E-2
0.88 Agreement (Face-loaded Cartridge)
Co-60 4.47 E-2 4.98 1 0.08 E-2 62-0.90 Agreeeemt Y-88 9.26 E-2 1.02 1 0.02 E-1
0.91 Agreement
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Cd-109 1.57 E-0 1.82 i O.01 E-0 182 0.86 Ag reement Cs-137 5.35 E-2 5.94 1 0.07 E-2
0.90 Agreement
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Co-139 3.16 E-2 3.78 i 0.06 E-2
0.84 Agreement.
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Hg-203 6.46 E-2 8.07 i 0.31-E-2
0.80 Agreement
(0) CHARCOAL CARTRlDGE Co-57 3.45 E-2 3.84 i O.04 E-2
0.90 Ag reement l
(Face-loaded Cartridge)
Co-60 4.38 E-2 4.98 1 0.08 E-2
0.88 Agreement j
Y-88 9.26 E-2 1.02 1 0.02 E-1
0.91 Agreement j
Cd-109 1.57 E-0 1.82 1 0.01 E-O 182 0.86 Agreement
Cs-137 5.43 E-2 5.94 i 0.07 E-2
0.91 Agreement Ce-139 3.25 E-2 3.78 1 0.06 E-2
0.86 Agreement-
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Hg-203 6.91 E-2 8.07 1 0.31 E-2
0.86 Ag. m nt
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Table 1 (Cont' d )
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SAMPLE TYPE ISOTOPE CONCENTRATION f uCl/ Unit 1 RESOLUTI ftATIO COMPARISON (Licensee Geometry)
Licensee 3RQ Licensee /90RC
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(1) WASTE CAS DECAY TANK Kr-85e 1.88 E-3 2.37 1 0.07 E-3
0.79 Agreement
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1100 cc Gas Somb)
K r-88 1.94 E-3 2.57 i O.16 E-3
0.75 Agreement Xe-133e 1.08 E-2 1.35 1 0.03 E-2
0.80 Agreement Xe-133 9.68 E-1 9.42 1 0.008 E-1 1178 1.03 Ag reement
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Xe-135 3.73 E-2 4.26 i 0.01 E-2 426 0.88 Ag reement
(2) WAS1E GAS DECAY TANK Kr-85e 1.66 E-3 2.37 1 0.07 E-3
0.70 Disag reement (100 cc Gas Bomb)
Kr-88 1.59 E-3 2.57 1 0.16 E-3
0.62 Disagreement Xe-133e 9.78 E-3 1.35 1 0.03 E-2
0.72 Disagreement -
Xe-133 9.34 E-1 9.42 1 0.008 E-1 1178 0.99 Agreement Xe-135 3.65 E-2 4.26 1 0.01 E-2 426 0.86 Ag reeeent j
(3) WASTE GAS DECAY TAMK K r-85e 2.24 E-3 2.37 i 0.07 E-3
0.94 Ag reeers.7t
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(100 cc Gas Bomb)
K r-88 2.32 E-3 2.57 i 0.16 E-3
0.90 Agreement Xe-133u 1.31 E-2 1.35 i 0.03 E-2
0.97 Ag reement
Xe-133 9.59 E-1 9.42 1 0.008 E-1 1178 1.02 Ag reement Xe-135 4.22 E-2 4.26 1 0.01 E-2 426 0.99 Agreement
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(4) WASTE GAS DECAY TANK Kr-85e 2.39 E-3 2.37 i 0.07 E-3
1.01 Ag reement (100 cc Gas Bomb)
Kr-88 2.28 E-3 2.57 1 0.16 E-3
0.89 Ag reement Xe-133e 1.30 E-2 1.35 1 0.03 E-2
0.96 Ag reement Xe-133 9.93 E-1 9.42 1 0.008 E-1 1178 1.05 Agreement Xe-135 4.20 E-2 4.26 1 0.01 E-2 426 0.98 Ag reement i
(1) COOLANT GAS Kr-85m 1.33 E-2 1.40 1 0.01 E-2 140 0.95 Ag reement (12 cc Vial)
Kr-87 1.05 E-2 1.33 1 0.02 E-2
0.79 Disagreement Kr-88 2.31 E-2 2.64 1 0.03 E-2
0.88 Agreement Xe-133e 5.44 E-3 5.76 1 0.50 E-3
0.94 Ag reement Xe-133 2.08 E-1 2.23 1 0.005 E-1 446 0.93 Ag reement j
Xe-135 6.06 E-2 6.83 1 0.02 E-2 341 0.89 Ag reement f
(3) COOLANT CAS Kr-85e 1.31 E-2 1.40 1 0.01 E-2 140 0.94 Ag reement
(12 cc Vial)
Kr-87 1.13 E-2 1.33 1 0.02 E-2
0.85 Agreement
Kr-88 2.21 E-2 2.64 1 0.03 E-2
0.84 Agreement Xe-133e 4.78 E-3 5.76 i 0.50 E-3
0.83 Ag reement
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Xe-133 2.15 E-1 2.23 1 0.005 E-1 446 0.96 Agreement Xe-135 7.04 E-2 6.83 1 0.02 E-2 341 1.03 Ag reemen t I
(3) COOLANT GAS Kr-85e 1.29 E-2 1.40 1 0.01 E-2 140 0.92 Ag reement (12 cc Vial)
K r-87 1.09 E-2 1.33 1 0.02 E-2
0.82 Ag reement K r-88 2.28 E-2 2.64 1 0.03 E-2
0.86 Ag reement Xe-133m 4.28 E-3 5.76 1 0.50 E-3
0.84 Ag reement Xe-133 1.97 E-1 2.23 1 0.005 E-1 446 0.88 Ag reement Xe-135 5.71 E-2 6.83 1 0.02 E-2 341 0.83 Di sag reeeemt
