IR 05000269/1992022
| ML16148A684 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 09/18/1992 |
| From: | Decker T, David Jones NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML16148A683 | List: |
| References | |
| 50-269-92-22, 50-270-92-22, 50-287-92-22, NUDOCS 9209290075 | |
| Download: ML16148A684 (6) | |
Text
P9 REG,UNITED STATES o
NUCLEAR REGULATORY COMMISSION REGION il 101 MARIETTA STREET, ATLANTA, GEORGIA 30323 SEP 2 2 9 Report Nos.:
50-269/92-22, 50-270/92-22, and 50-287/92-22 Licensee:
Duke Power Company P. 0. Box 1007 Charlotte, NC 28201-1007 Docket Nos.: 50-269, 50-270, License Nos.: DPR-38, DPR-47, and 50-287 and DPR-55 Facility Name:
Oconee 1, 2, and 3 Inspection Conducted: August 31-September 4, 1992 Inspector:
.
2Z/7/1 D. r.,6nes Date Signed Approved by:
V L
/c/
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, unannounced inspection was conducted in the.areas of post accident sampling systems, primary and secondary wate chemistry, transportation of radioactive material, and solid waste managemen Results:
No violations or deviations were identifie The licensee had implemented an adequate program to ensure the capability to obtain and analyze samples of reactor coolant and containment atmosphere under accident conditions (Paragraph 2).
The licensee's water chemistry control program was effectively implemented. Parameters required to be monitored were maintained well within their specified limits. The program also included
. provisions for implementing, with few exceptions, the Electric Power Research Institute (EPRI) guidelines for PWR primary and secondary water chemistry (Paragraph 3).
9209290075 920922 PDR ADOCK 05000269 G
The licensee had effectively implemented a program for shipping radioactive materials. No recent transportation incidents involving the licensee's shipments of radioactive material have occurred (Paragraph 4).
The licensee had maintained the required records of spills involving the spread of contamination in and around the facilit That information is required for the safe and effective decommissioning of the facility (Paragraph 5).
0II II3 Based on the above reviews, it was concluded that the licensee's water chemistry control program was effectively implemente No violations or deviations were identifie.
Transportation of Radioactive Material (86750)
10 CFR 71.5 required the licensee to comply with the applicable regulations of the Department of Transportation (DOT) in 49 CFR Parts 170 through 189 when transporting licensed material outside the confines of the plant or other place of use, or when delivering licensed material to a carrier for transport. 10 CFR 20.311(d)(1) required th licensee to prepare all radioactive waste transferred to a land disposal facility such that the wastelis classified in accordance with 10 CFR 61.55 and meets the waste characteristic requirements of 10 CFR 61.5 The inspector reviewed the procedures listed below and determined that they adequately addressed the following:
assuring that the receiver has a license to receive the material being shipped; assigning the form, quantity type, and proper shipping name of the material to be shipped; classifying waste.destined for burial; selecting the type of package required; labeling and marking the package; placarding the vehicle; assuring that the radiation and contamination limits are met; and preparing shipping paper HP/0/B/1006/01
"Procedure for Packaging and Shipment of Radioactive Materials" HP/0/B/1006/01A "Procedure for Packaging and Shipment of Radioactive Waste" The inspector reviewed the licensee's records for 5 recent shipments. Those records indicated that the shipments were made in accordance with the above procedures and Codes. No transportation incidents involving the licensee's shipments of radioactive material have occurred during the last three year Based on the above reviews, it was concludbd that the licensee had effectively implemented a program for shipping radioactive material No violations or deviations were identifie.
Solid Radioactive Waste Management (86750)
10 CFR 50.75 required the licensee to keep~records of information pertaining to the safe and effective decommissioning of the facility.-That information includes records of spills or other unusual occurrences involving the spread of contamination in and around the facility, equipment, or site. These records must include any known information on identification of involved nuclides, quantities, forms, and concentrations. Other pertinent information includes drawings of structures and equipment in restricted areas where radioactive materials are used and/or stored and of locations of possible inaccessible contamination such as buried pipes which may be subject to contaminatio The licensee's activities with regard to maintaining records of spills and disposing of contaminated soil from around the plant site were discussed with the licensee. The licensee indicated that there were only three areas outside of buildings which would require additional cleanup during decommissioning. Those areas, which were located around each of the three borated water storage tanks, had been contaminated by a spent fuel pool overflow. For records purposes, a drawing which denoted those areas as potential sources of radioactive soil and asphalt was included in section 5.1 of the Radiation Protection Manual. The contaminated soil removed from those areas following the spill was stored in a warehouse awaiting disposition. The licensee indicated that an application had been submitted for a state permit to operate an on-site landfill for hazardous waste. If the permit is granted, the landfill could be used for disposal of the contaminated soil; otherwise the soil would be shipped off-site for disposa Based on the above, it was concluded that the licensee had maintained the required records of spills involving the spread of contamination in and around the facilit No violations or deviations were identifie.
