IR 05000298/2007009

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August 10, 2007

Stewart B. Minahan, Vice President-Nuclear and CNO Nebraska Public Power District P.O. Box 98 Brownville, NE 68321

SUBJECT: COOPER NUCLEAR STATION - NRC RADIATION SAFETY TEAMINSPECTION REPORT 05000298/2007009

Dear Mr. Minahan:

On July 3, 2007, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection atyour Cooper Nuclear Station 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 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 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 ControlProgramOn the basis of the results of this inspection, no findings of significance were identified.

Nebraska Public Power District-2-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 inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's 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, ChiefPlant Support Branch Division of Reactor SafetyDockets: 50-298Licenses: DPR-46

Enclosure:

NRC Inspection Report 05000298/2007009

w/attachment:

Supplemental InformationGene MaceNuclear Asset Manager Nebraska Public Power District P.O. Box 98 Brownville, NE 68321John C. McClure, Vice President and General Counsel Nebraska Public Power District P.O. Box 499 Columbus, NE 68602-0499P. V. Fleming, Licensing ManagerNebraska Public Power District P.O. Box 98 Brownville, NE 68321Michael J. Linder, DirectorNebraska Department of Environmental Quality P.O. Box 98922 Lincoln, NE 68509-8922ChairmanNemaha County Board of Commissioners Nemaha County Courthouse 1824 N Street Auburn, NE 68305Julia Schmitt, ManagerRadiation Control Program Nebraska Health & Human Services Dept. of Regulation & Licensing Division of Public Health Assurance 301 Centennial Mall, South P.O. Box 95007 Lincoln, NE 68509-5007H. Floyd GilzowDeputy Director for Policy Missouri Department of Natural Resources P. O. Box 176 Jefferson City, MO 65102-0176Director, Missouri State Emergency Management Agency P.O. Box 116 Jefferson City, MO 65102-0116 Nebraska Public Power District-3-Chief, Radiation and Asbestos Control Section Kansas Department of Health and Environment Bureau of Air and Radiation 1000 SW Jackson, Suite 310 Topeka, KS 66612-1366Daniel K. McGhee, State Liaison OfficerBureau of Radiological Health Iowa Department of Public Health Lucas State Office Building, 5th Floor 321 East 12th Street Des Moines, IA 50319Melanie Rasmussen, Radiation Control Program Director Bureau of Radiological Health Iowa Department of Public Health Lucas State Office Building, 5th Floor 321 East 12th Street Des Moines, IA 50319Ronald D. Asche, President and Chief Executive Officer Nebraska Public Power District 1414 15th Street Columbus, NE 68601Kevin V. Chambliss, Director of Nuclear Safety Assurance Nebraska Public Power District P.O. Box 98 Brownville, NE 68321John F. McCann, Director, LicensingEntergy Nuclear Northeast Entergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601-1813Keith G. Henke, PlannerDivision of Community and Public Health Office of Emergency Coordination 930 Wildwood, P.O. Box 570 Jefferson City, MO 65102Ronald L. McCabe, ChiefTechnological Hazards BranchNational Preparedness Division DHS/FEMA 9221 Ward Parkway Suite 300 Kansas City, MO 64114-3372 Nebraska Public Power District-4-Electronic distribution by RIV:Regional Administrator (BSM1)DRP Director (ATH)DRS Director (RJC1)DRS Deputy Director (WBJ)Senior Resident Inspector (NHT)Branch Chief, DRP/C (MCH2)Senior Project Engineer, DRP/C (WCW)Team Leader, DRP/TSS (CJP)RITS Coordinator (MSH3)DRS STA (DAP)M. Kunowski, OEDO RIV Coordinator (MAK3)D. Pelton, OEDO, RIV Coordinator (DLP1)ROPreports CNS Site Secretary (SEF1)SUNSI Review Completed: LTR ADAMS: O YesG No Initials: LTR O Publicly Available G Non-Publicly Available G SensitiveONon-SensitiveRIV:PSB\SHPPSB\HPPSB\HPPSB\SHPC:PSBLTRicketson/larBDBacaGLGuerraLCCarsonIIMPShannon/RA//RA//RA//RA//RA/08/07/0708/09/0708/07/0708/09/0708/10/07DRP\CC:PSBMCHayMPShannon/RA//RA/08/10/0708/10/07OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax Enclosure-1-U.S. NUCLEAR REGULATORY COMMISSION REGION IV Dockets:50-298Licenses:DPR-46 Report:05000298/2007009 Licensee:Nebraska Public Power District Facility:Cooper Nuclear Station Location:P.O. Box 98Brownville, NebraskaDates:May 14 through July 3, 2007 Inspectors:Larry Ricketson, P.E., Senior Health Physicist, Plant Support Branch Louis C. Carson II, Senior Health Physicist, Plant Support Branch Bernadette Baca, Health Physicist, Plant Support Branch Gilbert L. Guerra, C.H.P., Health Physicist, Plant Support BranchApproved By:Michael P. Shannon, ChiefPlant Support Branch Division of Reactor Safety Enclosure-2-

