IR 05000313/2006009
| ML061840025 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 06/30/2006 |
| From: | Shannon M Plant Support Branch Region IV |
| To: | Forbes J Entergy Nuclear Operations |
| References | |
| IR-06-009 | |
| Download: ML061840025 (16) | |
Text
une 30, 2006
SUBJECT:
ARKANSAS NUCLEAR ONE - NRC RADIATION SAFETY TEAM INSPECTION REPORT 05000313/2006009 AND 05000368/2006009
Dear Mr. Forbes:
On June 8, 2006, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Arkansas Nuclear One, Units 1 and 2, facility. The enclosed report documents the inspection findings, which were discussed at the conclusion of the inspection with you and other members of your staff.
The inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license.
The team reviewed selected procedures and records, observed activities, and interviewed personnel. Specifically, the team evaluated the inspection areas within the Radiation Protection Strategic Performance Area that are scheduled for review every two years. These areas are:
- Radiation Monitoring Instrumentation
- Radioactive Gaseous and Liquid Effluent Treatment and Monitoring Systems
- Radioactive Material Processing and Transportation
- Radiological Environmental Monitoring Program and Radioactive Material Control Program On the basis of the results of this inspection, no findings of significance were identified.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any) will be made available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component
Entergy Operations, Inc. -2-of NRCs document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Michael P. Shannon, Chief Plant Support Branch Division of Reactor Safety Dockets: 50-313 50-368 Licenses: DPR-51 NPF-6
Enclosure:
NRC Inspection Report 05000313/2006009 and 05000368/2006009 w/attachment: Supplemental Information
REGION IV==
Dockets: 50-313, 50-368 Licenses: DPR-51, NPF-6 Report: 05000313/2006009 and 05000368/2006009 Licensee: Entergy Operations, Inc.
Facility: Arkansas Nuclear One, Units 1 and 2 Location: Junction of Hwy. 64 W and Hwy 333 South Russellville, Arkansas Dates: June 5 - 8, 2006 Inspectors: Larry Ricketson, P.E., Senior Health Physicist, Plant Support Branch Bernadette Baca, Health Physicist, Plant Support Branch Gilbert Guerra, Health Physicist, Plant Support Branch Donald Stearns, Health Physicist, Plant Support Branch Binesh Tharakan, Health Physicist, Plant Support Branch Accompanied By: Joe Furia, Senior Health Physicist, Region I Approved By: Michael P. Shannon, Chief Plant Support Branch Division of Reactor Safety Enclosure
SUMMARY OF FINDINGS
IR 05000313/2006009, 05000368/2006009; 6/05/06-6/08/06; Arkansas Nuclear One, Units 1 and 2; Radiation Safety Team The report covered a four-day period of inspection on site by a team of five region-based health physics inspectors.
NRC-Identified and Self-Revealing Findings
No findings of significance were identified.
Licensee Identified Violations
None
REPORT DETAILS
RADIATION SAFETY
Cornerstones: Occupational Radiation Safety [OS] and Public Radiation Safety [PS] 2OS3 Radiation Monitoring Instrumentation and Protective Equipment (71121.03)
a. Inspection Scope
This area was inspected to determine the accuracy and operability of radiation monitoring instruments that are used for the protection of occupational workers and the adequacy of the program to provide self-contained breathing apparatus (SCBA) to workers. The team used the requirements in 10 CFR Part 20 and the licensees procedures required by Technical Specifications as criteria for determining compliance. The team interviewed licensee personnel and reviewed:
- Calibration of area radiation monitors associated with transient high and very high radiation areas and post-accident monitors used for remote emergency assessment
- Calibration of portable radiation detection instrumentation, electronic alarming dosimetry, and continuous air monitors used for job coverage
- Calibration of whole-body counting equipment and radiation detection instruments utilized for personnel and material release from the radiologically controlled area
- Self-assessments, audits, and Licensee Event Reports
- Corrective action program reports since the last inspection
- Calibration expiration and source response check currency on radiation detection instruments staged for use
- The licensees capability for refilling and transporting SCBA air bottles to and from the control room and operations support center during emergency conditions, status of SCBA staged and ready for use in the plant and associated surveillance records, and personnel qualification and training
- Qualification documentation for onsite personnel designated to perform maintenance on the vendor-designated vital components, and the vital component maintenance records for SCBA units Either because the conditions did not exist or an event had not occurred, no opportunities were available to review the following items:
- Licensee action in cases of repetitive deficiencies or significant individual deficiencies
The inspector completed 9 of the required 9 samples.
b. Findings
No findings of significance were identified.
2PS1 Radioactive Gaseous and Liquid Effluent Treatment and Monitoring Systems (71122.01)
a. Inspection Scope
This area was inspected to ensure that the gaseous and liquid effluent processing systems are maintained so that radiological releases are properly mitigated, monitored, and evaluated with respect to public exposure. The team used the requirements in 10 CFR Part 20; 10 CFR Part 50 Appendices A and I; the Offsite Dose Calculation Manual; and the licensees procedures required by Technical Specifications as criteria for determining compliance. The team interviewed licensee personnel and reviewed:
- The most current radiological effluent release reports, changes to radiation monitor setpoint calculation methodology, anomalous sampling results, effluent radiological occurrence performance indicator incidents, self-assessments, audits, and licensee event reports
- Gaseous and liquid release system component configurations
- Routine processing, sample collection, sample analysis, release of radioactive liquid and gaseous effluent, and radioactive liquid and gaseous effluent release permits and dose projections to members of the public
- Changes made by the licensee to the Offsite Dose Calculation Manual, the liquid or gaseous radioactive waste system design, procedures, or operation since the last inspection
- Monthly, quarterly, and annual dose calculations
- Surveillance test results involving air cleaning systems and stack or vent flow rates
- Instrument calibrations of discharge effluent radiation monitors and flow measurement devices, effluent monitoring system modifications, effluent radiation monitor alarm setpoint values, and counting room instrumentation calibration and quality control
- Interlaboratory comparison program results
- Licensee event reports, special reports, audits, self-assessments and corrective action reports performed since the last inspection
- Program for identifying contaminated spills and leakage and the licensee's process for control and assessment; licensee's understanding of the location and
construction of underground pipes and tanks and storage pools that contain radioactive contaminated liquids; the licensee's capabilities of detecting spills or leaks and identifying groundwater radiological contamination both on site and beyond the owner-controlled area Either because the conditions did not exist or an event had not occurred, no opportunities were available to review the following items:
- Abnormal releases The inspector completed 11 of the required 11 samples.
b. Findings
No findings of significance were identified.
