IR 05000250/1995013
| ML17353A332 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 08/16/1995 |
| From: | Robert Carrion, Decker T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML17353A331 | List: |
| References | |
| 50-250-95-13, 50-251-95-13, NUDOCS 9508280272 | |
| Download: ML17353A332 (10) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTASTREET, N.W., SUITE 2900 ATLANTA,GEORGIA 30323.0199 August 17, 1995 Report Nos:
50-250/95-13 and 50-251/95-13 Licensee:
Florida Power and Light Company 9250 West Flagler Street Miami, FL 33102 Docket Nos.:
50-250 and 50-251 License Nos.:
DPR-31 and DPR-41 Facility Name:
Turkey Point 3 and
Inspection Conducted:
July 19 - 21, 1995 Inspector:
R.
P. Carri on, Radi ati on Speci al ist
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Date Signed Accompanied by:
T.
R. Yolk, Physical Sciences Technician lP WMc..>>~
cy /d.'/P>~
T.
R. Decker, Chief Date Signed 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.
Results:
The licensee demonstrated that an effective Count Room radiochemical analysis program was in place.
(Paragraph 2)
9S08280272 9'50817 PDR ADOCK 05000250 O
REPORT DETAILS 1.
Persons Contacted
~,
Licensee Employees J.
E. Berg, Radiochemistry Supervisor
- D. E. Jernigan, Plant Manager D. J.
Lee, Primary Operations Supervisor
- C. Mowrey, Compliance Specialist C.
H. Hurray, Radiochemistry Supervisor
- T. Plunkett, Vice President
- W. Prevatt, Operations
- R. E.
Rose, Materials Manager
- R. N. Steinke, Chemistry Supervisor
- G. A. Warriner, guality Assurance (gA)
- E. J.
Weinkam, Licensing Manager Other licensee employees contacted during this inspection included technicians and administrative personnel.
Nuclear Regulatory Commission (NRC)
- T. Johnson, Senior Resident Inspector
",Attended exit interview on July 21, 1995.
Confirmatory Measurements (84750)
Per
CFR 20.1501, the licensee is required to perform surveys as necessary to evaluate the extent of radiation hazards.
a
~
Gamma-Emitting Radioisotopes To evaluate the licensee's analytical capability to make consistently accurate radioactivity measurements, seven samples were analyzed for their radionuclide concentrations by the licensee and the NRC Region II mobile laboratory, including:
samples (one from Unit 3 and one from Unit 4),
a gaseous sample from the Unit 3 Volume Control Tank (VCT), an NRC-supplied simulated gas standard, a particulate filter spiked with RCS liquid from Unit 3 and another spiked with RCS liquid from Unit 4, and an NRC-spiked charcoal cartridge.
The purpose of these comparative measurements was to verify the licensee's capability to accurately detect and identify gamma-emitting radionuclides and to quantify their concentrations.
The licensee analyzed each sample one time on the detector selected by the inspector.
The licensee's Chemistry Counting Room was equipped with three germanium-lithium (Ge-Li) gamma spectroscopy detectors.
Detector ¹1 was manufactured by Princeton Gamma Tech, Inc.
(PGT), while Detectors
¹2 and ¹3 were manufactured by Orte The inspector reviewed calibration curves for various geometries of the three detectors.
The calibration curves were developed using mixed gamma sources (which typically contained Cd-109, Co-57, Ce-139, Hg-203, Sn-113, Sr-85, Cs-137, Co-60, and Y-88).
The licensee used six sources for the various geometry calibrations.
The inspector reviewed Certificates of Calibration for several of the sources used to generate the referenced
,calibration curves.
Each source was prepared using an aliquot measured gravimetrically from a calibrated master radionuclide solution source.
The calibration had been confirmed by the National Institute of Standards and Technology (NIST) in a Measurements Assurance Program as described in NRC Regulatory Guide 4. 15, Rev.
1, dated February 1979.
Confirmation was obtained for each gamma ray listed to within the limits stated on the certificate.
The inspector noted that all of the detectors had been calibrated within the one-year period required by Procedure O-NCCP-103,
"Calibration of the Gamma Spectroscopy Counting System."
Daily performance checks for the detectors were done using Co-57, Co-60, and Cs-137 sources.
The inspector, reviewed the control charts for the period from January 1,
1995 to May 16, 1995 for Detector Pl.
The Co-57 and Co-60 Full Width Half Maximum (FWHM)
data started drifting high in May, prompting the licensee to change the detector in mid-May.
Activity plots for Co-57, Co-60, and Cs-137 indicated no bias during the period.
The inspector reviewed the control charts of Detector P2 for the period from January 1,
1995 to June 24, 1995.
The Co-57 FWHM data indicated a
slightly declining bias while the Co-60 FWHM data showed no bias.
The activity plots for Co-57, Co-60, and Cs-137 indicated no bias during the period.
The inspector also reviewed the control charts
.of Detector 83 for the period from January 1,
1995 to June 30, 1995.