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l Table 1 (Cont'd)
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SAMPLE TYPE ISOTOPE CONCENTRATION fuCl/Uniti RESOLUT1086 RATIO COMPARISolf (Licensee Geometry)
Licensee jeRQ Licensee /IIRC
(0) COOLANT GAS K r-85m 1.46 E-2 1.40 1 0.01 E-2 140 1.04-Ag reement (12 cc Vial)
K r-87 1.26 E-2 1.33 1 0.02 E-2
0.95 Ag reement K r-88 2.48 E-2 2.64 1 0.03 E-2
0.94 Ag reement Xe-133m 5.55 E-3 5.76 1 0.50 E-3
0.96 Ag reement Xe-133 2.33 E-1 2.23 1 0.005 E-1 446 1.04 Ag reement Xe-135 6.67 E-2 6.83 1 0.02 E-2 341 0.98 Ag reement (1) GASEOUS EFFLUENT Xe-133 1.46 E-6 1.36 1 0.06 E-6
1.07 Ag reement (4400 cc Marinelli Beaker)
j (2) CASEOUS EFFLUENT Xe-133 1.40 E-6 1.36 1 0.06 E-6
1.03 Agreement j
(4400 cc Marinelli Beaker)
j (3) GASEOUS EFFLUENT Xe-133 1.56 E-6 1.36 1 0.06 E-6
1.15 Agreement (4400 cc Marinelli Beaker)
(4) GASEOUS EFFLUENT Xe-135 1.40 E-6 1.36 i 0.06 E-6
1.03 Ag reement
'
(4400 cc Marinelli Beaker)
'
(1) Analyzed using Licensee Gamma Spectroscopy System No. A-GERM 25-P-2808 (2) Analyzed using Licensee Gamma Spectroscopy System No. B-GERM 24P1160B (3) Analyzed using Licensee Gamma Spectroscopy System No. C-GERM 24-P-1301 (4) Analyzed Using Licensee Gamma Spectroscopy System No. D-GERM 23=P-67WB
t
)
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. _ _
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TABEE 2
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RESULTS OF H-3, SR-89, SR-90, AND FE-55 ANALYSES FOR MCGUIRE NUCLEAR STATION, JANUARY 5-9, 1987*
,
SAMPLE TYPE
' ISOTOPE CONCENTRATION fuCl/ Unit)
RESOLUTION RATIO COMPARISON (Licensee Geometry)
Licensee 3RQ Licensee /NRC Simulated Liquid H-3 2.5 i 0.3 E-5 2.52 1 0.05 E-5
0.99 Agreement waste Fe-55 2.6 1 0.2 E-5 1.87 i 0.04 E-5 48-1.39 D # sag reement S r-89 1.9 1 0.4 E-5 3.17 1 0.10 E-5
0.60 Di sagreement Sr-90 3.3 1 0.1 E-6 3.09 i 0.12 E-6
1.07 Agreement
- Sample provided to McGuire Nuclear Station by MRC Contract Laboratory, September 1986 s
--
-
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4'
ATTACHMENT 2
!
Criteria for Comparing Analytical Measurements
This enclosure 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 judgement limits denoting agreement or disagre'ement
,
between licensee and NRC results are variable. This variability is a function of
the NRC's value relative to its associated uncertainty, referred to in this
'
program as " Resolution"1 increases, the range of acceptable differences between
,
the NRC and licensee values should be more restrictive.
Conversely, poorer i
agreement between NRC and licensee values must be considered acceptable as the
'
resolution decreases.
,
For comparison purposes, a ratio * of the licensee value to the NRC value for each individual nuclide is computed. This ratio is then evaluated for agreement based
'
on the calculated resolution. The corresponding resolution and calculated ratios which denote agreement are listed in Table 1 below.
Values outside of the agreement ratios for a selected nuclide are considered in disagreement.
i
~
2 Resolution = NRC Reference Value for a Particular Nuclide Associated Uncertainty for the Value
8 Comparison Ratio =
Licensee Value
,
.
NRC Reference Value TABLE 1 Confirmatory Measurements Acceptance Criteria Resolutions vs. Comparison Ratio
'
!
I Comparison Ratio for
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Resolution Agreement
<4 0.4 - 2.5
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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
>
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