IR 05000261/1988018
| ML14191A967 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 08/04/1988 |
| From: | Bermudez H, Hughey C, Kahle J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML14191A966 | List: |
| References | |
| 50-261-88-18, NUDOCS 8808170115 | |
| Download: ML14191A967 (9) | |
Text
RE UNITED STATES oNUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA STREET, ATLANTA, GEORGIA 30323 AUG 0 4 I Report No.:
50-261/88-18 Licensee:
Carolina Power and Light Company P. 0. Box 1551 Raleigh, NC 27602 Docket No.:
50-261 License No.:
DPR-23 Facility Name:
H. B.. Robinson Inspection Conducted:
July 11-15, 1988 Inspect sa Sin C. Hugey H.;/ e mudez Dat Signed Accompanying ersonnel:
T. Volk Approved by:
)
Aproe B:.'
ahle, Section Chief Divi on of Radiation Safety and Safeguards SUMMARY Scope: This routine, unannounced inspection was conducted in the areas of quality assurance and confirmatory measurements for inplant radiochemical analyse Results:
In the areas inspected, no violations or deviations-were identifie PDR ADOCK 050002 PDC
REPORT DETAILS 1. Persons Contacted Licensee Employees
- J. Eaddy, Environmental and Chemistry (E&C) Supervisor
- S. Griggs, Aide-Regulatory Compliance
- J. Harrison, Project Specialist, E&C Support J. Hill, E&C Technician I
- R. Mergan, General Manager
- R. Smith, Manager, Environmental and Radiation Control (E&RC)
- B. Toney, Radiation Control Foreman, E&RC
- H. Watkins, E&C Foreman, E&RC Other licensee employees contacted during this inspection included security force members, technicians, and administrative personne NRC Resident Inspectors
- L. Garner, SRI R. Latta, RI
- Attended exit interview Confirmatory Measurements (84725)
During this inspection, reactor coolant, a particulate filter, a charcoal cartridge and selected liquid and gaseous samples were obtained by or provided to the licensee for analysis by their gamma spectrometry system The licensee's results were compared against those obtained by the inspectors from the same samples analyzed by the NRC Region II Mobile Laboratory gamma spectrometry system. The purpose of these comparative measurements was to verify the licensee's capability to accurately identify and quantify gamma-emitting radionuclides in various plant systems and effluent stream Comparisons were made against the three detectors located in the chemistry counting roo Sample types compared included the following:
(1) reactor coolant, (2) waste gas decay tank, (3) liquid waste monitor tank (4) plant stack charcoal cartridge and (5) spiked particulate filter (provided to the licensee by the inspectors).
A more detailed description of the sample types and counting geometries along with a comparison of the NRC and licensee results is listed in Attachment 1. The methodology for determining agreement with licensee results is discussed in Attachment The results showed agreement for all compared radionuclides with the exception of the licensee's misidentification of Yttrium-88 (Y-88) in the spiked particulate filte The reason for the misidentification of Y-88 was that such radionuclide was not included i the licensee's radionuclide library, which is part of the computer software used during the identification proces When licensee representatives became aware that there was Y-88 in the sample, they performed an adequate quantification of the radionuclid The inspectors determined that misidentifying Y-88 in the NRC spiked filter was not safety-significant since Y-88 was not normally expected on in-plant particulate filters collected by the license However, the inspectors pointed out to cognizant. licensee representatives that as the radioisotope inventories in various plant systems change, a more formal review of the computer printouts and an upgrade of radionuclide libraries in the computer software would be necessary in order to prevent misidentification and misquantification of radionuclides present. Licensee representatives acknowledged the inspectors'
comments and indicated that procedural changes will take place to enhance the review process of the computer printouts prior to reporting result The inspectors observed the sampling of the waste gas decay tank and determined that sampling techniques and health physics practices were adequat No violations or deviations were identifie.
Quality Assurance -
Counting Rooms a. Chemistry Counting Room The inspectors reviewed quality control data for the licensee's gamma spectroscopy systems, liquid scintillation counter and gas-flow proportional counter Data reviewed included the gamma spectrometer, Packard 460 (liquid scintillation counter) and Tennelec LB1000 (gas-flow proportional counters) performance test data for the period January -
July, 1988. The inspectors also verified that standards used during.the performance tests and calibrations were traceable to the National Bureau of Standard.
