IR 05000269/1991019
| ML16148A556 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 09/05/1991 |
| From: | Decker T, David Jones NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML16148A555 | List: |
| References | |
| 50-269-91-19, 50-270-91-19, 50-287-91-19, NUDOCS 9109240346 | |
| Download: ML16148A556 (8) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA STREET, ATLANTA, GEORGIA 30323 SEP 09 3991 Report Nos.:
50-269/91-19, 50-270/91-19, and 50-287/91-19 Licensee:
Duke Power Company 422 South Church Street Charlotte, NC 28242 Docket Nos.: 50-269, 50,-270, License Nos.: DPR-38, DPR-47, and and 50-287 DRP-55 Facility Name:
Oconee 1, 2, and 3 Inspection Conducted: August 12-16, 1991 Inspector:
,
A-/'
D. W. -ones Date Signed Approved by: 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, unannounced inspection was conducted in the areas of radiological environmental monitoring, meteorological monitoring, audits, training, and dose commitment calculation Results:
The licensee had maintained an adequate environmental monitoring program. The required program for sampling and analysis was effectively implemented. The program results for 1990 indicated that there was no significant radiological impact on.the health and safety of the general public resulting from plant operations (Paragraph 2).
The results of the licensee's participation in the EPA's interlaboratory crosscheck program indicated that the licensee had maintained an adequate quality assurance program for the analysis of environmental samples (Paragraph 3).
The licensee had effectively implemented a meteorological monitoring program. The meteorological monitoring 9109240346 910909 PDR ADOCK 05000269
instrumentation was adequately maintained in an operable status (Paragraph 4).
The licensee had implemented an effective program for audits of radiation protection and chemistry activities. Audits of those activities were thorough and well documented. Management response to audit results and corrective actions were prudent and timely (Paragraph 5).
The licensee had implemented an adequate training and qualification program for Radiation Protection and Chemistry personnel (Paragraph 6).
The licensee had maintained adequate capability to determine the dose to members of the public from radioactive liquid effluents in accordance with the required methodology and parameters (Paragraph 7).
No violations or deviations were identifie REPORT DETAILS Persons Contacted Licensee Employees
- H.,Barron, Station Manager D. Berkshire, Scientist, Radiation Protection S. Coy, Supervising Scientist, Radiation Protection
- T. Curtis, Manager, Compliance D. Davidson, Clerk, Compliance B. Jones, Supervising Scientist, Chemistr C. Mcllwain, General Supervisor, Chemistry
- Perry, Clerk, Compliance
- G. Rothenberger, Superintendent, Integrated Scheduling M. Thorne, General Supervisor, Radiation Protection
- E. Wehrman,Scientist, Radiation Protection other licensee employees contacted included engineers,,
technicians, and office personne Nuclear Regulatory Commission B. Desai, Resident Inspector
- K. Poertner, Resident Inspector P. Harmon, Senior Resident Inspector
- Attended exit intervie..
Radiological-Environmental Monitoring Program (84750)
Technical Specification (TS) 6.4.7 and sections 16.11-6, 16.11-8 and 16.11-10 of the Final Safety Analysis Report (FSAR) described the operational, surveillance, and reporting requirements for the radiological environmental monitoring progra The inspector reviewed the licensee's Annual Radiological Environmental Operating Report for calendar year 1990 and discussed its content with licensee representative The report was submitted prior to May 1,.
