IR 05000269/1986019
| ML16161A753 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 07/15/1986 |
| From: | Harris J, Kuzo G, Stoddart P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML16161A752 | List: |
| References | |
| 50-269-86-19, 50-270-86-19, 50-287-86-19, NUDOCS 8607300268 | |
| Download: ML16161A753 (13) | |
Text
O ptREG(,
UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA STREET, ATLANTA, GEORGIA 30323
'JUL tj 1986 Report Nos.:
50-269/86-19, 50-270/86-19, and 50-287/86-19 Licensee:
Duke Power Company 422 South Church Street Charlotte, NC 28242 Docket Nos.: 50-269, 50-270, and 50-287 License Nos.:
DPR-38, DPR-47, and DPR-55 Facility Name:
Oconee 1, 2, and 3 Inspection Conducted:
June 23-26, 1986 Inspectors:
/
J. D. Harris O ate 5igned G. B. Kuzo-D 0ate Signed Accompanying Personnel: G. L. Froemsdorf
. Approved by:
P. G. Stoddart, Acting SectiadCh f ate digned Division of Radiation Safety a Safeguards SUMMARY Scope: This routine, unannounced inspection involved onsite review of quality control and confirmatory measurements including:
review of the laboratory quality program; review of chemical and radiochemical procedures; review of quality control records and logs; and comparison of the results of split samples analyzed by the licensee and NRC Region II Mobile Laborator Results: In the areas inspected, no violations or deviations were identifie )
00715 ADOCK PDR
REPORT DETAILS 1. Persons Contacted Licensee Employees
- D. S. Compton, Assistant Engineer
- E. H. Wehrman, Health Physicist
- J. M. Davis, Technical Services
- J. A. Long, Support Functions Coordinator, Health Physics
- T. S. Barr, Technical Services
- S. A. Coy, Health Physicist
- C. T. Yongue, Station Health Physicist D. J. Berkshire, Associate Health Physicist S. Spear, Health Physicist J. Brackett, Senior Quality Assurance Engineer Other licensee employees contacted included several Health Physics Associates, engineers, technicians, operators, mechanics, security force members, and office personne NRC Resident Inspectors J. Bryant
- Attended exit interview Exit Interview The inspection scope and findings were summarized on June 26, 1986, with those persons indicated in Paragraph 1 abov One unresolved item*
concerning gas calibrations was identified (Paragraph 7.a.).
The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspectors during this inspectio.
Laboratory Quality Control Program (84725)
The inspectors reviewed selected portions of the Quality Assurance program with cognizant licensee representatives and determined that organizational structure and program management had not changed since the previous confirmatory measurements inspection (IE 50-269/84-30, 50-270/84-29, and 50-287/84-32). The inspectors 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
- An Unresolved Item is a matter about which more information is required to determine whether it is acceptable or may involve a violation or deviatio monitoring progra The inspectors discussed the laboratory QA program with cognizant licensee representatives and noted that proposed changes included improved QC procedures for counting room instrumentatio These changes will be evaluated during a subsequent inspectio. Audits (84725, 80721)
Technical Specification 6.1.3.4 requires audits of station activities to be conducted under the cognizance of the NSRB encompassing the conformance of station operation to provisions contained within the Technical Specifications and applicable facility operating license conditions at least once per year; the Offsite Dose Calculation Manual and implementing procedures at least once per 24 months; and the Radiological Environmental Monitoring Program and the results thereof at least once per 12 months. The inspector reviewed the following audit reports: Departmental Audit NP-85-4(ON),
Operations and Technical Services Activities, March 1985 Departmental Audit NP-85-20(ON),
Operations and Technical Services Activities, November 1985 c. Departmental Audit NP-86-2(ON),
Operations and Technical Services Activities, February 1986 The inspectors discussed audit results with cognizant licensee representatives and noted the program areas were audited against Technical Specifications, procedural requirements and Regulatory Guide 4.15, "Quality Assurance for Radiological Monitoring Programs (Normal Operations) Effluent Streams and the Environment".
