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=Text=
=Text=
{{#Wiki_filter:ril 2, 2008
{{#Wiki_filter:April 2, 2008


==SUBJECT:==
==SUBJECT:==
NRC INSPECTION REPORT 050-00295/08-01(DNMS) -
NRC INSPECTION REPORT 050-00295/08-01(DNMS) -  
 
ZION NUCLEAR STATION
ZION NUCLEAR STATION


Line 34: Line 35:


Sincerely,
Sincerely,
/RA/
/RA/  
Patrick L. Louden, Chief Decommissioning Branch Docket No. 05000295 License No. DPR-39
 
Patrick L. Louden, Chief  
 
Decommissioning Branch  
 
Docket No. 05000295 License No. DPR-39  


===Enclosure:===
===Enclosure:===
Inspection Report 050-00295/08-01(DNMS)
Inspection Report 050-00295/08-01(DNMS)  


REGION III==
REGION III==
Docket No.: 050-00295 License No.: DPR-39 Report No.: 050-00295/08-01(DNMS)
Docket No.:  
Licensee: Exelon Generation Company, LLC Facility: Zion Nuclear Station Location: 101 Shiloh Boulevard Zion, IL 60099 Date: March17 through 19, 2008 NRC Inspector: Peter J. Lee, Ph.D., CHP Health Physicist Approved by: Patrick L. Louden, Chief Decommissioning Branch Division of Nuclear Materials Safety
 
050-00295  
 
License No.:  
 
DPR-39  
 
Report No.:  
 
050-00295/08-01(DNMS)  
 
Licensee:  
 
Exelon Generation Company, LLC  
 
Facility:  
 
Zion Nuclear Station  
 
Location:  
 
101 Shiloh Boulevard  
 
Zion, IL 60099  
 
Date:  
 
March17 through 19, 2008  
 
NRC Inspector:  
 
Peter J. Lee, Ph.D., CHP  
 
Health Physicist  
 
Approved by:  
 
Patrick L. Louden, Chief  
 
Decommissioning Branch  
 
Division of Nuclear Materials Safety  
 
EXECUTIVE SUMMARY
 
Zion Nuclear Station
 
NRC Inspection Report 050-00295/08-01(DNMS)


EXECUTIVE SUMMARY Zion Nuclear Station NRC Inspection Report 050-00295/08-01(DNMS)
This routine decommissioning inspection focused on the evaluation of the licensees facility management and control, spent fuel safety, and radiological safety.
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
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)
 
! The inspector determined that the licensees process for evaluating the safety impacts of facility changes was in compliance with the requirements of 10 CFR Part 50.59.
!
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)  
 
!
The inspector determined that the licensees process for evaluating the safety impacts of facility changes was in compliance with the requirements of 10 CFR Part 50.59.
 
(Section 1.2)
 
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 determined that the licensee had complied with NRC and Department of Transportation regulations for shipments of radioactive materials. (Section 3.1)
 
The inspector concluded that the licensee effectively monitored and controlled personnel exposures to radiation, and adequately controlled contamination. (Section 3.2)
 
The inspector concluded that the licensee effectively implemented radiological effluent control programs and processes. (Section 3.3)
 
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 and transferred the spent resin to the shipping cast.
 
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-07-10), which was conducted from December 4 through December 14, 2007. The inspector reviewed selected corrective action work orders, which were associated with deficiencies identified during the annual audit.
 
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 annual audit was consistent with license requirements in both scope and level of detail, and the licensee initiated appropriate corrective actions to resolve audit findings.
 
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.
 
1.2 Safety Reviews, Design Changes, and Modifications (IP 37801)
 
a.
 
Inspection Scope


(Section 1.2)
The inspector reviewed the licensees safety screening reviews to verify that completed reviews were consistent with the requirements of 10 CFR Part 50.59. The review included selected screening reviews completed since October 2007.
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 determined that the licensee had complied with NRC and Department of Transportation regulations for shipments of radioactive materials. (Section 3.1)
The inspector concluded that the licensee effectively monitored and controlled personnel exposures to radiation, and adequately controlled contamination. (Section 3.2)
The inspector concluded that the licensee effectively implemented radiological effluent control programs and processes. (Section 3.3)


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 and transferred the spent resin to the shipping cast.
b.


1.0 Facility Management and Control 1.1 Self-Assessment, Auditing, and Corrective Actions (IP 40801)
Observations and Findings
a. Inspection Scope The inspector reviewed the licensees annual audit (NOSA-ZIN-07-10), which was conducted from December 4 through December 14, 2007. The inspector reviewed selected corrective action work orders, which were associated with deficiencies identified during the annual audit.


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 annual 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 licensees Administrative Procedure ZAP-100-06 was consistent with the NRCs guidance on 10 CFR 50.59 screening reviews. The licensee conducted several safety screening reviews of facility changes and none of the changes required a formal 10 CFR Part 50.59 safety evaluation.