1991, as required and included the following:
a description of the program, a summary and discussion of the results for each exposure pathway, analysis of trends and comparisons with previous years and preoperational studies, and an assessment of the impact on the environment resulting from plant operation The report also included the results of the Land Use Census and the Interlaboratory Comparison Program. The licensee's evaluation of the CY 90 environmental monitoring program data for the various exposure pathways indicated the following:
Airborne -
No activity was detected on particulate filters. Cs-137 was the only radionuclide detected in charcoal cartridges but was not found inthe
corresponding particulate filter. The concentration was well below the required lower limit of detection (LLD). An extensive investigation revealed that the Cs 137 was a constituent of the charcoal and was present in the activated carbon media before the cartridges were installed in the air sampler Direct Radiation -
The average quarterly dose for all TLD indicator locations was 15 millirem per quarter and the highest average quarterly dose observed for an indicator location was 28 millirem per quarter. The average quarterly dose for the control location was 19 millirem per quarter. The inspector noted a decreasing trend in the averages of the quarterly doses between 1986 and 199 Surface Water -
There was no significant change between CY 89 and CY 90 in the tritium concentration at the indicator location. The observed concentrations of-1.OE+04 pCi/l were approximately one half of the required reporting level for drinking wate Drinking Water -
No activity was detected at the indicator locations during CY 89 or CY 90 by gamma spectroscopy. Gross beta activity exhibited a slightly increasing trend over the last twelve years but the annual means were less than the required LL Shoreline Sediment -
Increasing trends were indicated in the concentrations of Mn-54, Co-60, Zn-65, Ag-110m, Sb-125, and Cs-137 in shoreline sediments at the indicator locations but the 1990 doses from shoreline sediments were well within dose limit Milk -
Cs-137 was the only man-made radionuclide detected in milk samples taken from indicator locations and its concentration was below the required LLD. No increasing trends were observed in the dat Fish -
Co-58, Cs-134, and Cs-137 were detected in fish samples collected from indicator locations. Their annual mean concentrations for CY 90 were lower than CY 89 levels and were below their required LLD Broadleaf Vegetation -
Cs-137 was the only man-made radionuclide detected in vegetation samples taken from indicator locations during CY 90 and it was only detected in one of the monthly samples. Its concentration was above the required LLD but well below the required reporting leve Dose estimates calculated from environmental monitoring program data were in reasonable agreement with dose estimates calculated from effluent data and were within
40 CFR 190 dose limits. The reports summary section indicated that the contribution to the environmental radioactivity resulting from plant operations was small and had no significant radiological impact on the health and safety of the general public. Based on the above review, it was concluded that the required program for sampling and analysis was effectively implemented and an adequate environmental monitoring program had been maintaine.No violations or deviations were identifie.
Environmental Monitoring Quality Assurance Program (84750)
Section 16.11-6 of the FSAR required the licensee to participate in an Interlaboratory Comparison Program as described in the Offsite Dose Calculation Manual (ODCM) and to include a summary of the results in the Annual Radiological Environmental Operating Report. The ODCM indicated that the licensee would participate in the Environmental Protection Agency's (EPA's) Environmental Radioactivity Laboratory Intercomparison Studies (Crosscheck) Program. The licensee's report for CY 90 described various types of samples analyzed pursuant to this program, the analytical methods employed, and a summary of the results. A total of 38 analyses were performed and the results for all but one sample (tritium in water) were within EPA acceptance criteria. Investigation of techniques employed for tritium analyses resulted.in procedural changes which increased sample reproducibility and accuracy of results. The licensee's overall performance in this program indicated that an effective quality assurance program had been maintained for analysis of environmental sample No violations or deviations were identifie.
Meteorological Monitoring Program (84750)
Section 2.3.3.2 of the FSAR required the licensee to perform weekly equipment calibration and maintenance checks for meteorological parameters as specified by station procedure IP-O-B-1601-03 "Meteorological Equipment Checks". The inspector reviewed the procedure and determined that it included provisions for performing weekly calibration and maintenance checks of the meteorological instrumentatio Instrumentation for the following parameters were included in the weekly checks:
wind speed and direction at 10 and 60 meters, and the difference in the air temperature between 10 and 60 meters. The inspector reviewed the recorded data for the checks performed during the weeks of June 27,1991, through August 8, 1991, and determined that the surveillances had been performed as required. On August 13, i991, the inspector visited the Unit 1 control room and
determined that the meteorological monitoring instrumentation was then currently operable. Based on the above reviews and observations, it was concluded that the meteorological instrumentation was adequately maintained and that the meteorological monitoring program had been effectively implemente No violations or deviations were identifie.