The Co-57 FWHM data indicated a slightly low bias while the Co-60 FWHM data showed no bias.
The activity plots for Co-57, Co-60, and Cs-137 indicated a very slightly high bias during the period.
The inspector concluded that the calibration curves and Certificates of Calibration were current and sufficient.
Attachment 1 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, all of the licensee's results compared favorably with those of the NRC, indicating that the licensee's analysis system was capable of identifying isotopes over a wide energy spectrum.
The inspector concluded that the licensee maintained a high capability to analyie samples of gamma-emitting radioactive materia b.
Sample Collection The inspector reviewed selected portions of Procedure O-NCZP-047.2,
"Volume Control Tank Gaseous Space Sampling,"
approved April 23, 1995.
, The inspector observed licensee technicians obtain a sample from the Unit 3 Volume Control Tank and noted that the procedure was followed closely as the sample was collected.
Proper sampling techniques and health physics practices were employed.
The sample was taken directly to the Count Room for analysis.
The inspector concluded that the licensee's technicians were competent in the collection of samples and knowledgeable of the procedures.
From the observations made during this inspection, the inspector concluded that the licensee had effectively maintained a high-quality radiochemical analysis program.
Exit Interview (84750)
The inspection scope and 'results were summarized on July 21, 1995, with those persons indicated in Paragraph 1.
The inspector described the areas inspected and discussed the inspection results, including likely informational content of the inspection report with regard to documents and/or processes reviewed during the inspection.
The licensee did not identify any such documents or processes as proprietary.
Dissenting comments were not received from the license ATTACHMENT 1 COMPARISON OF NRC AND TURKEY POINT ANALYTICALRESULTS JULY 20-21, 1995 Type of Sample:
Unit 3 Reactor Coolant System (RCS)
.NRC Geometry:
1000 ml Harinelli on Detector Face Turkey Point Geometry:
1000 ml Harinelli on Detector Face Radio-nuclide Detector No.
Na-24 Ar-41 Co-58 Kr-87 Kr-88 Xe-133 Xe-135 I-131 I-133 I-134 I-135 Licensee's Value Ci 9.54 E-4 1.85 E-3 1.71 E-4 1.78 E-3 2.06 E-3 5.74 E-3 9.02 E-3 5.72 E-4 6.59 E-3 1.55 E-2 1.20 E-2 NRC Value Ci (9.73 +/- 0.55)E-4 (2.82 +/- 0.20)E-3 (2.01 +/- 0.24)E-4 (2.29 +/- 0.46)E-3 (2.76 +/- 0.37)E-3 (6.04 +/- 0.16)E-3 (9.51 +/- 0.55)E-3 (6.53 +/- 0.59)E-4 (7.00 +/- 0.10)E-3 (2.58 +/- 0.43)E-2 (1.33 +/- 0.03)E-2 Reso-lution
14
5
38
11
6
Ratio 0.98 0.66 0.85 0.78 0.75 0.95 0.95 0.88 0.94 0.60 0.90 Compar-ison Agree Agree Agree Agree Agree Agree Agree Agree Agree Agree Agr ee Type of Sample:
Unit 4 Reactor Coolant System (RCS)
NRC Geometry:
1000 ml Marinelli on Detector Face Turkey Point Geometry:
1000 ml Marinelli on Detector Face Radio-nuclide Detector Licensee's Value Ci No.
NRC Value Ci Reso-Compar-lution Ratio ison Na-24 Mn-54 Xe-133 Xe-135 1-131 I-133 I-134 1-135 Cs-134 Cs-137 6.07 E-4 7.06 E-5 2.81 E-3 3.51 E-3 2.10 E-4 2.36 E-3 5.76 E-3 4.40 E-3 3.08 E-4 4.58 E-4 (6.44 +/- 0.38)E-4 (6.73 +/- 1.62)E-5 (2.55 +/- 0.22)E-3 (4.04 +/- 0.24)E-3 (3.62 +/- 0.70)E-4 (2.63 +/- 0.06)E-3 (1. 43 +/- 0. 42) E-2 (4.99 +/- 0.19)E-3 (3.34 +/- 0.31)E-4 (4.86 +/- 0.29)E-4
12
5 44'3
11
0.94 Agree 1.05 Agree 1.10 Agree 0.87 Agree 0.58 Agree 0.90 Agree 0.40 Agree 0.88 Agree 0.92 Agree 0.94 Agree
'0 Attachment
2 Type of Sample:
Simulated Gas Standard (Supplied by NRC)
NRC Geometry:
.
1260 cc Gas Harinelli on Detector Face Turkey Point Geometry:
1260 cc Gas Harinelli on Detector Face Detector No.