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.
c.


1.2 Safety Reviews, Design Changes, and Modifications (IP 37801)
Conclusions
a. Inspection Scope The inspector reviewed the licensees safety screening reviews to verify that completed reviews were consistent with the requirements of 10 CFR Part 50.59. The review included selected screening reviews completed since October 2007.


b. Observations and Findings The licensees Administrative Procedure ZAP-100-06 was consistent with the NRCs guidance on 10 CFR 50.59 screening reviews. The licensee conducted several safety screening reviews of facility changes and none of the changes required a formal 10 CFR Part 50.59 safety evaluation.
The inspectors determined that the licensees process for evaluating the safety impacts of facility changes was in compliance with the requirements of 10 CFR 50.59.


3  Enclosure
2.0 Spent Fuel Safety


c. Conclusions The inspectors determined that the licensees process for evaluating the safety impacts of facility changes was in compliance with the requirements of 10 CFR 50.59.
2.1 Spent Fuel Pool Safety (IP 60801)


2.0 Spent Fuel Safety 2.1 Spent Fuel Pool Safety (IP 60801)
a.
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 2008 through March 2008 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 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 2000 parts per million (ppm) versus the Technical Specifications limit of greater than 500 ppm. The licensees personnel were knowledgeable of spent fuel pool water analyses, and all analyses were performed in accordance with the required procedures.
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 2008 through March 2008 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 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 2000 parts per million (ppm) versus the Technical Specifications limit of greater than 500 ppm. The licensees personnel were knowledgeable of spent fuel pool water analyses, and all analyses were performed in accordance with the required procedures.


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.
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.
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.
 
Enclosure
 
3.0 Radiological Safety
 
3.1 Solid Radioactive Waste Management and Transportation of Radioactive Materials (86750)
 
a.
 
Inspection Scope


3.0 Radiological Safety 3.1 Solid Radioactive Waste Management and Transportation of Radioactive Materials (86750)
The inspector reviewed radioactive material shipping documents and conducted interviews of the responsible individual to ensure compliance with NRC and U.S.
a. Inspection Scope The inspector reviewed radioactive material shipping documents and conducted interviews of the responsible individual to ensure compliance with NRC and U.S.


Department of Transportation (DOT) regulations.
Department of Transportation (DOT) regulations.


b. Observations and Findings On February 18, 2008, the licensee made one excepted quantity radioactive material shipment of safety injection pump. The licensees shipping manifest showed that personnel packaged, labeled, and marked the shipping container according to the DOT and 10 CFR Part 71 transportation requirements. The licensee verified that the results of radiation and removable contamination levels were within applicable limits.
b.
 
Observations and Findings  
 
On February 18, 2008, the licensee made one excepted quantity radioactive material shipment of safety injection pump. The licensees shipping manifest showed that personnel packaged, labeled, and marked the shipping container according to the DOT and 10 CFR Part 71 transportation requirements. The licensee verified that the results of radiation and removable contamination levels were within applicable limits.


c. Conclusions The inspector determined that the licensee had complied with NRC and Department of Transportation regulations for shipments of radioactive materials.
c.


3.2 Occupational Radiation Exposure (83750)
Conclusions
a. Inspection Scope The inspector reviewed the external dosimetry records for the second half of 2007. The inspector reviewed the general air sampling, direct radiation survey, and smear sample results from the Fuel Building and the Auxiliary Building from January 2008 to March 2008.
 
The inspector determined that the licensee had complied with NRC and Department of Transportation regulations for shipments of radioactive materials.
 
3.2 Occupational Radiation Exposure (83750)  
 
a.
 
Inspection Scope  
 
The inspector reviewed the external dosimetry records for the second half of 2007. The inspector reviewed the general air sampling, direct radiation survey, and smear sample results from the Fuel Building and the Auxiliary Building from January 2008 to March 2008.


The inspector reviewed the radiation work permit and exposure records during the transfer of spent resin from spent fuel pool demineralizer to shipping cast.
The inspector reviewed the radiation work permit and exposure records during the transfer of spent resin from spent fuel pool demineralizer to shipping cast.


b. Observations and Findings The highest dose received by the individuals was 77 mrem during the second half of 2007. The results of general area air sampling in the fuel and auxiliary buildings did not positively identify the presence of any licensed materials. The results of the routine quarterly surveys in the Fuel Building and the Auxiliary Building had not identified any significant removal contamination. Workers received doses less than the dose limits specified in radiation work permit.
b.
 
Observations and Findings  
 
The highest dose received by the individuals was 77 mrem during the second half of 2007. The results of general area air sampling in the fuel and auxiliary buildings did not positively identify the presence of any licensed materials. The results of the routine quarterly surveys in the Fuel Building and the Auxiliary Building had not identified any significant removal contamination. Workers received doses less than the dose limits specified in radiation work permit.
 
c.
 
