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{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I475 ALLENDALE ROADKING OF PRUSSIA, PENNSYLVANIA 19406-1415 April 11, 2007Docket No. 05000213License No. DPR-61 Mr. Wayne A. NortonPresident and Chief Executive Officer Connecticut Yankee Atomic Power Company 362 Injun Hollow Road East Hampton, CT 06424-3099SUBJECT:INSPECTION 05000213/2006003, CONNECTICUT YANKEE ATOMIC POWERCOMPANY, EAST HAMPTON, CONNECTICUT SITE
{{#Wiki_filter:UNITED STATES ril 11, 2007
 
==SUBJECT:==
INSPECTION 05000213/2006003, CONNECTICUT YANKEE ATOMIC POWER COMPANY, EAST HAMPTON, CONNECTICUT SITE


==Dear Mr. Norton:==
==Dear Mr. Norton:==
On March 30, 2007, the United States Nuclear Regulatory Commission completed anannounced inspection at your Haddam Neck facility. The enclosed report (Enclosure 1)
On March 30, 2007, the United States Nuclear Regulatory Commission completed an announced inspection at your Haddam Neck facility. The enclosed report (Enclosure 1)
documents the inspection results which were discussed with Mr. G. van Noordennen and other members of your staff on April 3, 2007. The inspection examined your decommissioning activities as they relate to safety andcompliance with the Commission's rules and regulations. The inspector reviewed selected procedures and records, interviewed personnel, and observed activities. The report also includes two survey reports (Enclosures 2 and 3) conducted by the Oak Ridge Institute for Science and Education (ORISE). With respect to these inspection areas, we noted that you maintained effective programs for decommissioning the site and for the safe storage of spent fuel. Based on the results of this inspection, no violations were identified.
documents the inspection results which were discussed with Mr. G. van Noordennen and other members of your staff on April 3, 2007.
 
The inspection examined your decommissioning activities as they relate to safety and compliance with the Commissions rules and regulations. The inspector reviewed selected procedures and records, interviewed personnel, and observed activities. The report also includes two survey reports (Enclosures 2 and 3) conducted by the Oak Ridge Institute for Science and Education (ORISE). With respect to these inspection areas, we noted that you maintained effective programs for decommissioning the site and for the safe storage of spent fuel.
 
Based on the results of this inspection, no violations were identified.


In accordance with Section 2.390 of the NRC's "Rules and Practices," Part 2, Title 10, Code ofFederal Regulations, a copy of this letter and its enclosure will be placed in the NRC Public Document Room (PDR) and will be accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. No reply to this letter is required. Your cooperationwith us is appreciated.
In accordance with Section 2.390 of the NRCs Rules and Practices, Part 2, Title 10, Code of Federal Regulations, a copy of this letter and its enclosure will be placed in the NRC Public Document Room (PDR) and will be accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. No reply to this letter is required. Your cooperation with us is appreciated.


Sincerely,
Sincerely,
/RA/Samuel Hansell, ChiefDecommissioning Branch Division of Nuclear Materials Safety W. Norton2Enclosure:1.NRC Region I Inspection Report No. 05000213/2006003 2.Confirmatory Survey Results for the East Mountain Side at the Connecticut YankeeHaddam Neck Plant, Haddam, Connecticut, dated July 18, 2006 [ADAMS Accession Number ML070320448]3.Confirmatory Survey Results for Survey Units 9304, 9527, and 9530 at the ConnecticutYankee Haddam Neck Plant, Haddam, Connecticut, dated September 25, 2006, which are enclosed [ADAMS Accession Number ML070320450]cc w/encls:T. Smith, Executive Director of Business Operations G. van Noordennen, Director, Nuclear Safety/Regulatory Affairs C. Pizzella, Treasurer J. Fay, General Council R. Capstick, Communications Manager R. Bassilakis, Citizens Awareness Network J. Brooks, CT Attorney T. Bondi, Town of Haddam E. Woollacott, NEAC H. Curley, Chair, SFAC State of Connecticut
/RA/
Samuel Hansell, Chief Decommissioning Branch Division of Nuclear Materials Safety Enclosure:
1. NRC Region I Inspection Report No. 05000213/2006003 2. Confirmatory Survey Results for the East Mountain Side at the Connecticut Yankee Haddam Neck Plant, Haddam, Connecticut, dated July 18, 2006 [ADAMS Accession Number ML070320448]
3. Confirmatory Survey Results for Survey Units 9304, 9527, and 9530 at the Connecticut Yankee Haddam Neck Plant, Haddam, Connecticut, dated September 25, 2006, which are enclosed [ADAMS Accession Number ML070320450]
cc w/encls:
T. Smith, Executive Director of Business Operations G. van Noordennen, Director, Nuclear Safety/Regulatory Affairs C. Pizzella, Treasurer J. Fay, General Council R. Capstick, Communications Manager R. Bassilakis, Citizens Awareness Network J. Brooks, CT Attorney T. Bondi, Town of Haddam E. Woollacott, NEAC H. Curley, Chair, SFAC State of Connecticut