In addition, the inspectors reviewed the current voltage plateaus determinations for the gas-flow proportional counters, the current annual calibration data package for the gamma spectrometers and the Lower Limit of Detection verification worksheets for the gamma
.spectrometer No violations or deviations were identifie j.
b. Health Physics Counting Room The licensee also had a gamma spectrometer located in the Health Physics counting roo The detector was calibrated to analyze charcoal cartridges and particulate filters onl However, at the time of the inspection, the detector was not operational and the inspectors were not able to test its performanc The inspectors verified that the analyses of charcoal cartridges and particulate filters that would normally be performed by the health physics counting room detector were being performed by the chemistry counting room detector Licensee representatives indicated that they were in the process of upgrading procedures and formalizing a quality assurance/cross-check program for that spectrometer in accordance with the chemistry counting room program. The inspectors indicated that counting and quality control procedures and the cross-check program for the health physics counting room will be reviewed during subsequent inspection.
Followup on Information Notices (92701)
The inspectors determined that the following Information Notices (INs)
have been received by the licensee, reviewed for applicability, distributed to appropriate personnel and that action, as appropriate, was taken or schedule IN 88-22: Disposal of Sludge from Onsite Sewage Treatment Facilities at Nuclear Power Stations IN 88-31: Steam Generator Tube Rupture Analysis Deficiency 5. Summary o
The correlation between the licensee and the NRC Mobile Laboratory gamma spectroscopy measurements was well within the NRC's acceptance criteri o The licensee acknowledged the possibility of misidentifying or misquantifying radionuclides when radionuclide inventories change significantl The licensee will initiate procedural changes to minimize this possibilit o Quality control of radiation measurement activities by the Chemistry Counting Room was adequat o The licensee will upgrade the quality control/cross-check program for the Health Physics Counting Roo *
6. Exit Interview The inspection scope and results were summarized on July 15, 1988, with those persons indicated in Paragraph The inspectors described the areas inspected and discussed in detail the inspection result Proprietary information is not contained in this repor Dissenting comments were not received from the license ATTACHMENT 1 NRC-LICENSEE SAMPLE COMPARISON EVALUATION CONCENTRATION RAT10 SAMPLE ISOTOPE LICENSEE NRC RESOLUTION LICENSEE/NRC COMPARE Particulate Co-60 4.223 E-2 4.559 E-2 +/- 4.584 E-4
0.93 Agreement Filter (spiked)
Sr-85 2.606 E-3 2.515 E-3 + 1.137 E-4
1.04 Agreement NRC-LQ-0114-D Cd-109 1.578 E-1 1.655 E-1 + 1.816 E-3
0.95 Agreement Det # APTEC 1299 Sn-113 8.112 E-3 7.970 E-3 + 1.736 E-11
1.02 Agreement Ce-139 2.989 E-3 3.057 E-3 + 7.5011 E-5