Conclusions
 
The inspector concluded that the licensee effectively monitored and controlled personnel exposures to radiation, and adequately controlled contamination.
 
3.3 Radioactive Waste Treatment, Effluent, and Environmental Monitoring


c. Conclusions The inspector concluded that the licensee effectively monitored and controlled personnel exposures to radiation, and adequately controlled contamination.
a.


5  Enclosure
Inspection Scope (IP 84750)


3.3 Radioactive Waste Treatment, Effluent, and Environmental Monitoring a. Inspection Scope (IP 84750)
The inspector reviewed the records and selected analytical results of effluent releases from Fuel Building and Unit 2 vents, and Turbine Building fire sump during the first quarter of 2008.
The inspector reviewed the records and selected analytical results of effluent releases from Fuel Building and Unit 2 vents, and Turbine Building fire sump during the first quarter of 2008.


b. Observations and Findings The licensees gaseous effluent release data didnt indicate any positive results from the licensed materials. The liquid effluent release data demonstrated that the concentrations of released effluent conformed to limits in 10 CFR Part 20, Appendix B, Table 3.
b.
 
Observations and Findings  
 
The licensees gaseous effluent release data didnt indicate any positive results from the licensed materials. The liquid effluent release data demonstrated that the concentrations of released effluent conformed to limits in 10 CFR Part 20, Appendix B, Table 3.


c. Conclusions The inspector concluded that the licensee effectively implemented radiological effluent control programs and processes.
c.


4.0 Exit Meeting The inspectors presented the inspection results to licensee management at the conclusion of the inspection on March 19, 2008. The licensee acknowledged the findings presented did not identify any of the documents or processes reviewed by the inspectors as proprietary.
Conclusions


Attachment: Supplemental Information
The inspector concluded that the licensee effectively implemented radiological effluent control programs and processes.


SUPPLEMENTAL INFORMATION PARTIAL LIST OF PERSONS CONTACTED
4.0 Exit Meeting
* R. Schuster, Plant Manager
 
* J. Ashley, Design Engineering
The inspectors presented the inspection results to licensee management at the conclusion of the inspection on March 19, 2008. The licensee acknowledged the findings presented did not identify any of the documents or processes reviewed by the inspectors as proprietary.
* R Adams, Operations and Engineering Manager
 
* L. Cunningham, Security Project Manager
Attachment: Supplemental Information
* M. Petersen, Administration/Training Supervisor
 
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.
* Present at the March 19, 2008, exit meeting.


INSPECTION PROCEDURES (IP) USED IP 60801 Spent Fuel Safety IP 37801 Safety Reviews, Design Changes, and Modifications IP 83750 Occupational Radiation Exposure IP 40801 Self-Assessment, Auditing, and Corrective Actions IP 86750 Transportation of Radioactive Materials 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 NRC Nuclear Regulatory Commission Attachment
INSPECTION PROCEDURES (IP) USED  
 
IP 60801  
 
Spent Fuel Safety IP 37801  
 
Safety Reviews, Design Changes, and Modifications IP 83750  
 
Occupational Radiation Exposure IP 40801 Self-Assessment, Auditing, and Corrective Actions IP 86750  
 
Transportation of Radioactive Materials 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 NRC  
 
Nuclear Regulatory Commission
}}
}}

Latest revision as of 17:24, 14 January 2025

IR 05000295-08-001(DNMS), on 03/17 - 19/2008, Zion, Unit 1, Routine Decommissioning Inspection
ML080930452
Person / Time
Site: Zion File:ZionSolutions icon.png
Issue date: 04/02/2008
From: Louden P
NRC/RGN-III/DNMS/DB
To: Pardee C
Exelon Generation Co
References
IR-08-001
Download: ML080930452 (9)
v • d • e


Text

April 2, 2008

SUBJECT:

NRC INSPECTION REPORT 050-00295/08-01(DNMS) -

ZION NUCLEAR STATION

Dear Mr. Pardee:

On March 19, 2008, the NRC completed an inspection at the 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 organization and management controls, safety reviews, maintenance and surveillance, and radiological waste. At the conclusion of the inspection on March 19, 2008, 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). The NRCs document system is 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/

Patrick L. Louden, Chief

Decommissioning Branch

Docket No. 05000295 License No. DPR-39

Enclosure:

Inspection Report 050-00295/08-01(DNMS)

REGION III==

Docket No.:

050-00295

License No.:

DPR-39

Report No.:

050-00295/08-01(DNMS)

Licensee:

Exelon Generation Company, LLC

Facility:

Zion Nuclear Station

Location:

101 Shiloh Boulevard

Zion, IL 60099

Date:

March17 through 19, 2008

NRC Inspector:

Peter J. Lee, Ph.D., CHP

Health Physicist

Approved by:

Patrick L. Louden, Chief

Decommissioning Branch

Division of Nuclear Materials Safety

EXECUTIVE SUMMARY

Zion Nuclear Station

NRC Inspection Report 050-00295/08-01(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)

!