Exit Interview The inspection scope and results were summarized on September 3, 1992, with those persons indicated in Paragraph 1. The inspector described the areas inspected and discussed in detail the inspection results listed above. No dissenting comments were received from the license Proprietary information is not contained in this repor REPORT DETAILS Persons Contacted Licensee Employees
- H. Barron, Station Manager L. Benge, Technical Manager, Chemistry
- R. Bowser, Scientist, Radiation Protection
- Coy, Supervising Scientist, Radiation Protection
- B. Jones, Manager, Chemistry
- 0. Kohler, Licensing Coordinator, Compliance B. Norris, Senior Scientist, Chemistry
- Perry, Licensing Coordinator, Compliance
- D. Robinson, Shift Supervisor, Radiation'Protection T. Smith, Supervisor, Radiation Protection M. Thorne, General Supervisor, Radiation Protection
- C. Yongue, Manager, 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.
Post Accident Sampling Systems (84750)
Technical Specifications (TSs) 6.4.4 and 6.4.5 required the licensee to establish, implement, and maintain a program, which would ensure the capability to obtain and analyze samples of reactor coolant, containment atmosphere, and radioactive iodines and particulates in plant gaseous effluents under accident conditions. The program was required to include training of personnel, procedures for sampling and analysis, and provisions for testing and maintenance of sampling and analytical equipmen The licensee's program included the use of a Post Accident Liquid Sampling (PALS) systems for reactor coolant and a Post Accident Gas Sampling (PAGS) systems for containment atmosphere. The inspector reviewed section 3.10 of the licensee's Chemistry Manual, section 11.1 for the Radiation Protection Manual, procedures CP/e,2,&3/A/2002/04D "Test Procedure For Operation Of Thed Post Accident Liquid Sampling system", and procedures HP/C,2,&3/A/1009/17 "Operating Procedure For Post Accident Containment Air Sampling System". Those manuals and procedures included provisions for training of personnel in operation of the equipment,
periodic testing of the systems and acceptance criteria for analytical results obtained during those tests. A review of the selected licensee records for recent tests of the systems indicated that the systems were being adequately maintained and tested in accordance with the above manuals and procedure Based on the above reviews, it was concluded that the licensee had implemented an adequate program to ensure the capability to obtain and analyze samples of reactor coolant and containment atmosphere under accident condition No violations or deviations were identifie.
Water Chemistry (84750)
TSs 3.14, 3.15 and 4.1 described the operational and surveillance requirements for reactor coolant chemistry and total activity. Maximum concentration limits and sampling frequencies were specified for dissolved oxygen, chloride, fluoride, and total activit The inspector reviewed section 3.10 of the Oconee Chemistry Manual and determined it included provisions for sampling and analyzing reactor coolant for the TS required parameters at the specified frequencies. Sections 3.8 and 3.10 of the manual also included provisions for implementing, with a few exceptions, the Electric Power Research Institute (EPRI)
guidelines for PWR primary and secondary water chemistr The inspector also reviewed trend plots of analytical results for dissolved oxygen, chloride, fluoride, and dose equivalent iodine-131 (DEI) in reactor coolant. The trend plots reviewed included data generated for all three units during the period January through August 1992. Records for the three most recent semi-annual evaluations of reactor coolant total activity and records generated during August 1992 for selected primary and secondary parameters included in the EPRI guidelines were also examined. During steady state operations the dissolved oxygen concentrations were typically <1 ppb, chloride concentrations were typically
<20 ppb, and fluoride concentrations were typically <15 pp These parameters were well below their respective TS limits of 100 ppb, 150 ppb, and 150 ppb. The total activity of the reactor coolant for all three units was also well within its TS limit of 224/E. The Unit 1 DEI was typically 2 E-2 ACi/ml, the Unit 2 DEI was typically 2 E-2 ACi/ml, and the Unit 3 DEI was typically 2.5 E-1 ACi/ml. The other parameters selected for review were generally maintained within the EPRI guidelines.