IR 05000335/1995013
| ML17228B254 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 08/17/1995 |
| From: | Robert Carrion, Decker T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML17228B253 | List: |
| References | |
| 50-335-95-13, 50-389-95-13, NUDOCS 9508290186 | |
| Download: ML17228B254 (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:
50-335/95-13 and 50-389/95-13 Licensee:
Florida Power and Light Company 9250 West Flagler Street Hiami, FL 33102 Docket Nos.:
50-335 and 50-389 Facility Name:
St.
Lucie 1 and
License Nos.:
Inspection Conducted:
July 17 - 19, 1995
.
P. Carrion, Radiation Specialist
])~~ Pa Date.Signed Accompanied by:
T.
R. Yolk, Physical Sciences Technician
/
/
P t7 T.
R. Decker, Chief ate Signed Radiological Effluents and Chemistry Section Radiological Protection and Emergency Preparedness Branch Division of Radiation Safety and Safeguards SUHHARY Scope:
This routine, announced inspection was conducted in the areas of confirmatory measurements and the controls to prevent the release of radioactively-contaminated materials offsite.
Results:
The licensee demonstrated that an effective Count Room radiochemical analysis program was in place.
(Paragraph 2)
The licensee had an effective program in place to control the release of material from the RCA.
(Paragraph 3)
9508P90l8b 9508<7335 PDR ADQCK 05000335
REPORT DETAILS 1.
Persons Contacted Licensee Employees
- E. J.
Benken, Licensing Engineer
- H. F. Buchanan, Health Physics (HP) Supervisor
- R. E.
Cox, Chemistry Effluents Supervisor
- R. Dawson, Licensing Manager D. H. Faulkner, Primary Chemistry Supervisor
- R. J. Frechette, Chemistry Supervisor
- D. A. Sager, Site Vice President
- J. Scarola, Operations Manager R.
B. Somers, HP (Radwaste)
Supervisor Other licensee employees contacted during this inspection included technicians and administrative personnel.
Nuclear Regulatory Commission (NRC)
M. S. Miller, Resident Inspector
- S. Sandin, Resident Inspector
- Attended exit interview 2.
Acronyms and Initialisms used throughout this report are listed in the last paragraph.
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, five samples were analyzed for their radionuclide concentrations by the licensee and the NRC Region II mobile laboratory, including:
a reactor coolant system (RCS)
sample, a liquid sample from the Waste Decay Tank, a Unit 1 containment atmosphere sample, a
particulate filter spiked with RCS liquid, and an NRC-spi ked 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 all of the samples in the Chemistry Count Room, which was equipped with two High Purity Germanium (HpGe)
gamma spectroscopy detectors with a Nuclear Data ND 9900 analysis system.
(Detector ¹3 was not in service for counting plant samples but was being used to try out a new system by Ortec, which was expected to be installed by year's end.)
Detectors
¹1 and ¹2 were manufactured by Princeton Gamma Tech, Inc.
(PGT), while Detector ¹3 was manufactured by EGSG.
Both in-service detectors were used to count all samples.
The inspector reviewed selected portions of Chemistry Procedure C-48C,
"Operation of the Nuclear Data (ND) 9900 Computer Based Counting System."
The procedure provided instruction for the calibration of the detectors and the determination of radionuclide activities of samples based on their gamma emissions.
The inspector reviewed calibration curves for various geometries for 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 inspector also 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 (HIST) 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 Chemistry Procedure C-48C.
Daily performance checks for the detectors were done using Co-60 and Cs-137 sources.
The inspector reviewed the control charts for the period from June 1,
1995 to July 18, 1995 for Detectors
¹1 and
¹2.
For Detector ¹1, the Cs-137 and Co-60 activity plots indicated a stable to slightly declining bias, while the Co-60 Full Width Half Maximum (FWHH) plot indicated a stable to slightly rising bias for the period.
For Detector ¹2, the Cs-137 and Co-60 activity plots indicated no bias, while the Co-60 FWHH plot indicated a stable to slightly declining bias for 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 an adequate capability to analyze samples of gamma-emitting radioactive materia b.
Sample Collection The inspector reviewed selected portions of Chemistry Operating Procedures C-70, Rev. 31,
"Processing Aerated Liquid Wastes,"
approved on May 19, 1995 and C-72, Rev. 36, "Processing Gaseous Waste,"
approved on May 19, 1995.
The portions reviewed included sampling instructions and were adequate for the intended purpose.
The source of the liquid waste sample was Waste Decay Tank 1A and the source of the noble gases sample was the Unit 1 containment atmosphere.
The inspector observed a licensee technician obtain the liquid waste and noble gas samples and noted that the procedures were followed closely by the technician as he completed his duties.
Proper sampling techniques and health physics practices were utilized.
The technicians took the samples 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 respective procedures.
From the observations made during this inspection, the inspector concluded that the licensee had effectively maintained a good radiochemical analysis program.
No violations or deviations were identified.
3.