No significant items or adverse trends regarding the present inspection scope were identified in the audit report For those items that were identified, the corrective actions proposed in response to audit findings addressed short term and long term corrective action No violations or deviations were identifie. Procedures (84725, 80721)
Technical Specification 6.4.1 requires the station to be operated and maintained in accordance with approved written procedures with appropriate check-off lists and instructions for the following conditions:
normal startup, operation, and shutdown of the complete facility and of all systems and components involving potential or actual release of radioactivity; personnel radiation protection procedures; and Offsite Dose Calculation Manual implementation. The inspectors reviewed selected portions of the following procedures:
(1) HP/O/B/1000/60A, Waste Gas Decay Tank Sampling and Release Requirements, Rev. 25, February 14, 1986
(2) HP/O/B/1000/60B, Reactor Containment Building Sampling and Release Rate Determination, Rev. 24, February 14, 1986 (3) HP/O/B/1000/60C, Release of Radioactive Waste Through the Liquid Radwaste Effluent Line, Rev. 22, October 21, 1985 (4) HP/O/B/1000/60D, Procedure for Unit Vent, Hot Machine Shop Vent, and Interim Radwaste Building Vent Sampling and Analysis, Rev. 14, February 24, 1986 (5) HP/O/B/1000/60F, Procedure for Correlation of Effluent RIA Monitors, Rev. 6, July 31, 1985 (6) HP/O/B/1000/57, Procedure for Quantifying Airborne Radioactivity, Rev. 7, January 31, 1985 (7) HP/O/B/1000/60Q, Primary to Secondary Leakage Effluent Surveillance, Rev. 11, April 21, 1986 (8) HP/O/B/1000/67, Procedure for Quality Assurance for Radiological Monitoring Systems, Rev. 3, January 10, 1984 (9) HP/O/B/1000/72, Procedure for Removing Dissolved Noble Gases from Tritiated Airborne Samples, Rev. 1, September 24, 1985 (10)
HP/O/B/1000/81, Radiation Protection Practices for Diving in Contaminated Water and/or Near Radioactive Components, Rev. 4, December 9, 1985 (11)
HP/O/B/1000/82, Dose Projections for Untreated Wastes, Rev. 4, January 20, 1986 (12)
HP/O/B/1000/11, Operating Procedure for the Beckman LS-1000 Liquid Scintillation System, Rev. 5, April 25, 1985 (13)
HP/O/B/1000/14, Procedure for Nuclear Data 6600 Operation, Rev. 7, April 3, 1985 (14)
HP/O/B/1000/19, Operating Procedure for the Tennelec LB 5100 Series Low Background Automatic Alpha-Beta Systems, Rev. 1, July 5, 1981 (15)
HP/O/B/1000/22, Procedure for the Operation of the Beckman LS-7500 Liquid Scintillation Counter, Rev. 1, August 13, 1985 (16)
HP/O/B/1000/24, Procedure for Operation of Nuclear Data ND-6 Multichannel Analyzer with Nal Detector, Rev. 1, November 27, 1985 (17)
HP/O/B/1003/01, Calibration Procedure for Thin Window GM Detectors, Rev. 9, April 29, 1986
(18)
HP/O/B/1003/02, Calibration Procedure for the Alpha Scintillation Detector, Rev. 9, April 29, 1986 (19)
HP/0/B/1003/08, Calibration Procedure for the Beckman LS-100 Liquid Scintillation Systems, Rev. 8, June 14, 1985 (20)
HP/0/B/1003/09, Procedure for Calibration of GeLi and IGE Detectors on the Nuclear Data 6600 System, Rev. 6, August 13, 1985 (21)
HP/O/B/1003/10, Calibration Procedure for Tennelec LB 5100 Series Automatic Alpha/Beta Counter, Rev. 2, April 17, 1985 (22)
HP/O/B/1003/12, Calibration Procedure for the ND 6600 System Body Burden Analyzer With Multiple Nal Detectors, Rev. 3, September 11, 1985 (23)
HP/O/B/1003/13, Procedure for Calibration and Parameter Set-up for the Beckman LS-7500 Liquid Scintillation Counter, Rev. 1, June 6, 1985 (24) HP/0/B/1003/15, Calibration Procedure for the ISCO Flow Meter and Sampler Located on the Discharge of Chemical Treatment Pond #3, Rev. 0, April 7, 1986 (25)
HP/O/B/1006/07, Procedure for Preparation of Gas Calibration Sources,
.Rev. 0, July 9, 1981 (26)
HP/O/B/1006/08, Preparation of Tritium Quench Curve and Unknown Standards, Rev. 2, June 10, 1985 (27)
Health Physics Manual Section 5.5, Non-Routine Disposal of Radioactive Material, June 24, 1986 (28)
HP/O/B/1000/54, Plant Radiological Status Guide, May 21, 1986 (29)
CP/0/A/2005/04A, Determination of Tritium Activity by Ion Exchange, Rev. 0, July 7, 1981 The inspector noted that procedures were being reviewed, updated, and approved in accordance with established procedure No violations or deviations were identifie.