Audits and Appraisals (84750 and 86750)
TSs 6.1.3.4 and 6.1.3.5.d required the licensee to perform audits of station activities, under the cognizance of the Nuclear Safety Review Board, and to forward the audit reports to licensee management within 30 days of completion of each audit. The audits were required to encompass, in part, the following:
the conformance of station operation to provisions contained within the TSs and applicable facility operating license conditions at least once per year; the performance, training and qualifications of the station staff at least once per year; the Offsite Dose Calculation Manual and implementing procedures at least once per-24 months; the Radiological Environmental Monitoring Program and the results thereof at least once per 12 months; and the Process Control Program and implementing procedures for solidification of radioactive wastes at least once per year. The inspector reviewed the report for Departmental Audit NP-91-03(ON), Radiation Protection and Chemistry Activities, dated February 25, 1991, and the management response to the audit results, dated March 25, 1991. The scope of the audit included, in part, activities in the areas of procedures and instructions, training and qualification, liquid and gaseous waste releases, radwaste shipments, and environmental monitoring. The audit was found to have been thorough and well documented. Management response to the audit results and corrective actions were prudent and timely. Based on the above reviews, it was concluded that the licensee had implemented an effective program for audits of station activitie No violations or deviations were identifie.
Training and Qualifications (84750 and 86750)
Section 13.2.2 of the FSAR indicated that station assigned personnel may be trained and qualified through participation in prescribed parts of the Employee Training and Qualification System (EQTS) which consists of general employee training, technical training, and employee/professional development trainin Section 13.2.2.2 of the FSAR indicated that technical training may consist of initial training, on-the-job training and
qualification, and.continuing training. TS 6.5.2.j required the licensee to prepare and retain, for a minimum of six years, records of training. The inspector reviewed training records for three individuals assigned to the Radiation Protection and Chemistry organizational units. The.records reviewed included EQTS Task Lists and Qualification Summaries. The EQTS Task List was a list of tasks which had been developed for each position and for which an individual must have been trained and qualified prior to independently performing the task. The Qualification Summary was maintained for each individual and listed the tasks for which the individual had received training and qualification. 'The inspector compared the EQTS Task List and the Qualification Summary for each of the three individuals selected. The Qualification Summary for one of the individuals included all of the tasks listed on that individual's EQTS Task List. The Qualification Summaries for the other two individuals included all but a very few of the tasks listed on their EQTS Task List. The licensee indicated that procedural requirements prohibited those individuals from performing those tasks for which they had not received training and qualification. Based on the above reviews, it was concluded that the licensee had implemented an adequate training and qualification progra No violations or deviations were identifie.
Dose Calculations (84750)
Section 16.11-7 of the FSAR specified the limits for the dose to a member of the public from radioactive material in liquid effluents released to unrestricted areas and that the dose shall be determined in accordance with the methodology and parameters in the Offsite Dose Calculation Manual (ODCM). In an effort to verify that the licensee was performing dose calculations in accordance with the ODCM, the licensee was requested to calculate the dose from a liquid release using sets of test data provided by the inspector. The test data included typical values for discharge time, discharge flow rate, and dilution flow rat Three fourths of the maximum permissible concentration (MPC)
for Cs-137 listed in 10 CFR 20, Appendix B, was selected for the radionuclide concentration in one set of test dat Since the typical dilution ratio was -260 to one, a Cs-137 concentration of 300 times MPC was selected for another set of test data. Using the equations and parameters in the ODCM and the above test data, the inspector calculated the doses to the total body and to the liver for both of the selected concentrations of Cs-13 The licensee entered the test data into the computer system used for dose calculations and provided the results to the inspector. In each case the calculated doses were in agreement. Based on the above comparisons, it was concluded that the licensee had maintained adequate capability to determine the dose to members of the public from radioactive effluents in accordance with the required methodology and parameter No violations or deviations were identifie.
Exit Interview The inspection scope and results were summarized on August 16, 1991, with those persons indicated in Paragraph 1. The inspector described the areas inspected and discussed in detail the results listed above. No dissenting comments were received from the licensee. The licensee did not identify as proprietary any information provided to the inspector during this inspection.