Controls for the Removal of Material From the Radiation Control Area (RCA)
(84750)
The inspector discussed the process used to remove material from the RCA with the Radwaste Supervisor.
The licensee removes material from the RCA by Health Physics Procedure HPP-41,
"Movement of Material and Equipment," which specifies the criterIa by which material may be released from the RCA.
Per procedure, in order to release material (or a vehicle) from the RCA, that material shall have no detectable activity, as determined by direct frisks or smear surveys done by Health Physics (HP) personnel.
Material determined to be clean then may be released from the RCA with authorization from HP.
All material surveyed and released through designated control points is entered into the
"Unconditional Release Log" and the log entry is signed by HP personnel authorizing the release.
The log is later inspected by HP supervisory personnel for proper signatures.
The inspector went to one of the designated control points and discussed the procedure with the technician on duty at the time.
The inspector was shown the area where material, from the RCA was placed prior to being frisked/surveyed, where and how the frisks were done, and where the clean material was placed subsequent to frisking.
Each area was properly posted and identified the material held within.
The inspector reviewed entries in the Unconditional Release Log of the previous several months and noted that it was being properly used to document
released material.
Periodically, the clean material in the holding area was collected, removed from the RCA, and disposed of as normal trash.
There was no evidence of improper release of radiologically-contaminated material.,
Based on observations in the work area, discussions with cognizant licensee, and review of the procedures used for this work, the inspector concluded that the licensee had implemted an effective program to control the release of material from the RCA within regulatory limits.
Exit Interview (84750)
The inspection scope and results were summarized on July 19, 1995, with those persons indicated in Paragraph I.
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 licensee.
Acronyms and Initialisms CFR
- Code of Federal Regulations Ci
- curie FWHM
- Full Width Half Maximum HP
- Health Physics HPGe
- High Purity Germanium
- liter pCi
- micro-Curie (1.0E-6 Ci)
ml
- milli-liter (1.0E-3 1)
- National Institute of Standards and Technology NRC
- Nuclear Regulatory Commission RCA
- Radiation Control Area RCS
ATTACHMENT 1 COMPARISON OF NRC AND ST.LUCIE ANALYTICALRESULTS JULY 17-18, 1995 Type of Sample:
Unit 2 Reactor Coolant System (RCS)
NRC Geometry:
50 ml Bottle on Shelf
St.
Lucie Geometry:
16 ml Cocktail Vial on Shelf
Radio-nuclide Licensee's NRC
~V1 Ci
~Vi Ci Reso-lution Ratio Compar-ison Detector No.
Na-24 Ar-41 Kr-88 I-131 I-132 I-133 Xe-133 I-135 Xe-135 1.25 E-3 5.23 E-3 1.42 E-3 1.07 E-3 1.67 E-2 1.16 E-2 1.69 E-3 1.91 E-2 8.44 E-3 (1. 17 +/- 0. 06) E-3 (5.12 +/- 0.31)E-3 (1. 48 +/- 0. 35) E-3 (1. 18 +/- 0. 06) E-3 (2.11 +/- 0.05)E-2 (1. 22 +/- 0. 02) E-2 (1.62 +/- 0.10)E-3 (2.00 +/- 0.04)E-2 (7.03 +/- 0.41)E-3
17
20
63
50
1.07 1.02 0.96 0.91 0.79 0.95 1.04 0.96 1.20 Agree Agree Agree Agree Agree Agree Agree Agree Agree Detector No.
Na-24 Ar-41 Kr-88 I-131 I-132 I-133 Xe-133 I-135 Xe-135 1.26 E-3 4.95 E-3 1.36 E-3 1.12 E-3 1.67 E-2 1.14 E-2 1.61 E-3 2.00 E-2 6.98 E-3 (1.17 +/- 0.06)E-3 (5.12 +/- 0.31)E-3 (1.48 +/- 0.35)E-3 (1. 18 +/- 0. 06) E-3 (2. 11 +/- 0. 05) E-2 (1.22 +/- 0.02)E-2 (1.62 +/- 0.10)E-3 (2.00 +/- 0.04)E-2 (7.03 +/- 0.41)E-3
17
20
63
50
1.08 0.97 0.92 0.95 0.79 0.93 0.99 0.90 0.99 Agree Agree Agree Agree Agree Agree Agree Agree Agree
Attachment
2 Type of Sample:
Unit 1 Containment Atmosphere Sample NRC Geometry:
1260 cc Gas Harinelli on Detector Face St. Lucie Geometry:
4600 cc. Gas Harinelli on Detector Face Radio-nuclide Licensee's Value Ci NRC Value Ci Reso-lution Ratio Compar-ison Detector No.
Ar-41 Xe-133 Xe-135 2.36 E-6 (3.29 +/- 0.30)E-6
4. 90 E-5 (5. 10 +/- 0. 18) E-5
1.04 E-.6 (1.12 +/- 0.06)E-6
0.71 0.96 0.86 Agree Agree Agree Detector No.