Records (84725)
The inspectors reviewed selected portions of the following records:
a. Liquid Scintillation Counter Nos. LS-23-2 and LS-23-4 Quality Control Logs, Trend Charts, and Maintenance Notes for January 1985 to June 1986 including:
(1) 1986 Efficiency Calibration Data
(2) Performance Checks for Gross Beta and Tritium Analysis (3) Quench Correction Data for Tritium Analysis b. Gas Flow Proportional Counter Nos: LB 5110-10-1, LB 5110-10-2, and LB 5110-10-3, Quality Control Logs, Trend Charts, and Maintenance Notes for January 1985 through June 1986 including:
(1) Daily Performance Checks (2) Daily Background Checks (3) Voltage Plateaus (4) Efficiency Calibrations c. Geiger-Mueller Detector Nos. APC-1 and APC-2, Quality Control Logs, Trend Charts, and Maintenance Notes for January 1985 through June 1986 including:
(1) Daily Performance Checks (2) Daily Background Checks (3) Efficiency Calibrations d. Gamma Spectroscopy Detector Systems IGAE, GeLi B, IGCE, GeLi D, GeLi E, and GeLi F, Quality Control Logs, Trend Charts, and Maintenance Notes for January 1985 to June 1986 including:
(1) Daily Performance Checks (2) Daily Resolution Checks (3) Daily Linearity Checks (4) Semi-Annual Efficiency Checks e. Annual 1984, 1985, and 1986 Gamma Spectroscopy Detector Efficiency Calibration Data for Systems IGAE, GeLi B, IGCE, GeLi D, GeLi E, and GeLi F, including the following geometries:
Liter Polybottle, 3500 Liquid Marinelli, 2-inch Particulate Filter, Face-Load Charcoal Cartridge, 15cc Gas Vial, 100cc Gas Marinelli, and 4400cc Gas Marinell f. Gaseous Release Permit Data, January - June 198 g. Software Changes and LLD Calculations for ND 6600 MCA, Memo to Oconee Nuclear Station Files, File No. 768.20, March 13, 198 Interlaboratory, Intralaboratory, and Interstation Crosscheck Results for January 1985 -
June 198 i. ND6 Surveys of Feedwater Heater Disposal, June 24, 198 j. Burial Site Broadleaf Vegetation Sample Results, April 198 Results of the record review were discussed with cognizant licensee representatives as noted belo During the review of the crosscheck program, the inspector noted that a small number of cross-check samples had high counting errors associated with low activity. The licensee acknowledged the inspector's comments and agreed to review this area for possible improvement The licensee used the NRC comparison criteria (see Attachment 1) and showed good overall agreement during the period reviewe The inspector noted the use of informal maintenance notes to help correlate adverse QC checks to overall instrument performanc The inspector noted that more formal guidelines would assist in decisions on when a system needs to be taken out of servic The licensee informed the inspector that this would be reviewed for possible improvements in use of the maintenance lo The inspector had no further question No violations or deviations were note.
Confirmatory Measurements (84725) During the inspection, reactor coolant and selected liquid and gaseous plant effluent process streams were sampled and the resultant sample 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 gamma spectroscopy systems as practicabl Sample types and counting geometries included the following:
50 ml bottle; liquid waste - 3500cc marinelli; and gaseous waste 15cc bottle; 100cc gas bomb; and 4400cc marinell Spiked particulate filter and charcoal cartridge sample types were provided for analysis in lieu of licensee samples which did not have sufficient levels of activity for analysi Comparison of licensee and NRC results are listed in Table 1 with the acceptance criteria listed in Attachment Results were in agreement for all liquid, particulate filter, and charcoal cartridge sample analyse Disagreements were noted for selected nuclides in analyses of gas samples collected using standard plant operating procedure For Xe-133 in the 15cc vial, and both Xe-133 and Xe-135 in the 4400cc marinelli geometries, results were biased nonconservatively relative to NRC value An additional RCS gas sample was obtained and utilized to spike both NRC and licensee geometries for additional split sample gas analyse Similar disagreements with the licensee's values nonconservatively biased relative to NRC data, were noted (Table 2).