0.98 Agreement Co-57 4.719 E-3 4.676 E-3 + 6.537 E-5
1.01 Agreemen t Y-88 1.1495 E-2 1.560 E-2 + 3.232 E-4
0.96 Ag reement Cs-137 4.155 E-2 4.138 E-2 + 3.755 E-4 110 1.00 Agreement Det # PGT1452 Co-60 4.276 E-2 14.559 E-2 4 1.584 E-4
0.94 Agreement Sr-85 2.682 E-3 2.515 E-3 + 1.437 E-4
1.07 Agreement Cd-109 1.573 E-1 1.655 E-1 + 1.816 E-3
0.95 Agreement Sn-113 8.081 E-3 7.970 E-3 + 1.736 E-4
1.01 Agreement Ce-139 2.985 E-3 3.057 E-3 + 7.504 E-5 140 0.98 Agreement Co-57 4.630 E-3 14.676 E-3 + 6.537 E-5
0.99 Agreement Y-88 1.536 E-2 1.560 E-2 + 3.232 E-4
0.98 Agreement Cs-137 4.091 E-2 4.138 E-2 + 3.755 E-4 110 0.99 Agreement Part Filter Co-60 4.164 E-2 4.559 E-2 + 4.584 E-4
0.91 Agreement Det #ORTEC 1602A Sr-85 2.616 E-3 2.515 E-3 + 1.437 E-4
1.04 Agreement Cd-109 1.601 E-1 1.655 E-1 + 1.816 E-3
0.97 Agreement Sn-113 8.045 E-3 7.970 E-3 + 1.736 E-4
1.01 Agreement Ce-139 2.850 E-3 3.057 E-3 + 7.5011 E-5
'40 0.93 Agreement Co-57 I4.1464 E-3 4.676 E-3 + 6.537 E-5
0.95 Agreement Y-88 1.463 E-2 1.560 E-2
+ 3.232 E-4
0.94 Agreement Cs-137 4.188 E-2 4.138 E-2 + 3.755 E-4 110 0.99 Agreement Charcoal Cartridge 1-131 7.859 E-4 7.869 E-4 + 3.855 E-5
1.00 Agreement Det # 1299 (APTEC)
Det # PGT 1452 1-131 7.494 E-4 7.869 E-4 + 3.855 E-5
0.95 Agreement Det # ORTEC 1602A 1-131 7.482 E-4 7.869 E-4 + 3.855 E-5
0.95 Agreement 1260 Gas Marinelli Xe-131M 4.841 E-6 4.104 E-6 + 0.700 E-6
1.18 Agreement Det # APTEC 1299 Xe-133M 3.166 E-6 3.455 E-6 + 0..236 E-6
0.92 Agreement Xe-133 3.482 E-4 3.553 E-4 + 0.010 E-4
>200 0.98 Agreement Xe-135 1.418 E-6 1.629 E-6 + 0.055 E-6
0.87 Agreement 1260 Gas Marinelli Xe-131M 4.840,E-6 4.104 E-6 + 0.700 E-6
1.18 Agreement Det # PGT 1452 Xe-133M 3.216 E-6 3.455 E-6 + 0.236 E-6
0.93 Agreement Xe-133 3.473 E-4 3.553 E-4 + 0.010 E-4
>200 0.98 Agreemen Xe-135 1.337 E-6 1.629 E-6 + 0.055 E-6
0.82 Agreement
Attachmen 9FPage 2 CONCENTRATION RATIO SAMPLE ISOTOPE LICENSEE NRC RESOLUT ION LICENSE/NRC COMPARE 1260 Gas Marinel Ii Xe-131M 4.113 E-6 4.104 E-6 + 0.700 E-6
1.00 Agreement Det # ORTEC 1602A Xe-133M 3.231 E-6 3.455 E-6 + 0.236 E-6
0.93 Agreement Xe-133 3.489 E-4 3.553 E-4 + 0.010 E-4
>200 0.98 Agreement Xe-135 1.340 E-6 1.629 E-6 + 0.055 E-6
0.82 Agreement Reactor Coolant Tc-99M 9.662 E-14 9.623 E-4 + 5.716 E-5
1.00 Ag reement Det # APTEC 1299 1-131 3.203 E-3 3.147 E-3 + 3.871 E-5
1.02 Agreement 1-133 3.648 E-3 3.592 E-3 + 4.615 E-5
. 78 1.02 Agreement Cs-134 2.994 E-3 2.709 E-3 + 4.973 E-5
1.11 Agreement Cs-137 4.051 E-3 3.706 E-3 + 4.549 E-5
1.09 Agreement Reactor Coolant Tc-99M 9.818 E-4 9.623 E-4 + 5.716 E-5
1.02 Agreement Det # PGT 1452
.1-131 3.107 E-3 3.1117 E-3 + 3.871 E-5
0.99 Agreement 1-133 3.517 E-3 3.592 E-3 + 4.615 E-5
0.98 Agreement Cs-134 2.807 E-3 2.709 E-3 + 4.549 E-5
1.04 Agreement Cs-137 4.057 E-3 3.706 E-3 + 4.549 E-5
1.09 Agreement Reactor Coolant Tc-99M 8.831 E-4 9.623 E-4 + 5.716 E-5
0.92 Agreement Det # ORTEC 1602A 1-131 3.243 E-3 3.147 E-3 + 3.871 E-5
1.03 Agreement 1-133 3.726 E-3 3.592 E-3 + 4.615 E-5
1.0l Agreement Cs-134 2.965 E-3 2.709 E-3 + 4.549 E-5
