IR 05000313/2006009

IR 05000313-06-009, 05000368-06-009; 6/05/06-6/08/06; Arkansas Nuclear One, Units 1 and 2; Radiation Safety Team

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

June 30, 2006Jeffrey S. ForbesVice President Operations Arkansas Nuclear One Entergy Operations, Inc.

1448 S.R. 333 Russellville, AR 72801-0967SUBJECT:ARKANSAS NUCLEAR ONE - NRC RADIATION SAFETY TEAM INSPECTIONREPORT 05000313/2006009 AND 05000368/2006009

Dear Mr. Forbes:

On June 8, 2006, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection atyour Arkansas Nuclear One, Units 1 and 2, facility. The enclosed report documents theinspection 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 andcompliance with the Commission's 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 ProtectionStrategic 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 ControlProgram 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, itsenclosure, and your response (if any) will be made available electronically for public inspectionin the NRC Public Document Room or from the Publicly Available Records (PARS) com ponent Entergy Operations, Inc.-2-of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site athttp://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,

/RA/Michael P. Shannon, ChiefPlant Support Branch Division of Reactor SafetyDockets: 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, 50-368Licenses:DPR-51, NPF-6 Report:05000313/2006009 and 05000368/2006009 Licensee:Entergy Operations, Inc.

Facility:Arkansas Nuclear One, Units 1 and 2Location:Junction of Hwy. 64 W and Hwy 333 SouthRussellville, ArkansasDates: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 BranchAccompanied By:Joe Furia, Senior Health Physicist, Region IApproved By:Michael P. Shannon, ChiefPlant Support Branch Division of Reactor Safety Enclosure-2-

SUMMARY OF FINDINGS

IR 05000313/2006009, 05000368/2006009; 6/05/06-6/08/06; Arkansas Nuclear One, Units 1and 2; Radiation Safety Team The report covered a four-day period of inspection on site by a team of five region-based healthphysics inspectors. A.

NRC-Identified and Self-Revealing Findings

No findings of significance were identified.

B.Licensee Identified Violations

None

Enclosure-3-

REPORT DETAILS

2.RADIATION SAFETY Cornerstones: Occupational Radiation Safety [OS] and Public Radiation Safety [PS]2OS3Radiation Monitoring Instrumentation and Protective Equipment (71121.03)

a. Inspection Scope

This area was inspected to determine the accuracy and operability of radiation monitoringinstruments that are used for the protection of occupational workers and the adequacy ofthe program to provide self-contained breathing apparatus (SCBA) to workers. The team used the requirements in 10 CFR Part 20 and the licensee's 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 highradiation areas and post-accident monitors used for remote emergency assessment*Calibration of portable radiation detection instrumentation, electronic alarmingdosimetry, and continuous air monitors used for job coverage *Calibration of whole-body counting equipment and radiation detection instrumentsutilized 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 detectioninstruments staged for use *The licensee's capability for refilling and transporting SCBA air bottles to and fromthe control room and operations support center during emergency conditions, status of SCBA staged and ready for use in the plant and associated surveillancerecords, and personnel qualification and training*Qualification documentation for onsite personnel designated to performmaintenance 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 opportunitieswere available to review the following items:*Licensee action in cases of repetitive deficiencies or significant individualdeficiencies

-4-The inspector completed 9 of the required 9 samples.

b. Findings

No findings of significance were identified.2PS1Radioactive 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 processingsystems 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 licensee's 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 monitorsetpoint 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 radioactiveliquid 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 liquidor gaseous radioactive wast e system design, procedures, or operation since thelast 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 flowmeasurement devices, effluent monitori ng system modifications, effluent radiationmonitor alarm setpoint values, and counting room instrumentation calibration and quality control *Interlaboratory comparison program results

• Licensee event reports, special reports, audits, self-assessments and correctiveaction reports performed since the last inspection*Program for identifying contaminated spills and leakage and the licensee's processfor control and assessment; licensee's understanding of the location and

-5-construction of underground pipes and tanks and storage pools that containradioactive contaminated liquids; the licensee's capabilities of detecting spills orleaks and identifying groundwater radiological contamination both on site and beyond the owner-controlled areaEither because the conditions did not exist or an event had not occurred, no opportunitieswere 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.2PS2Radioactive Material Processing and Transportation (71122.02)

a. Inspection Scope

This area was inspected to verify that the licensee's radioactive material processing andtransportation 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 releasereports, and the scope of the licensee's audit program*Liquid and solid radioactive waste processing systems configurations, the statusand control of any radioactive waste process equipment that is not operational or is abandoned in place, changes made to the radioactive waste processi ng systemssince 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 ofscaling 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.

-6-

b. Findings

No findings of significance were identified.2PS3Radiological Environmental Monitoring Program (REMP) and Radioactive MaterialControl Program (71122.03)

a. Inspection Scope

This area was inspected to ensure that the REMP verifies the impact of radioactiveeffluent releases to the environment and sufficiently validates the integrity of theradioactive gaseous and liquid effluent release program; and that the licensee's 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 licensee's 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 whichinvolved a missed sample, inoperable sampler, lost thermoluminescence dosimeter, or anomalous measurement *Significant changes made by the licensee to the Offsite Dose Calculation Manualas 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 controlprogram, interlaboratory comparison program results, and vendor audits *Locations where the licensee monitors potentially contaminated material leavingthe 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 correctiveaction reports performed since the last inspection Either because the conditions did not exist or an event had not occurred, noopportunities were available to review the following items:

-7-*Collection and preparation of environmental samples The inspector completed 10 of the required 10 samples.

b. Findings

No findings of significance were identified.4.OTHER ACTIVITIES 4OA2Problem Identification and Resolution

a. Inspection Scope

The team evaluated the effectiveness of the licensee's problem identification andresolution 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 ControlProgram (Section 2PS3)

a. Findings and Observations

No findings of significance were identified.4OA6Management MeetingsExit Meeting SummaryOn June 8, 2006, the team presented the inspection results to Mr. J. Forbes, VicePresident 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, ChemistryNRC pers onnel

E. Crowe, Resident Inspector

J. Kirkland, Project Engineer

LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED

OpenedNONEOpened and Closed During this InspectionNONE

Section 2OS3: Radiation Monitoring Instrumentation and Protective EquipmentAudits and Self-AssessmentsLO-ALO-2005-00090,

CA-10