A review of licensee procedures and records did not indicate causes for the observed difference Cognizant licensee representatives agreed to evaluate gas calibrations for the gamma spectroscopy system The inspectors informed licensee representatives that pending their review and evaluation of the gas geometry calibrations this item would be considered an unresolved item (50-269,-270,-287/86-19-01).
b. The inspectors noted that the licensee was provided with a simulated liquid waste sample by the NRC contract laboratory and was requested to complete radiochemical analyses for H-3, Fe-55, Sr-89, and Sr-9 Comparison of licensee and NRC results are listed in Table 2 with the acceptance criteria listed in Attachment 1. Results were in agreement for all analyse (Opened):
Unresolved Item (URI) (50-269,-270,-287/86-19-01), Review of licensee gamma spectroscopy gas calibration.
Radwaste Burial Site Environmental Monitoring (80721)
The inspector toured the radwaste burial site with licensee representative The environmental sampling program associated with this area includes periodic surveys and collection of vegetation, soil and groundwater samples for radionuclide analyses. Results of these surveys are compared with data from control stations associated with the normal environmental monitoring program. The inspector discussed the collection of background samples within an area adjacent to the burial site for comparison purposes prior to the burial of additional contaminated materia Licensee representatives agreed to evaluate this issu The inspector reviewed selected procedures and the resultant data concerning environmental monitoring for this are The surveys and radionuclides analyses were conducted as required and there were no indications of anamolous data relative to background level.
Inspector Followup Items (92701) (Closed)
50-269,-270,-287/86-07-01:
Review of Radwaste Site Environmental Monitorin The inspector toured the radwaste site burial area and discussed the implemented radiological environmental monitoring procedures with cognizant licensee representatives (Paragraphs 5 and 8). Required surveys and environmental samples were being collected and analyzed as specified by station procedure (Closed) 50-269,-270,-287/86-07-03:
Evaluation of Dose Assessment for Multiple Environmental Pathways. The inspector reviewed and discussed the offsite dose calculations for the maximum exposed individual for 1985 based upon the 1985 environmental program results. The maximum whole body dose was 2.7 mrem/yr (adult) and maximum organ (liver) dose was 6.3 mrem/yr (child). The major contributors to the dose estimates resulted from radiocesium in broadleaf vegetation and fish and from tritium in surface wate TABLE 1 RESULTS OF CONFIRMATORY MEASUREMENTS AT OCONEE NUCLEAR STATION, JUNE 23-26, 1986 SAMPLE CONCENTRATION (uCi/Unit)