SUMMARY OF FINDINGS

IR 05000298/2007009; 5/14/07 - 7/03/07; Cooper Nuclear Station ; Radiation Safety TeamInspectionThe report covered a four-day period of inspection on site by a team of four region-based healthphysics inspectors. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process," Revision 4, dated December 2006.A.NRC-Identified and Self-Revealing Findings

===Cornerstone: Occupational Radiation Safety [OS] and Public Radiation Safety [PS]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 of the 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

• Licensee action in cases of repetitive deficiencies or significant individualdeficiencies*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 surveillance records, 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 The inspector completed nine of the required nine samples.

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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 fordetermining compliance. The team interviewed licensee personnel and reviewed: *Radiological effluent release reports since the last inspection, changes to theOffsite Dose Calculation Manual, radiation monitor setpoint calculation methodology, anomalous sampling results, effluent radiological occurrence performance indicator incidents, program for identifying contaminated spills and leakage and the licensee's process for control and assessment, self-assessments, audits, and licensee event reports*Gaseous and liquid release system component configurations

• Routine processing, sample collection, sample analysis, and release of radioactivegaseous effluent and review of release permits and dose projections to members of the public *Abnormal releases

• The licensee's understanding of the location and construction of undergroundpipes and tanks and storage pools that contain radioactive contaminated liquids; the technical bases for onsite monitoring, the licensee's capabilities of detecting spills or leaks and identifying groundwater radiological contamination both on siteand beyond the owner-controlled area*Changes made by the licensee to the Offsite Dose Calculation Manual, the liquidor 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

-5-*Instrument calibrations of discharge effluent radiation monitors and flowmeasurement 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 correctiveaction reports performed since the last inspectionThe 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 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 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 non-excepted 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 six of the required six samples.

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b. Findings

No findings of significance were identified.2PS3Radiological Environmental Monitoring Program (REMP) and Radioactive Material ControlProgram (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 the radioactive 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

• Collection and preparation of environmental samples

• 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 control program, interlaboratory comparison program results, and vendor audits*Locations where the licensee monitors potentially contaminated material leavingthe radiological controlled 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

-7-*Licensee event reports, special reports, audits, self-assessments and correctiveaction reports performed since the last inspectionThe inspector completed 10 of the required 10 samples.

b. Findings

No findings of significance were identified.4.OTHER ACTIVITIES4OA2Problem 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)

b. Findings and Observations

No findings of significance were identified.4OA6Management MeetingsExit Meeting SummaryOn July 3, 2007, the team presented the inspection results to Mr. Stewart B. Minahan,Vice President-Nuclear and Chief Nuclear Officer, 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