2PS2 Radioactive Material Processing and Transportation (71122.02)
a. Inspection Scope
This area was inspected to verify that the licensees radioactive material processing and transportation program complies with the requirements of 10 CFR Parts 20, 61, and 71 and Department of Transportation regulations contained in 49 CFR Parts 171-180. The team interviewed licensee personnel and reviewed:
- The radioactive waste system description, recent radiological effluent release reports, and the scope of the licensees audit program
- Liquid and solid radioactive waste processing systems configurations, the status and control of any radioactive waste process equipment that is not operational or is abandoned in place, changes made to the radioactive waste processing systems since the last inspection, and current processes for transferring radioactive waste resin and sludge discharges
- Radio-chemical sample analysis results for radioactive waste streams and use of scaling factors and calculations to account for difficult-to-measure radionuclides
- Shipment packaging, surveying, labeling, marking, placarding, vehicle checking, driver instructing, and disposal manifesting
- Shipping records for nonexcepted package shipments
- Licensee event reports, special reports, audits, state agency reports, self-assessments and corrective action reports performed since the last inspection The inspector completed 6 of the required 6 samples.
b. Findings
No findings of significance were identified.
2PS3 Radiological Environmental Monitoring Program (REMP) and Radioactive Material Control Program (71122.03)
a. Inspection Scope
This area was inspected to ensure that the REMP verifies the impact of radioactive effluent releases to the environment and sufficiently validates the integrity of the radioactive gaseous and liquid effluent release program; and that the licensees surveys and controls are adequate to prevent the inadvertent release of licensed materials into the public domain. The team used the requirements in 10 CFR Part 20, Appendix I of 10 CFR Part 50, the Offsite Dose Calculation Manual, and the licensees procedures required by technical specifications as criteria for determining compliance. The team interviewed licensee personnel and reviewed
- Annual environmental monitoring reports and licensee event reports
- Selected air sampling and thermoluminescence dosimeter monitoring stations
- Operability, calibration, and maintenance of meteorological instruments
- Each event documented in the Annual Environmental Monitoring Report which involved a missed sample, inoperable sampler, lost thermoluminescence dosimeter, or anomalous measurement
- Significant changes made by the licensee to the Offsite Dose Calculation Manual as the result of changes to the land census or sampler station modifications since the last inspection
- Calibration and maintenance records for air samplers, composite water samplers, and environmental sample radiation measurement instrumentation, quality control program, interlaboratory comparison program results, and vendor audits
- Locations where the licensee monitors potentially contaminated material leaving the controlled access area and the methods used for control, survey, and release from these areas
- Type of radiation monitoring instrumentation used to monitor items released, survey and release criteria of potentially contaminated material, radiation detection sensitivities, procedural guidance, and material release records
- Licensee event reports, special reports, audits, self-assessments and corrective action reports performed since the last inspection Either because the conditions did not exist or an event had not occurred, no opportunities were available to review the following items:
- Collection and preparation of environmental samples The inspector completed 10 of the required 10 samples.
b. Findings
No findings of significance were identified.
OTHER ACTIVITIES
4OA2 Problem Identification and Resolution
a. Inspection Scope
The team evaluated the effectiveness of the licensees problem identification and resolution process with respect to the following inspection areas:
- Radiation Monitoring Instrumentation (Section 2OS3)
- Radioactive Gaseous and Liquid Effluent Treatment and Monitoring Systems (Section 2PS1)
- Radioactive Material Processing and Transportation (Section 2PS2)
- Radiological Environmental Monitoring Program and Radioactive Material Control Program (Section 2PS3)
a. Findings and Observations
No findings of significance were identified.
4OA6 Management Meetings
Exit Meeting Summary
On June 8, 2006, the team presented the inspection results to Mr. J. Forbes, Vice President Operations, and other members of the staff who acknowledged the findings.
The team confirmed that proprietary information was not provided or examined during the inspection.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee personnel
- D. Calloway, Environmental Specialist, Chemistry
- G. Carothers, Journeyman Instrument Technician, Instrument and Control
- G. Damron, Health Physicist, Radiation Protection
- J. Forbes, Vice President Operations
- M. Frala, Supervisor, Chemistry
- A. Hawkins, Specialist, Licensing
- P. Killane, Health Physicist, Radiation Protection
- D. Marvel, Supervisor, Radiation Protection
- M. McCullah, Technician, Radiation Protection
- T. Mitchell, General Manager, Plant Operations
- D. Moore, Superintendent, Radiation Protection
- D. Norman, Health Physicist, Radiation Protection
- G. Stephenson, Specialist, Chemistry
- J. Tarvin, Supervisor, Instrument and Control
- T. Wilkins, Maintenance Instrument and Control Specialist-Nuclear, Maintenance
- M. Frala, Supervisor, Chemistry
NRC personnel
- E. Crowe, Resident Inspector
- J. Kirkland, Project Engineer
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
Opened
NONE Opened and Closed During this Inspection NONE