IR 05000298/2007009

IR 05000298-07-009; 5/14/07 - 7/03/07; Cooper Nuclear Station Radiation Safety Team Inspection

ML072220134
Person / Time
Site:	Cooper
Issue date:	08/10/2007
From:	Shannon M Plant Support Branch Region IV
To:	Minahan S Nebraska Public Power District (NPPD)
References
IR-07-009
Download: ML072220134 (15)

Text

ust 10, 2007

SUBJECT:

COOPER NUCLEAR STATION - NRC RADIATION SAFETY TEAM INSPECTION REPORT 05000298/2007009

Dear Mr. Minahan:

On July 3, 2007, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your 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 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.

Nebraska Public Power District -2-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 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: 50-298 Licenses: DPR-46 Enclosure:

NRC Inspection Report 05000298/2007009 w/attachment: Supplemental Information Gene Mace Chairman Nuclear Asset Manager Nemaha County Board of Commissioners Nebraska Public Power District Nemaha County Courthouse P.O. Box 98 1824 N Street Brownville, NE 68321 Auburn, NE 68305 John C. McClure, Vice President Julia Schmitt, Manager and General Counsel Radiation Control Program Nebraska Public Power District Nebraska Health & Human Services P.O. Box 499 Dept. of Regulation & Licensing Columbus, NE 68602-0499 Division of Public Health Assurance 301 Centennial Mall, South P. V. Fleming, Licensing Manager P.O. Box 95007 Nebraska Public Power District Lincoln, NE 68509-5007 P.O. Box 98 Brownville, NE 68321 H. Floyd Gilzow Deputy Director for Policy Michael J. Linder, Director Missouri Department of Natural Resources Nebraska Department of P. O. Box 176 Environmental Quality Jefferson City, MO 65102-0176 P.O. Box 98922 Lincoln, NE 68509-8922 Director, Missouri State Emergency Management Agency P.O. Box 116 Jefferson City, MO 65102-0116

Nebraska Public Power District -3-Chief, Radiation and Asbestos Technological Hazards Branch Control Section National Preparedness Division Kansas Department of Health DHS/FEMA and Environment 9221 Ward Parkway Bureau of Air and Radiation Suite 300 1000 SW Jackson, Suite 310 Kansas City, MO 64114-3372 Topeka, KS 66612-1366 Daniel K. McGhee, State Liaison Officer Bureau of Radiological Health Iowa Department of Public Health Lucas State Office Building, 5th Floor 321 East 12th Street Des Moines, IA 50319 Melanie 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 50319 Ronald D. Asche, President and Chief Executive Officer Nebraska Public Power District 1414 15th Street Columbus, NE 68601 Kevin V. Chambliss, Director of Nuclear Safety Assurance Nebraska Public Power District P.O. Box 98 Brownville, NE 68321 John F. McCann, Director, Licensing Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601-1813 Keith G. Henke, Planner Division of Community and Public Health Office of Emergency Coordination 930 Wildwood, P.O. Box 570 Jefferson City, MO 65102 Ronald L. McCabe, Chief

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 Yes G No Initials: LTR O Publicly Available G Non-Publicly Available G Sensitive ONon-Sensitive RIV:PSB\SHP PSB\HP PSB\HP PSB\SHP C:PSB LTRicketson/lar BDBaca GLGuerra LCCarsonII MPShannon

/RA/ /RA/ /RA/ /RA/ /RA/

08/07/07 08/09/07 08/07/07 08/09/07 08/10/07 DRP\C C:PSB MCHay MPShannon

/RA/ /RA/

08/10/07 08/10/07 OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax

U.S. NUCLEAR REGULATORY COMMISSION

REGION IV

Dockets: 50-298 Licenses: DPR-46 Report: 05000298/2007009 Licensee: Nebraska Public Power District Facility: Cooper Nuclear Station Location: P.O. Box 98 Brownville, Nebraska Dates: 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 Branch Approved By: Michael P. Shannon, Chief Plant Support Branch Division of Reactor Safety-1- Enclosure

SUMMARY OF FINDINGS

IR 05000298/2007009; 5/14/07 - 7/03/07; Cooper Nuclear Station ; Radiation Safety Team

Inspection The report covered a four-day period of inspection on site by a team of four region-based health physics 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.

Cornerstone: Occupational Radiation Safety [OS] and Public Radiation Safety [PS]

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

• Licensee action in cases of repetitive deficiencies or significant individual deficiencies

• 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 The inspector completed nine of the required nine 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:

• Radiological effluent release reports since the last inspection, changes to the Offsite 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 radioactive gaseous 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 underground pipes 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 site and beyond the owner-controlled area

• 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 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 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.

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

• Collection and preparation of environmental samples

• 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 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

• Licensee event reports, special reports, audits, self-assessments and corrective action reports performed since the last inspection The inspector completed 10 of the required 10 samples.

b. Findings

No findings of significance were identified.

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)

b. Findings and Observations

No findings of significance were identified.

4OA6 Management Meetings

Exit Meeting Summary

On 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 Department

NRC

N. Taylor

LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED

NONE