G. Armknecht, Radiological Specialist

B. Duncan, Radiation Protection Technician, Environmental

K. Fike, Supervisor, Chemistry

S. Freling, Radiological Specialist

J. Kuttler, Staff Health Physicist, Radiation Protection Department

J. Larson, Supervisor, Quality Assurance

L. Maine, Technician, Chemistry

R. McDonald, Staff Health Physicist, Radiation Protection Department

D. Sabine, Radwaste Operations Specialist, Operations Department

C. Stipp, Environmental, Corporate

K. Tanner, Manager, Radiation Protection

J. Teten, Supervisor, Chemistry

D. Van Der Kamp, Supervisor, Licensing

J. White, Radiological Protection Technician, Radiation Protection Department

B. Williams, Radiation Protection Technician, Radiation Protection Department

R. Willis, Radwaste Operations Specialist, Operations DepartmentNRCN. Taylor

LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED

NONE

Section 2OS3: Radiation Monitoring Instrumentation and Protective EquipmentProcedures9.ALARA.3In-Vitro and In-Vivo Bioassays, Revision 19.ALARA.11Operation of the

PM-7 Passive Monitor, Revision 1

9.ALARA.13Radiation Worker and Tour Group Dosimetry Management, Revision 6

9.INST.10Eberline Model

PM-7 Portal Monitor, Revision 2

9.INST.47Eberline Personnel Contamination Monitor Model

PCM-2, Revision 2

9.INST.48Siemens Mk 2.X Electronic Dosimeter System, Revision 1

9.INST.55Eberline Model

ASP-1 With Model NRD Neutron Detector, Revision 1

9.INST.56Portable Alpha Meter Ludlum Model 2, Revision 0

9.INST.61Merlin Gerin

AMP-100/AMP-200, Revision 2

9.RESP.2Self-Contained Breathing Apparatus, Revision 13

AttachmentA-2Condition Reports2005-051792005-0088512005-088552006-005832006-024782006-027722006-099282007-0000582007-009542007-034852007-035142007-03518Audit and Self-AssessmentsCooper Nuclear Station Quality Assurance Surveillance Report QAD20070017, April 3,, 2007NUPIC Audit/Survey:

Thermo Electro Radiation Measurement and Protection Audit No. 19042, October 22, 2004,

NUPIC Audit/Survey of Thermo Electro Radiation Measurement and Protection Audit No. 19070, October 22, 2004, Calibration RecordsIdentification Number 378, Eberline

PCM-2, February, 2007Identification Number 401, Eberline

PCM-2,

28, 2006

Identification Number 483, Eberline

PM-7, December 1, 2006

Identification Number 488, Eberline

PM-7, May 4, 2007

Identification Number 490, Eberline

PM-7, September 6, 2006

Identification Number 363-375,

SAM-11 Tool Contamination Monitor, March 19, 2007

Identification Number 431-446,

SAM-11 Tool Contamination Monitor, March 19, 2007

Identification Number 60375, Ludlum-2 Alpha Meter, May 17, 2007

Identification Number 20860, Ludlum-2 Alpha Meter, January 30, 2007

Identification Number 353,

ASP-1 Neutron Detector, July 14, 2006

Identification Number 354,

ASP-1 Neutron Detector, September 15, 2006

Identification Number 355,

ASP-1 Neutron Detector, January 27, 2006

Identification Number 466,

ASP-1 Neutron Detector, August 8, 2006Surveillance Procedures6

PRM.312 Reactor Building Kaman Monitor Channel Functional Test, Revision 76

PRM.315 Turbine Building Kaman Monitor Channel Functional Test, Revision 5

6.PRM.322Containment High Range Area Monitor Channel Calibration and SetpointDetermination, Revision 106.PRM.331SW Radiation Monitor - A Calibration Check and Instrument Channel TestRevision 66.PRM.332SW Radiation Monitor - B Calibration Check and Instrument Channel TestRevision 5

Section 2PS1: Radioactive Gaseous and Liquid Effluent Treatment and MonitoringSystemsAudits and Self-AssessmentsS07-05Quality Assurance Surveillance Report - Radiological EffluentsCondition Reports2005-066112005-068682005-076272006-009922007-000472007-000582007-01308

AttachmentA-3Procedures6.HV.104Control Room Emergency Fan Charcoal and HEPA Filter Leak Test, Fan Capacityand Charcoal Sampling, Revision 126.HV.105Control Room Envelope Pressurization Test, Revision 11

8.8.8Particulate and Iodine Sample Collection for Effluent Monitors and Drywell AirMonitor, Revision 348.8.11Liquid Radioactive Waste Discharge Authorization, Revision 27