Co-57 Co-60 Y-88 Kr-85 Sr-85 Cd-109 Sn-113 Cs-137 Ce-139 Hg-203 1.61 E-2 1.62 E-1 4.31 E-2 1.50 E+0 6.46 E-3 5.13 E-1 2.46 E-2 1.52 E-1 8.85 E-3 1.08 E-3 (1.76 +/- 0.04)E-2 (1.64 +/- 0.02)E-1 (4.33 +/- 0.08)E-2 (1.58 +/- 0.12)E+0 (7.04 +/- 0.54)E-3 (5. 90 +/- 0. 18) E-1 (2.50 +/- 0.07)E-2 (1.59 +/- 0.02)E-1 (9.40 +/- 0.30)E-3 (1.22 +/- 0.22)E-3
82
13
33
80
6 0.91 Agree 0.99 Agree 1.00 Agree 0.95 Agree 0.92 Agree 0.87 Agree 0.98 Agree 0.96 Agree 0.94 Agree 0.89 Agree Type of Sample:
Unit 3 Volume Control Tank (VCT) Gas Sample NRC Geometry:
1260 cc Gas Harinelli on Detector Face Turkey Point Geometry:
1260 cc Gas Harinelli on Detector Face
Detector No.
Kr-85m Kr-88 Xe-133 Xe-133m Xe-135 6.65 1.12 9.48 3.28 1.13 E-5 E-4 E-4 E-5 E-3 (8.23 +/- 0.19)E-5 (1.37 +/- 0.04)E-4 (9.46 +/- 0.32)E-4 (3.38 +/- 0.25)E-5 (1.12 +/- 0.03)E-3
34
14
0.81 Agree 0.82 Agree 1.00 Agree 0.97 Agree 0.94 Agree Radio-nuclide Detector No.
Type of Sample:
Face-Loaded Charcoal Cartridge (NRC Spike)
NRC Geometry:
Charcoal Cartridge on Shelf
Turkey Point Geometry:
Charcoal Cartridge in elevated geometry Licensee's NRC Reso-Compar-V~lli
~V1 Ci 1 ti R ti
Co-57 Co-60 Y-88 Cd-109 Sn-113 Cs-137 Ce-139 Hg-203 1.71 E-2 1.66 E-1 4.39 E-2 5.44 E-1 2.47 E-2 1.54 E-1 9.14 E-3 6.59 E-4 (1.74 +/- 0.02)E-2 1.68 +/- 0.01)E-1 (4.14 +/- 0.06)E-2 (6.07 +/- 0.06)E-1 (2.66 +/- 0.04)E-2 (1.56 +/- 0.01)E-1 (9.40 +/- 0.17)E-3 (7.40 +/- 1.84)E-4
168
101
156
4 0.98 0.99 1.06 0.90 0.93 0.99 0.97 0.89 Agree Agree Agree Agree Agree Agree Agree Agree
Attachment
Type of Sample:
Particulate NRC Geometry:
Turkey Point Geometry:
Filter Spiked With Unit 3 RCS Liquid Particulate Filter on Shelf ¹1 (Petri Dish)
Particulate Filter in elevated geometry (Hetal Planchet in Petri Dish)
Radio-nuclide Licensee's Value Ci NRC Value Ci Reso-lution Ratio Compar-1 SOll Detector No.
Na-24 Hn-54 Co-58 Co-60 I-132 I-133 I-135 Ba-140 5.38 E-6 5.46 E-6 4.16 E-5 4.90 E-6 3.15 E-5 1.68 E-5 3.01 E-5 1.48 E-5 (6.06 +/- 1.50)E-6 (3.08 +/- 0.80)E-6 (3.53 +/- 0.19)E-5 (4.39 +/- 0.87)E-6 (3.34 +/- 0.37)E-5 (1.58 +/- 0.16)E-5 (2.92 +/- 0.52)E-5 (1.60 +/- 0.28)E-5
4
5
10
6 0.89 Agree 1.77 Agree 1.18 Agree 1'.12 Agree 0.94 Agree 1.06 Agree 1.03 Agree 0.93 Agree Type of Sample:
Particulate Filter Spiked With Unit 4 RCS Liquid NRC Geometry Particulate Filter on Shelf ¹I (Petri Dish)
Turkey Point Geometry:
Particulate Filter in elevated geometry (Netal Planchet in Petri Dish)
Radio-nuclide Licensee's NRC
~Ui i
~U1 Reso-lution Ratio Compar-ison Detector No.
Co-58 I-132 7.81 E-6 (8.76 +/- 0.99)E-6
6.28 E-6 (1.02 +/- 0.23)E-5
0.89 Agree 0.62 Agree
ATTACHMENT 2 CRITERIA FOR COMPARISONS OF ANALYTICALMEASUREMENTS 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 emission, and the accuracy needs of this program.
In these criteria, the "Comparison Ratio Limits"'enoting 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 uncert'ainty, referred to in this program as
"Resolution".'or 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 t
to be in disagreement, while r'atio 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 Resolution Comparison Ratio Limits for A reement
<4 4-7 8-15 16 - 50 51 - 200
) 200.
0.40 - 2.5 0.50 - 2.0 0.60 - 1.66 0.75 - 1.33 0.80 - 1.25 0.85 - 1.18
'Comparison Ratio
= Licensee Value NRC Reference Value Resolution
=
NRC Reference Value Associated Uncertainty
'I 0