1.09 Agreemen t Cs-137 4.087 E-3 3.706 E-3 + 4.549 E-5
1.10 Agreement B Monitor Tank Xe-131M 1.070 E-5 1.065 E-5 + 1.700 E-6
1.00 Agreement Effluent Xe-133M 8.365 E-6 7.011 E-6 + 5.720 E-7
1.19 Agreement Det # APTEC 1299 Xe-133 1.079 E-3 1.009 E-3 + 2.000 E-6
>200 1.07 Agreement Co-58 8.427 E-7 7.991 E-7 + 8.260 E-8
1.05 Agreement Co-60*-
5.167 E-6 5.723 E-6 + 1.870 E-7
0.90 Agreement Sb-125 1. 429 E-6 1.1104 E-6 + 1.840 E-7
1.25 Agreement B Monitor Tank Xe-131M 1.1453 E-5 1.065 E-5 + 1.700 E-6
1.36 Agreement Effluent Xe-133M 7.739 E-6 7.0l1 E-6 + 5.720 E-7
1.10 Agreement Det # ORTEC 1602A Xe-133 1.133 E-3 1.009 E-3 + 2.000 E-6
>200 1.12 Agreement Co-58 7.790 E-7 7.991 E-7 + 8.260 E-8
0.97 Agreement Co-60 5.131 E-6 5.723 E-6 + 1.870 E-7
0.90 Agrement Sb-125 1.238 E-6 1.144 E-6 + 1.840 E-7
1.08 Agreement B Monitor Tank Xe-131M 1.160 E-5 1.065 E-5 + 1.700 E-6
1.09 Agreement Effluent Xe-133M 7.102 E-6 7.041 E-6 + 5.720 E-7
1.01-Ag-reement Det # PGT 1452 Xe-133 1.100 E-6 1.009 E-3
+ 2.000 E-6
>200 1.09 Agreement Co-58 1.063 E-6 7.991 E-7 + 8.260 E-8
1.33 Agreement Co-60 5.246 E-6 5.723 E-6 + 1.870 E-7
0.92 Agreement Sb-125 1.183 E-6 1.144 E-6 + 1.840 E-7
1.03 Agreement
"D" Waste Gas Xe-131M 1.009 E-4 9.365 E-5 + 1.137 E-5
1.08 Agreement Decay Tank Xe-133M 4.250 E-5 4.516 E-5 + 3.390 E-6
0.9 Agreement Det # APTEC 1299 Xe-133 6.765 [-3 7.375 E-3 + 1.700 E-5
>200 0.92 Agreement
Attachmen
t'
Page 3 CONCENTRATION RAT IO SAMPLE ISOTOPE LICENSEE NRC RESOLUTION LICENSE/NRC COMPARE
"D" Waste Gas Xe-131M 8.118 E-5 9.365 E-5 + 1.137 E-5
0.87 Agreement Decay Tank Xe-133M 0.775 E-5 4.516 E-5 + 3.390 E-6
1.06 Agree ment Det # PGT 1052 Xe-133 7.016 E-3 7.375 E-3 + 1.700 E-5
>200 0.95 Agreement
"D" Waste Gas Xe-131M 1.010 E-0 9.365 E-5 + 1.137 E-5
1.08 Agreement Decay Tank Xe-133M 4.055 E-5 4.516 E-5 + 3.390 E-6
0.99 Agreement Det # ORTEC 1602A Xe-133 6.824 E-3 7.375 E-3 + 1.700 E-5
>200 0.92 Agreement
ATTACHMENT 2 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 this criteria, the judgement limits denoting agreement or disagreement between licensee and NRC results are variable. This variability is a function of the NRC's value relative to its associated uncertainty. As the ratio of the NRC value to its associated uncertainty referred to in this program as
"Resolution"'
increases, the range of acceptable differences between the NRC and licensee values should be more restrictiv Conversely, poorer agreement between NRC and licensee values must be considered acceptable as the resolution decrease For comparison purposes, a ratio2 of the licensee value to the NRC value is compute 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 belo Values outside of the agreement ratios are considered in disagreemen 'Resolution =
NRC Reference Value Associated Uncertainty for the Value 2Comparison Ratio =
Licensee Value NRC Reference Value TABLE 1 Confirmatory Measurements Acceptance Criteria Resolutions vs. Comparison Ratio Comparison Ratio Resolution for Agreement
<4
.4 -.5 -.6 -
1.66 16 - 50
.75 -
1.33 51 - 200
.80 -
1.25
>200
.85 -
1.18