IR 05000269/1978017
| ML15251A120 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 09/20/1978 |
| From: | Gibson A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML15223A282 | List: |
| References | |
| 50-269-78-17, 50-270-78-17, 50-287-78-18, NUDOCS 7810130064 | |
| Download: ML15251A120 (4) | |
Text
SRE UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
V K
2101 MARIETTA STREET, ATLANTA, GEORGIA 30303
Report Nos.: 50-269/78-17, 50-270/78-17 and 50-287/78-18 Docket Nos.: 50-269, 50-270 and 50-287 License Nos.: DPR-38, DPR-47 and DPR-55 Licensee: Duke Power Company P. 0. Box 33189 422 South Church Street Charlotte, North Carolina 28242 Inspection at:
Oconee Nuclear Station Inspection conducted: August 7, 1978 Inspector: W. J. Mill Reviewed by:
D A. F. Gibs n, Chief Date Radiation Support Section Fuel Facility and Materials Safety Branch Inspection Summary Inspection on August 7, 1978 (Report Nos. 50-269/78-17, 50-270/78-17 and 50-287/78-18)
Area Inspected: Whole body counting practices and procedures, and a test count of the NRC phantom on the whole body counter. The inspection involved 3 inspector-hours on site by one NRC inspecto Results: In the one area inspected, no items of noncompliance or deviations were identifie t/ 00O(/
.RII Report Nos. 50-269/78-17, 50-270/78-17 and 50-287/78-18 I-1 DETAILS I Prepared by:
ad iaonS y
p cial
t W. J. Millsap, adiation Spfcialist Dat Radiation Sup rt Section Fuel Facility and Materials Safety Branch Date of Inspecti n' A 1978 Reviewed by: _
_____
A. F. Gibson, Chief Date Radiation Support Section Fuel Facility and Materials Safety Branch Persons Contacted
- J. E. Smith, Station Manager
- R. M. Koehler, Technical Services Superintendent
- C. T. Yongue, Station Health Physicist
- R. T. Bond, Licensing and Projects
- D. J. Vito, Licensing and Projects
- Steve Morgan, Health Physics Laboratory Technician
- Denotes those present at the exit interview Questionnaire Review The inspector reviewed with a licensee representative his answers to the questions concerning whole body counting sent to him in a letter signed by J. T. Sutherland, dated July 31, 1978. A summary of certain aspects of these results is given belo a. Whole Body Counting System This system utilizes a chair whole body counter designed by Masse and Bolton. The two detectors, each Nal (Tl) crystals, are of the following sizes:
for the torso, 3"diameter x 3" thick, and for the thyroid, 1 "diameter x " thic The torso crystal is shielded on the sides and back by two inches of lead incased in steel. The chair, which acts as a shadow shield for the crystals, is contructed with " of steel on the back and 3/4" of steel on the botto I
RII Report Nos. 50-269/78-17, 50-270/78-17 and 50-287/78-18 I-2 The system uses a Northern Scientific Model 710 Multichannel Analyzer with 1024 channels which can be used by either of the detectors. Each channel represents approximately 2 key of energ Data reduction is accomplished on-site using a Hewlett Packard Model 9830 computer, which utilizes a program of the "matrix method" type supplied by Applied Physical Technology, In The torso detector is calibrated for the following radio-nuclides:
Cs-1347, Cs-137, Co-58 and Co-60. The thyroid detector is cali brated for 1-13 The lower limit of detection for Co-60 and Cs-137 in the torso is approximatley 7 nCi. The lower limit of detection for 1-131 in the thyroid is approximately 10 nCi. The normal period of count is 600 second Procedures Health Phsics Procedural Guide No. IV-1 (Interim Guidance For Scheduling of Body - Burden Analyses) states that body burden analysis should be performed as soon as practicable on each individual who has been newly assigned a visitor or permanent Health Physics badge number; on each individual who has worked at a non-Duke Nuclear facility since last receiving a body - burden analysis at a Duke facility; on each individual who has accumulated 40 or more MPC - hours of exposure to air particulates, iodines or tritiated water vapor during the immediate past seven - consecu tive -day period; on each individual who has been involved in a real or suspected accidental internal exposure incident; and on each individual who has a visitor or permanent Health Physics badge number and who is terminating employment or assignment with Duke Power Company. In addition Oconee Nuclear Station Procedure HP/0/B/1000/63 states that a routine monitoring schedule is in effect to include at least annual monitoring of all persons frquenting the Radiation Control Area, or having significant potential for internal exposure, as determined by the Station Health Physicist. In addition, Procedure HP/0/13/1000/63 states that if a body burden analysis reveals the presence of radioiodine, a thyroid count should be schedule Oconee Nuclear Station Procedure HP/0/B/1001/08 (Operating/
Calibration Procedure For The Body Burden Analyzer) states that calibration of the whole body counter is to be accomplished every six month Calibration is performed using two five gallon jerry
RII Report Nos. 50-269/78-17, 50-270/78-17 and 50-287/78-18 1-3 cans filled with demineralzed water and placed in an "L" shaped arrangement to simulate a human being. The upper can is fitted with a glass tube down the center into which point sources are placed during calibration. The calibration is performed using a program developed by Applied Physical Technology, Inc. Procedure HP/0/13/100/63 states that operational checks (energy and effi ciency checks) are performed daily on the whole body counter during us Oconee Nuclear Station Procedure HP/0/B/1000/63 (Body Burden Analysis Including Radioiodine and Trituim) states that if a body burden analysis reveals internal activities greater than or equal to 5% Maximum Permissible Organ Burden additional analysis are performed and a dose commitment calculation is made. Also, if an acute intake of greater than 10% Maximum Permissible Organ Burden is discovered, an investigation for possible overexposure is initated and a dose commitment assigne. Test Count of the NRC Phantom At the request of the inspector, the licensee counted a torso phantom provided by the inspector. The licensee informed the inspector of the amount of each radionuclide detected in the phantom. Since this phantom will be counted by other licensees in Region II, the actual amount of each radionuclide present in the phantom at the time of the count was not communicated to the licensee at the time of this inspectio A summary report will be provided to participating licensees at the conclusion of the test progra. Exit Interview The inspector met with the station manager and other members of the plant staff at the conclusion of the inspection on August 7, 1978 and summarized the scope and findings of the inspection. Items discussed included certain information to be forwarded to the inspector at the Region II office and the issuance of a summary report once the test program is completed.