The inspector determined that the licensees process for evaluating the safety impacts of facility changes was in compliance with the requirements of 10 CFR Part 50.59.

(Section 1.2)

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 determined that the licensee had complied with NRC and Department of Transportation regulations for shipments of radioactive materials. (Section 3.1)

The inspector concluded that the licensee effectively monitored and controlled personnel exposures to radiation, and adequately controlled contamination. (Section 3.2)

The inspector concluded that the licensee effectively implemented radiological effluent control programs and processes. (Section 3.3)

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 and transferred the spent resin to the shipping cast.

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-07-10), which was conducted from December 4 through December 14, 2007. The inspector reviewed selected corrective action work orders, which were associated with deficiencies identified during the annual audit.

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 annual audit was consistent with license requirements in both scope and level of detail, and the licensee initiated appropriate corrective actions to resolve audit findings.

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.

1.2 Safety Reviews, Design Changes, and Modifications (IP 37801)

a.

Inspection Scope

The inspector reviewed the licensees safety screening reviews to verify that completed reviews were consistent with the requirements of 10 CFR Part 50.59. The review included selected screening reviews completed since October 2007.

b.

Observations and Findings

The licensees Administrative Procedure ZAP-100-06 was consistent with the NRCs guidance on 10 CFR 50.59 screening reviews. The licensee conducted several safety screening reviews of facility changes and none of the changes required a formal 10 CFR Part 50.59 safety evaluation.

c.

Conclusions

The inspectors determined that the licensees process for evaluating the safety impacts of facility changes was in compliance with the requirements of 10 CFR 50.59.

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 2008 through March 2008 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 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 2000 parts per million (ppm) versus the Technical Specifications limit of greater than 500 ppm. The licensees personnel were knowledgeable of spent fuel pool water analyses, and all analyses were performed in accordance with the required procedures.

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.

Enclosure

3.0 Radiological Safety

3.1 Solid Radioactive Waste Management and Transportation of Radioactive Materials (86750)

a.

Inspection Scope

The inspector reviewed radioactive material shipping documents and conducted interviews of the responsible individual to ensure compliance with NRC and U.S.

Department of Transportation (DOT) regulations.

b.

Observations and Findings

On February 18, 2008, the licensee made one excepted quantity radioactive material shipment of safety injection pump. The licensees shipping manifest showed that personnel packaged, labeled, and marked the shipping container according to the DOT and 10 CFR Part 71 transportation requirements. The licensee verified that the results of radiation and removable contamination levels were within applicable limits.

c.

Conclusions

The inspector determined that the licensee had complied with NRC and Department of Transportation regulations for shipments of radioactive materials.

3.2 Occupational Radiation Exposure (83750)

a.

Inspection Scope

The inspector reviewed the external dosimetry records for the second half of 2007. The inspector reviewed the general air sampling, direct radiation survey, and smear sample results from the Fuel Building and the Auxiliary Building from January 2008 to March 2008.

The inspector reviewed the radiation work permit and exposure records during the transfer of spent resin from spent fuel pool demineralizer to shipping cast.

b.

Observations and Findings

The highest dose received by the individuals was 77 mrem during the second half of 2007. The results of general area air sampling in the fuel and auxiliary buildings did not positively identify the presence of any licensed materials. The results of the routine quarterly surveys in the Fuel Building and the Auxiliary Building had not identified any significant removal contamination. Workers received doses less than the dose limits specified in radiation work permit.

c.

Conclusions

The inspector concluded that the licensee effectively monitored and controlled personnel exposures to radiation, and adequately controlled contamination.

3.3 Radioactive Waste Treatment, Effluent, and Environmental Monitoring

a.

Inspection Scope (IP 84750)

The inspector reviewed the records and selected analytical results of effluent releases from Fuel Building and Unit 2 vents, and Turbine Building fire sump during the first quarter of 2008.

b.

Observations and Findings

The licensees gaseous effluent release data didnt indicate any positive results from the licensed materials. The liquid effluent release data demonstrated that the concentrations of released effluent conformed to limits in 10 CFR Part 20, Appendix B, Table 3.

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 19, 2008. 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

IP 60801

Spent Fuel Safety IP 37801

Safety Reviews, Design Changes, and Modifications IP 83750

Occupational Radiation Exposure IP 40801 Self-Assessment, Auditing, and Corrective Actions IP 86750

Transportation of Radioactive Materials 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 NRC

Nuclear Regulatory Commission

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