IR 05000295/2009002
| ML090860846 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 03/26/2009 |
| From: | Christine Lipa Division of Nuclear Materials Safety III |
| To: | Pardee C Exelon Generation Co, Exelon Nuclear |
| References | |
| IR-09-002 | |
| Download: ML090860846 (8) | |
Text
March 26, 2009
SUBJECT:
NRC INSPECTION REPORT 050-00295/09-02(DNMS);
05000304/09-02(DNMS) - ZION NUCLEAR STATION
Dear Mr. Pardee:
On March 11, 2009, the NRC completed an inspection at the permanently shutdown Zion Nuclear Station. The purpose of the inspection was to determine whether decommissioning activities were conducted safely and in accordance with NRC requirements. Specifically, the inspector evaluated facility management control, spent fuel safety and radiological safety. At the conclusion of the inspection on March 11, 2009, the NRC inspector discussed the findings with members of your staff.
The inspection consisted of an examination of activities at the facility as they relate to safety and compliance with the Commissions rules and regulations. Areas examined during the inspection are identified in the enclosed report. Within these areas, the inspection consisted of a selective examination of procedures and representative records, field observations of activities in progress, and interviews with personnel.
Based on the results of this inspection, the NRC did not identify any violations.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be 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), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. We will gladly discuss any questions you may have regarding this inspection.
Sincerely,
/RA/
Christine A. Lipa, Chief
Materials Control, ISFSI, and
Decommissioning Branch
Docket No. 05000295; 05000304 License No. DPR-39; DPR-48
Enclosure:
Inspection Report 050-00295/09-02(DNMS); 050-00304/09-02(DNMS)
REGION III==
Docket No.:
050-00295; 050-00304
License No.:
Report No.:
050-00295/09-02(DNMS);
050-00304/09-02(DNMS)
Licensee:
Exelon Generation Company, LLC
Facility:
Zion Nuclear Station
Location:
101 Shiloh Boulevard
Zion, IL 60099
Date:
March 9, through 11, 2009
NRC Inspector:
Peter J. Lee, Ph.D., CHP
Health Physicist
Approved by:
Christine A. Lipa, Chief
Materials Control, ISFSI, and
Decommissioning Branch
Division of Nuclear Materials Safety
Enclosure EXECUTIVE SUMMARY
Zion Nuclear Station NRC Inspection Report 050-00295/09-02(DNMS); 05000304/09-02(DNMS)
This routine decommissioning inspection focused on the evaluation of the licensees facility management and control, spent fuel safety, and radiological safety.
Facility Management and Control
!
The inspector concluded that the licensee adequately implemented its audit and corrective action programs in accordance with the licensees Quality Assurance Program, and that the programs were consistent with NRC requirements. (Section 1.1)
Spent Fuel Safety
The inspector determined that the licensee properly maintained the spent fuel pool water level, temperature, chemistry, cleanliness control, and criticality control to ensure the safe wet storage of the spent fuel. The inspector also determined that the licensee had adequately performed the functional tests to ensure that abnormal spent fuel pool conditions would be made known to the operators in a timely fashion. (Section 2.1)
Radiological Safety
The inspector concluded that the licensee effectively monitored and controlled personnel exposures to radiation, and adequately controlled contamination. (Section 3.1)
The inspector concluded that the licensee effectively implemented radiological effluent control programs and processes. (Section 3.2)
Enclosure Report Details
Summary of Plant Activities
During the period covered by this inspection, the licensee maintained the spent fuel in storage within the spent fuel pool.
1.0 Facility Management and Control
1.1 Self-Assessment, Auditing, and Corrective Actions (IP 40801)
a.
Inspection Scope
The inspector reviewed the licensees annual audit (NOSA-ZIN-08-12), which was conducted from December 1, through December 12, 2008, and the Nuclear Procurement Issues Committees audit of the off-site laboratory (Audit #20110) conducted from September 29, through October 2, 2008. The inspector reviewed selected corrective action work orders, which were associated with deficiencies identified during the audits.
b.
Observations and Findings
The licensees annual audit included the evaluation of activities affecting plant systems, structures, and components necessary for the safe storage of spent fuel. The audit was consistent with license requirements in both scope and level of detail, and the licensee initiated appropriate corrective actions to resolve audit findings.
The Nuclear Procurement Issues Committee conducts off-site laboratory audits on a triennial basis. The off-site laboratory performed Part 61 and environmental sample analyses for the licensee. Audit #20110 was appropriately focused in both scope and level of detail and the findings identified were programmatic in nature and had no impact on the quality of products.
c.