RESOLUTION RATIO COMPARISON (Geometry)
ISOTOPE LICENSEE NRC LICENSEE/NRC (1) Reactor Coolant Co-58 8.24 E-3 6.40+/-0.58 E-3
1.29 Agreement (50 ml Bottle)
1-131 1.42 E-2 1.58+/-0.06 E-2
0.90 Agreement 1-132 1.11 E-1 1.25+/-0.02 E-1
0.89 Agreement 1-133 8.40 E-2 0.43+/-0.09 E-2 105 0.89 Agreement 1-135 1.34 E-1 1.45+/-0.05 E-2
0.92 Agreement Cs-134 1.46 E-2 1.61+/-0.05 E-2
0.91 Agreement Cs-137 1.77 E-2 1.87+/-0.06 E-2
0.95 Agreement (2) Reactor Coolant Co-58 7.93 E-3 6.40+/-0.58 E-3
1.24 Agreement (50 ml Bottle)
1-131 1.66 E-2 1.58+/-0.06 E-2
1.05 Agreement 1-132 1.19 E-1 1.25+/-0.02 E-1
0.95 Agreement 1-133 8.99 E-2 9.43+/-0.09 E-2 105 0.95 Agreement 1-135 1.49 E-1 1.45+/-0.04 E-1
1.03 Agreement Cs-134 1.44 E-2 1.61+/-0.05 E-2
0.89 Agreement Cs-137 1.97 E-2 1.87+/-0.06 E-2
1.05 Agreement (3) Reactor Coolant Co-58 8.26 E-3 6.40+/-0.58 E-3
1.29 Agreement (50 ml Bottle)
1-131 1.42 E-2 1.58+/-0.06 E-2
0.90 Agreement 1-132 1.04 E-1 1.25+/-0.02 E-1
0.83 Agreement 1-133 8.06 E-2 9.43+/-0.09 E-2 105 0.85 Agreement 1-135 1.34 E-1 1.45+/-0.04 E-1
0.92 Agreement Cs-134 1.32 E-2 1.61+/-0.05 E-2
0.82 Agreement Cs-137 1.78 E-2 1.87+/-0.06 E-2
0.95 Agreement (1) Liquid Waste Co-58 1.11 E-6 1.12+/-0.11 E-6
0.99 Agreement Co-60 1.54 E-6 1.21+/-0.15 E-6
1.27 Agreement 1-131 8.85 E-7 7.64+/-1.11 E-7
1.16 Agreement (2) Liquid Waste Co-58 1.11 E-6 1.12+/-0.11 E-6
0.99 Agreement Co-60 1.22 E-6 1.21+/-0.15 E-6
1.01 Agreement 1-131 7.56 E-7 7.64+/-1.11 E-7
0.99 Agreement (3) Liquid Waste Co-58 1.19 E-6 1.12+/-0.11 E-6
1.06 Agreement Co-60 1.58 E-6 1.21+/-0.15 E-6
1.30 Agreement 1-131 5.36 E-7 7.64+/-1.11 E-7
0.70 Agreement (1) Particulate Filter Co-60 9.53 E-3 0.76+/-0.30 E-3
0.98 Agreement (47 mm Filter)
Cs-137 1.35 E-2 1.25+/-0.03 E-2
1.08 Agreement (2) Particulate Filter Co-60 9.32 E-3 9.76+/-0.30 E-3
0.95 Agreement (47 mm Filter)
Cs-137 1.30 E-2 1.25+/-0.03 E-2
1.04 Agreement (3) Particulate Filter Co-60 9.34 E-3 9.76+/-0.30 E-3
0.96 Agreement (47 mm Filter)
Cs-137 1.28 E-2 1.25+/-0.03 E-2
1.02 Agreement (1) Charcoal Cartridge Ba-133 4.34 E-2 4.04+/-0.04 E-2 101 1.07 Agreement (Face-Loaded)
S B
ISOTOPE CONCENTRATION (uCi/Un
RESOLUTION RATIO COMPARIS
@
(Geometry)
LICENSEE NRC LICENSEE/NRC (2) Charcoal Cartridge Ba-133 4.60 E-2 4.04+/-0.04 E-2 101 1.14 Agreement (Face-Loaded)
(3) Charcoal Cartridge Ba-133 4.43 E-2 4.04+/-0.04 E-2 101 1.10 Agreement (Face-Loaded)
(2) Gas-RCS Kr-85m 4.83 E-1 4.21+/-0.03 E-1 140 1.15 Agreement (15 cc Vial)
Kr-87 4.25 E-1 4.95+/-0.10 E-1
0.86 Agreement Kr-88 8.09 E-1 9.03+/-0.13 E-1
0.90 Agreement Xe-133 5.93 E-0 7.41+/-0.01 E-0 741 0.80 Disagreement Xe-133m 1.27 E-1 1.50+/-0.15 E-1
0.85 Agreement Xe-135 1.86 E-0 2.11 +/- 0.006 E-0 351 0.88 Agreement (3) Gas-RCS Kr-85m 4.78 E-1 4.21+/-0.03 E-1 140 1.14 Agreement (15 cc Vial)
