IR 05000269/1990019
| ML15224A698 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 07/05/1990 |
| From: | Decker T, Marston M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML15224A697 | List: |
| References | |
| 50-269-90-19, 50-270-90-19, 50-287-90-19, 72-0004-90-19, NUDOCS 9007260162 | |
| Download: ML15224A698 (4) | |
Text
p R.EoG UNITED STATES o
NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA STREET, ATLANTA, GEORGIA 30323 Wi& 0 6 1990 Report Nos.:
50-269/90-19, 50-270/90-19, 50-287/90-19, and 72-4/90-19 Licensee: Duke Power Company 422 South Church Street Charlotte, NC 28242 Docket Nos.: 50-269, 50-270, License Nos.: DPR-38, DPR-47, 50-287, and 72-4 DPR-55, and SNM-2503 Facility Name:
Oconee 1, 2, 3, and ISFSI Inspection Conducted:
June 11-13, 1990 Inspector:
-745/9?___
R. R. Marston Date Signed Accompanying Personnel:
T-,-R. Decker Approved by:
/
T. R. Decker, Chief Date Signed Radiological Effluents and Chemistry Section Emergency Preparedness and Radiological Protection Branch Division of Radiation Safety and Safeguards SUMMARY Scope:
This special, unannounced inspection was conducted in the areas of radiological effluent measurements and preparation for use of an Independent Spent Fuel Storage Installation (ISFSI).
Results:
The licensee's effluent analysis program was acceptable. Documentation of the calibration and quality control program showed that the program was very detailed and complet One non-cited violation (NCV)
was identified and reviewed during this inspection:
failure to meet Lower Limits of Detection for nuclides during measurement of liquid radwaste releases (Paragraph 2).
One Inspector Followup Item (IFI)
was identified:
incorporate into two Abnormal Procedures (APs)
requirements to include the ISFSI in damage surveys following an earthquake and other natural disasters (Paragraph 3).
1* 2 ()7 0 FIDR FT1C:
CLU:
REPORT DETAILS 1. Persons Contacted Licensee Employees
- T. Cherry, Radiation Protection Supervisor
- J. Davis, Technical Services Superintendent
- B. Dolan, Design Site Officer
- T. Glenn, Maintenance Engineering E. Lampe, Associate Scientist
- R. Lingle, Nuclear Production Engineer
- S. Perry, Compliance Clerical S. Smith, Radiation Production Specialist
- S. Spear, Acting Radiation Protection Manager
- R. Sveigart, Operations Superintendent
- G. Waldron, General Office NRC Resident Inspectors B. Desai, RI
- Skinner, SRI L. Wert, RI
- Attended exit intervie. Radiological Effluent Lab Instrumentation (84750)
Technical Specification (TS) 4.1 and TS Table 4.1-3 state the requirements for sampling, analysis, and Lower Limits of Detection (LLDs)
for liquid and gaseous effluent system The inspector discussed the gamma spectroscopic systems with cognizant Radiation Protection (RP)
representatives and reviewed calibration and quality control records for the systems to evaluate capability and quality and verify compliance with the applicable T Six gamma spectroscopic detectors were installed in the count room, with two of them out of service at the time of the inspectio Two ND9900 computer systems control and readout the six detector The four in-service detector systems were adequate to handle the required workloa The inspector also reviewed RP Procedure HP//B/1003/19, Calibration of the ND9900 Gamma Spectroscopy System, approved February 28, 199 Calibration data was checked for Detectors 1242, 1641, 1692, 1716, and 183 Pole/Zero was determined first, then the efficiency calibration was don Performance counts (centroid, energy, resolution) were done for energies of 122 KeV, 662 KeV, and 1836 KeV. Activity concentrations were done for 662 Ke LLD calculations were done for the specific nuclides found in various geometrie The last calibrations were done for the
detectors in March 198 A RP Specialist stated that efficiency calibration frequency was undergoing change, based on calibration checks coordinated at six month frequencies. The calibration program appeared to be adequat The inspector reviewed data for the detectors for the daily source checks and background checks for the period from January 1 through June 12, 199 Control charts were kept in ND9900 computer memory and viewed or printed out as require The inspector examined control charts for one of the detectors for February through early June, 199 The control charts showed that the count system operated under good contro The inspector reviewed Licensee Event Report (LER) 269/90-0 The LER identified a problem involving count room detector 164 The count room used minimum count times for each sample which would meet required LLDs specified in TS Table 4.1-3, and specified note Detector 1641 had been able to meet LLD requirements for liquid radwaste by counting a 1-liter sample for 600 second Due to an increase in background level, the calibration performed on March 13, 1989, showed that the required LLD of 5.OE-7 microcuries per milliliter was no longer met for this detector for a count time of 600 seconds, but, instead, would be met with a count of 2,000 second The calibration showed that at a 600 second count, the LLD for Iron-59 was 6.51E-7 microcuries per milliliter, and for Zinc-65, the LLD was 6.75E-7 microcuries per milliliter. No annotation was made on the worksheet where actual LLDs were compared to required LLD As a result, the memorandum for Detector 1641, which showed minimum count times for each geometry, was not updated. When the memorandum was updated on the computer, the previous value (600 seconds) remained in the memorandu The liquid radwaste (one liter) samples were counted at the erroneous time on this detector until January 17, 1990, when the error was discovered during a Corporate Quality Assurance audit of liquid radwaste release Corrective actions were initiated to remove Detector 1641 from service until a corrected memorandum was issue The affected releases were identified and were recalculated assuming levels equal to the actual limit of detectability. Verification obtained confirmed that no other detectors were similarly affected, and the calibration procedure revise The inspector reviewed the procedure and noted that the LLD worksheets had been included as Enclosures to the procedure and required an entry for
"LLD not met."
The licensee stated that no limits were exceeded during the period the LLDs were not me The corrective action was adequate to correct this proble The failure to measure the liquid radwaste samples such that the required LLDs of TS Table 4.1-3 were met was identified as a violation by the inspector:
NCV 50-269, 270, 287/90-19-01; failure to meet LLDs in liquid radwaste sample The violation is not being cited because the criteria specified in Section V.A. of the Enforcement Policy was satisfie No violations or deviations were identifie.
Exit Interview The inspection scope and results were summarized on June 13, 1990, with those persons indicated in Paragraph 1. The inspector described the areas inspected and discussed in detail the inspection results listed abov Proprietary information is not contained in this repor Dissenting comments were not received from the license One NCV was identified (Paragraph 2);
failure to meet LLDs for nuclides during measurement of liquid radwaste release, and one IFI was identified:
include in appropriate APs, that ISFSI be surveyed following a seismic event or other natural disaster.