8.8.15Noble Gas Sample Collection for Effluent Monitors and Drywell Air Monitor,Revision 28.11.1Effects Program, Revision 14MiscellaneousAction Plan for Tritium in Groundwater, July 31, 2006Offsite Dose Calculation Manual

Section 2PS2:

Radioactive Material Processing and TransportationAudits and SurveillancesQuality Assurance Audit 06-08Quality Assurance Reports S408-0501 and S07-05Condition Reports2005-042472005-060582005-066132005-066222005-066242005-068672006-052952006-05527Procedures0.PCP.1Process Control Program (PCP), Revision 09.ENN-RP-106-1Radiation and Contamination Surveys, Revision 3

9.RADOP.13Survey Techniques and Radiological Hazards of Failed Fuel Situations,Revision 09.RW.1Radioactive Shipments, Revision 19

9.RW.2Condensate Waste Resins, Spent Resins, RWCU Resins, and WasteSludge Classification and Listing, Revision 109.RW.3Dry Radioactive Waste Classification/listing and Radioactive MaterialShipments, Revision 39.RW.7Waste Stream Sampling, Revision 9

Shipping Packages05-13,

06-06R,

06-06T,

06-06WW,

07-05,

07-06Miscellaneous2005 and 2006 Scaling Factor ReportsCooper Nuclear Station Radioactive Material Shipment Log for 2005 and 2006

User's Information Package for US DOT Specification 7A Type A 14-210L, 14-210H and

14-215 Transportation Casks;

RSM-A : Technical 3002, Cask Handling Procedure AttachmentA-4

Section 2PS3:

Radiological Environmental Monitoring Program (REMP) And RadioactiveMaterial Control ProgramProcedures9.ENN-RP-106-1 Radiation and Contamination Surveys, Revision 30-QA-09Supplier Evaluation Process, Revision 1

9.ENV.1CNS Radiological Environmental Monitoring Program Administration, Revision 09.ENV.2Sampling Manual for the CNS REMP, Revision 2

9.ENV.3Action Levels for Environmental Samples, Revision 1

9.ENV.4CNS Environmental Air Pump Calibration and Maintenance, Revision 2

9.ENV.5Annual Review of Broadleaf Vegetation Sample Locations Procedure, Revision 0

9.ENV.6Annual CNS Land Use Census, Revision 0

9.ENV.7CNS Temporary LLRW Storage Facility Sampling Program, Revision 0

9.ENV.8Administering the CNS Meteorological Program, Revision 0Corrective Action Documents2005-053592005-053992005-054312005-056592005-065112005-065182005-083452005-089732005-091782006-078312006-083322007-02336

2007-023372007-024982007-035122007-03513Audits and AssessmentsNupic Audit Report of Teledyne-Brown Engineering-Environmental Services-

3/12/01, 3/25/03, 1/10/06Quality Assurance Surveillance Reports- S07-05, "Radiological Effluents," 4/3/07Cooper Nuclear Station 2005 Environmental Assessment Report, Sept. 26-28, 2005

Cooper Nuclear Station 2006 Environmental Assessment Report, May 22-June 7, 2006

Cooper Nuclear Station 2007 Environmental Assessment Report, March 5-15, 2007CalibrationsEnvironmental air pump maintenance document and log14.MET.301, "Meteorological Maintenance Procedure for 10-Meter Tower"- 4/3/07, 9/13/06, 4/7/06, 10/5/05, 4/6/0514.MET.302, "Meteorological Maintenance Procedure for 100-Meter Tower - System A"- 4/3/07, 9/12/06, 4/4/06, 12/13/05, 9/27/05, 8/4/05, 4/4/0514.MET.303, "Meteorological Maintenance Procedure for 100-Meter Tower - System B"- 4/3/07, 9/12/06, 4/5/06, 9/27/05, 4/6/05MiscellaneousRadiological Protection Position Paper (P)97-01 R2TLD Location Upgrade (White Paper)

Annual Radiological Environmental Operating Report for 2005 and 2006

Radioactive Effluent Release Report for 2005 and 2006