Kr-87 4.08 E-1 4.95+/-0.10 E-1
0.82 Agreement Kr-88 7.28 E-1 9.03+/-0.13 E-1
0.81 Agreement Xe-133 5.74 E-0 7.41+/-0.01 E-1 741 0.77 Disagreement Xe-133m 1.20 E-1 1.50+/-0.15 E-1
0.80 Agreement Xe-135 1.80 E-0 2.11+/-0.006 E-0 351 0.85 Agreement (2) Gas-Vent Xe-133 1.19 E-6 2.00+/-0.11 E-6
.60 Disagreement (4400 cc Marinelli)
Xe-135 1.50 E-7 2.59+/-0.32 E-7
.58 Disagreement (3) Gas-Vent Xe-133 1.28 E-6 2.00+/-0.11 E-6
.64 Disagreement (4400 cc Marinelli)
Xe-135 1.51 E-7 2.59+/-0.32 E-7
.58 Disagreement (1) Analyzed Using Gamma Spectroscopy System No. 1112 (2) Analyzed Using Gamma Spectroscopy System No. 1242 (3) Analyzed Using Gamma Spectroscopy System No. 1692
TABLE 2 RESULTS OF CONFIRMATORY MEASUREMENTS FOR SPIKED GAS SAMPLES AT OCONEE NUCLEAR PLANT, JUNE 23-26, 1986 SAMPLE ISOTOPE CONCENTRATION (uCi/Unit)
RESOLUTION RATIO COMPARISON (Geometry)
LICENSEE NRC LICENSEE/NRC (Geometry)
(3) RCS Gas Kr-85m 4.97 E-1 5.15+/-0.06 E-1
0.96 Agreement (15 cc Vial)
Xe-133m 1.20 E-1 1.92+/-0.21 E-1
0.62 Agreement Xe-133 6.01 E-0 8.21+/-0.02 E-0 410 0.73 Disagreement Xe-135 1.84 E-0 2.52+/-0.01 E-0 251 0.73 Disagreement (3) RCS Gas Kr-85m 3.51 E-1 5.15+/-0.06 E-1
0.68 Disagreement (100 cc Bomb)
Xe-133m 9.21 E-2 1.92+/-0.21 E-1
0.48 Disagreement Xe-133 4.63 E-0 8.21+/-0.02 E-0 410 0.56 Disagreement Xe-135 1.36 E-0 2.52+/-0.01 E-0 251 0.54 Disagreement (3) RCS Gas Kr-85m 3.83 E-1 5.15+/-0.06 E-1
0.74 Disagreement (4400 cc Marinelli)
Xe-133m 9.95 E-2 1.92+/-0.21 E-1
0.52 Disagreement Xe-133 4.82 E-0 8.21+/-0.02 E-0 410 0.59 Disagreement Xe-135 1.40 E-0 2.52+/-0.01 E-0 251 0.56 Disagreement (3) Analyzed Using Gamma Spectroscopy System No. 1692
TABLE 3 RESULTS OF H-3, Sr-90, AND Fe-55 ANALYSES FOR OCONEE NUCLEAR PLANT, JUNE 23-26, 1986 SAMPLE ISOTOPE CONCENTRATION (uCi/Unit)
RESOLUTION RATIO COMPARISON LICENSEE NRC LICENSEE/NRC (Geometry)
Liquid -
NRC H-3 2.6 E-5 2.33+/-0.04 E-5
1.16 Agreement Spike Sr-89 2.7 E-5 2.93+/-0.09 E-5
0.92 Agreement Sr-90 2.7 E-6 2.77+/-0.11 E-6
0.97 Agreement Fe-55 2.0 E-5 1.73+/-0.04 E-5
1.16 Agreement
Attachment 1 CRITERIA FOR COMPARING ANALYTICAL MEASUREMENTS This attachment provides criteria for comparing results of capability tests and verification measurements. The criteria are based on an empirical relationship which combines prior experience and the accuracy needs of this progra In these criteria, the judgement limits are variable in relation to the compari son of the NRC's value to its associated uncertainty. As that ratio, referred to in this program as "Resolution",
increases, the acceptability of a licensee's measurement should be more selectiv Conversely, poorer agreement must be considered acceptable as the resolution decrease RATIO =
LICENSEE VALUE NRC REFERENCE VALUE Resolution Agreement
<4 0.4 -.5 -.6 -
1.66 16 -
0.75 -
1.33 51 -
200 0.80 -
1.25
>200 0.85 -
1.18