Ar -41 Xe-133 Xe-135 2. 16 E-6 (3.29 +/- 0.30)E-6
4.75 E-5 (5.10 +/- 0.18)E-5
1. 06 E-2 (1. 12 +/- 0. 06) E-6
0.65 0.93 0.88 Agree Agree Agree Type of Sample:
Face-Loaded Charcoal Cartridge (NRC Spike)
NRC Geometry:
Charcoal Cartridge on Shelf
St.
Lucie Geometry:
Charcoal Cartridge on Shelf
Radio-Licensee's NRC lid YIfl Detector No.
Reso-lution Ratio Compar-ison Co-57 Co-60 Y-88 Cd-109 Sn-113 Cs-137 Ce-139 Hg-203 1.74 E-2 1.65 E-1 4.55 E-2 5.76 E-1 2.42 E-2 1.53 E-1 9.45 E-3 6.17 E-4 (1. 78 +/- 0. 02) E-2 (1.70 +/- 0.01)E-1 (4.33 +/- 0.06)E-2 (6.06 +/- 0.06)E-1 (2.69 +/- 0.05)E-2 (1.55 +/- 0.01)E-1 (9.60 +/- 0. 17)E-3 (1.03 +/- 0.19)E-3
170
101
155
5 0.98 0.97 1.05 0.95 0.90 0.99 0.98 0.60 Agree Agree Agree Agree Agree Agree Agree Agree Detector No.
Co-57 Co-60 Y-88 Cd-109 Sn-113 Cs-137 Ce-139 Hg-203 1.69 E-2 1.61 E-1 4.58 E-2 5.53 E-1 2.38 E-2 1.50 E-1 9.53 E-3 1.15 E-3 (1.78 +/- 0.02)E-2 (1.70 +/- 0.01)E-1 (4.33 +/- 0.06)E-2 (6. 06 +/- 0. 06) E-1 (2. 69 +/- 0. 05) E-2 (1.55 +/- 0.01)E-1 (9. 60 +/- 0. 17) E-3 (1.03 +/- 0.19)E-3
170
101
155
5 0.95 0.95 1.06 0.91 0.88 0.97 0.99 1.12 Agree Agree Agree Agree Agree Agree Agree Agree
Attachment
3 Type of Sample:
Liquid Sample from the Waste Decay Tank lA NRC Geometry:
1000 ml Marinelli on Detector Face St. Lucie Geometry:
1000 ml Marinelli on Detector Face Radio-nuclide Licensee's Value Ci NRC
Reso-
~Y1 Compar-Ratio ison Detector No.
Co-58 Co-60 Ag-110m Xe-133 Cs-137 Detector No.
6.53 E-7 1.16 E-6 1.14 E-6 6.26 E-7 2.61 E-7 (5.19 +/- 0.80)E-7 (1.07 +/- 0.12)E-6 (9.04 +/- 0.87)E-7 (4.53 +/- 1.24)E-7 (2.78 +/- 0.44)E-7
9
4
1.26 Agree 1.08 Agree 1.26 Agree 1.38 Agree 0.93 Agree Co-58 Co-60 Ag-110m Xe-133 Cs-137 7.42 E-7 1.20 E-6 1.25 E-6 4.53 E-7 2.35 E-7 (5. 19 0/- 0.80)E-7 (1.07 +/- 0.12)E-6 (9.04 +/- 0.87)E-7 (4.53 +/- 1.24)E-7 (2.78 +/- 0.44)E-7
9
6 1.42 1.12 1.38 1.00 0.85 Agree Agree Agree.
Agree Agree Type of Sample:
Particulate Filter Spiked With Unit 2 RCS Liquid NRC Geometry:
Particulate Filter on Shelf 1 (Petri Dish)
St. Lucie Geometry:
Particulate Filter on Shelf 1 (Whirlpack)
Radio-nuclide Ci Licensee's NRC ffi
~V1 Reso-lution Ratio Compar-ison Detector No.
Na-24 I-131 I-132 I-133 I-135 9.45 E-4 9.89 E-4 9.75 E-3 6.55 E-3 1.12 E-2 (8.58 +/-
(8.11 +/-
(1.17 +/-
(7.67 +/-
(1.19 +/-
1.18)E-4 0.78)E-4 0.05)E-2 0.21) E-3 0.08)E-2
~
10
37
1.10 1.22 0.83 0.85 0.94 Agree Agree Agree Agree Agree Detector No.
Na-24 I-131 I-132 I-133 I-135 1.11 E-3 6.04 E-4 1.19 E-2 7.25 E-3 1.18 E-2 (8.58 +/-
(8.11 +/-
(1.17 +/-
(7.67 +/-
(1.19 +/-
1.18)E-4 0.78)E-4 0.05)E-2 0.21) E-3 0.08)E-2
10
37
1.29 Agree 0.74 Agree 1.02 Agree 0.95 Agree 0.99 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 uncertainty, 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 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 Resolution Comparison Ratio Limits for A reement 4 -
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