Conclusions
The inspector concluded that the licensee adequately implemented its audit and corrective action programs in accordance with the licensees Quality Assurance Program, and that the programs were consistent with NRC requirements.
2.0 Spent Fuel Safety
2.1 Spent Fuel Pool Safety (IP 60801)
a.
Inspection Scope The inspector verified the safe wet storage of spent fuel in the fuel building. The review included spent fuel pool (SFP) instrumentation, alarms, cleanliness control, chemistry, criticality controls, and the results of the January 2009 through March 2009 spent fuel pool water temperatures, levels, and chemistry and gamma spectrum analyses. The inspector reviewed the records of functional tests of alarms to alert operating personnel by pager for: spent fuel pool high and low water level, high water temperature, fuel
Enclosure building high radiation, cooling tower pump trip, and abnormal fuel building ventilation system operation.
b.
Observations and Findings The results of the analyses reviewed indicated that all parameters were within procedural limits. The licensee maintained the boron concentration in the spent fuel pool at approximately 2,000 parts per million (ppm) versus the Technical Specifications limit of greater than 500 ppm.
The licensee had performed the monthly test of high radiation in the spent fuel pool area, and other annual functional tests to verify proper pager function in response to anticipated control room alarms affecting spent fuel pool safety. The licensees personnel were knowledgeable of all functional tests; and all tests were performed in accordance with the required procedures.
c.
Conclusions The inspector determined that the licensee properly maintained the spent fuel pool water level, temperature, chemistry, cleanliness control, and criticality control to ensure the safe wet storage of the spent fuel. The inspector also determined that the licensee had adequately performed the functional tests to ensure that abnormal spent fuel pool conditions would be made known to the operators in a timely fashion.
3.0 Radiological Safety
3.1 Occupational Radiation Exposure (83750)
a.
Inspection Scope The inspector reviewed the external dosimetry records for the second half of 2008. The inspector reviewed the general air sampling results, direct radiation survey, and smear sample results of the January 2009 through March 2009 Fuel Building and Auxiliary Building. The inspector reviewed the calibration procedures of the radiation survey meters and then observed licensees health physics technicians performing the calibration using the Shepherd model 89 calibrator.
b.
Observations and Findings The highest external radiation exposure received by workers during the second half of calendar year 2008 was 30 millirem. The results of the January 2009 through March 2009 general area air sampling did not indicate any results above ambient background levels, and routine quarterly surveys had not identified any significant removable contamination in the Fuel Building and the Auxiliary Building.
During the inspection, licensee health physics technicians performed calibrations of Eberline RO-2 and Teletector 6112 survey meters. The licensee health physics technicians were knowledgeable of calibrations; and all calibrations were performed in accordance with the required procedures.
Enclosure c.
Conclusions The inspector concluded that the licensee effectively monitored and controlled personnel exposures to radiation. The inspector also determined that the licensee effectively implemented its survey instrument calibration program to ensure adequate response of the instruments to radiation.
3.2 Radioactive Waste Treatment, Effluent, and Environmental Monitoring (IP 84750)
a.
Inspection Scope The inspector reviewed the records and selected analytical results of effluent releases from the Fuel Building and Auxiliary Building vents, and Turbine Building sump during the first quarter of 2009.
b.
Observations and Findings The licensees effluent release data did not indicate any positive results from licensed materials.
c.
Conclusions The inspector concluded that the licensee effectively implemented radiological effluent control programs and processes.
4.0 Exit Meeting
The inspectors presented the inspection results to licensee management at the conclusion of the inspection on March 11, 2009. The licensee acknowledged the findings presented did not identify any of the documents or processes reviewed by the inspectors as proprietary.
Attachment: Supplemental Information
Attachment
SUPPLEMENTAL INFORMATION
PARTIAL LIST OF PERSONS CONTACTED
- R. Schuster, Plant Manager
- J. Ashley, Design Engineering
- R Adams, Operations and Engineering Manager
- L. Cunningham, Security Project Manager
- M. Petersen, Administration/Training Supervisor
- Present at the March 19, 2008, exit meeting.
INSPECTION PROCEDURES (IP) USED
Spent Fuel Safety IP 83750
Occupational Radiation Exposure IP 40801 Self-Assessment, Auditing, and Corrective Actions IP 84750
Radioactive Waste Treatment, Effluent, and Environmental Monitoring
ITEMS OPENED, CLOSED, AND DISCUSSED
Opened
None
Closed
None
Discussed
None
LIST OF ACRONYMS USED
CFR
Code of Federal Regulations DNMS
Division of Nuclear Materials Safety IP
Inspection Procedure NRC
Nuclear Regulatory Commission SFP
Spent Fuel Pool