=EXECUTIVE SUMMARY=
=EXECUTIVE SUMMARY=
Connecticut Yankee Atomic Power CompanyNRC Inspection Report No. 05000213/2006003This integrated inspection includes aspects of decommissioning activities regardingdismantlement and decommissioning of the facility, and storage of spent fuel. The report covers announced safety inspections conducted by one regional inspector. The report includes evaluations of your decommissioning activities related to organization, management oversight, the surveillance program, the corrective action program, the decommissioning performance and final status survey programs, the radiation protection program, and the solid radioactive waste treatment and transportation programs. The report also includes two Oak Ridge Institute for Science and Education (ORISE) Reports regarding two confirmatory inspections conducted inApril and August 2006.
Connecticut Yankee Atomic Power Company


Organization, Management Oversight, Surveillances, and Corrective ActionThe licensee's organization was adequate to support ongoing decommissioning activities. Management oversight was effective for the activities conducted. The licensee maintained an adequate surveillance and corrective action program to identify and resolve issues.Status of Decommissioning Performance and Inspection of Final Status SurveysThe licensee conducted decommissioning activities in accordance with the approved LicenseTermination Plan requirements, and adequately implemented sampling and survey procedures and protocols to support the final status survey program.Radiation Protection ProgramThe licensee maintained an effective radiation protection program, including the surveyinstrument calibration program and the contamination control program.Radioactive Waste Treatment and Transportation ProgramsThe licensee effectively implemented the solid radioactive waste management andtransportation programs.
NRC Inspection Report No. 05000213/2006003 This integrated inspection includes aspects of decommissioning activities regarding dismantlement and decommissioning of the facility, and storage of spent fuel. The report covers announced safety inspections conducted by one regional inspector. The report includes evaluations of your decommissioning activities related to organization, management oversight, the surveillance program, the corrective action program, the decommissioning performance and final status survey programs, the radiation protection program, and the solid radioactive waste treatment and transportation programs. The report also includes two Oak Ridge Institute for Science and Education (ORISE) Reports regarding two confirmatory inspections conducted in April and August 2006.


Enclosure
Organization, Management Oversight, Surveillances, and Corrective Action The licensees organization was adequate to support ongoing decommissioning activities.
 
Management oversight was effective for the activities conducted. The licensee maintained an adequate surveillance and corrective action program to identify and resolve issues.
 
Status of Decommissioning Performance and Inspection of Final Status Surveys The licensee conducted decommissioning activities in accordance with the approved License Termination Plan requirements, and adequately implemented sampling and survey procedures and protocols to support the final status survey program.
 
Radiation Protection Program The licensee maintained an effective radiation protection program, including the survey instrument calibration program and the contamination control program.
 
Radioactive Waste Treatment and Transportation Programs The licensee effectively implemented the solid radioactive waste management and transportation programs.
 
ii


=REPORT DETAILS=
=REPORT DETAILS=


===1. Organization, Management Oversight, Surveillances, and Corrective Action Programa.Inspection Scope Inspection Procedures (IPs) 36801 and 40801The inspector reviewed the decommissioning organization changes since September2006 to determine the effectiveness of the Connecticut Yankee (CY) management===
===1. Organization, Management Oversight, Surveillances, and Corrective Action Program===
 
====a. Inspection Scope====
Inspection Procedures (IPs) 36801 and 40801 The inspector reviewed the decommissioning organization changes since September 2006 to determine the effectiveness of the Connecticut Yankee (CY) management oversight of overall decommissioning and plant support activities. The inspector assessed the effectiveness of management oversight through discussions with CY managers and staff regarding organization changes and observations of managers and staff in the field and during staff meetings.
 
The inspector evaluated three Quality Surveillance Reports (QSRs) and five Condition Reports (CRs) from October through December 2006 to determine the licensees ability to identify, resolve, and prevent the recurrence of conditions that could degrade the safety or quality of decommissioning activities. The inspector reviewed the QSRs for the following activities: trans-loading concrete rubble at the Worcester, MA facility; Radiation Protection Release Program of equipment, material, and vehicles; and guidance for preparing Final Status Survey Release Records. The inspector reviewed CRs for issues related to the following: the final status survey program, the radiation protection program, and the radioactive waste and transportation of radioactive materials programs.
 
====b. Observations and Findings====
No findings of significance were identified.
 
The inspector noted a reduction of approximately 100 management and staff positions since the last inspection. The reductions were proportional to the decrease in decommissioning activities. The inspector also noted that managers continued to be directly involved in the implementation of decommissioning activities. The managers conducted site tours and verification checks in the field, making themselves accessible to the staff for oversight support. The surveillance activities performed by the licensee were sufficiently detailed and thorough to identify areas of declining performance. A review of selected CRs indicated that the licensee continued to maintain a program for reporting potential safety issues. The licensee generated CRs when deficiencies were noted. The CRs were entered into the Corrective Action Program to be dispositioned and corrected. The inspector determined that the CR issues did not impact safety and were corrected.
 
====c. Conclusions====
The licensees organization was adequate to support ongoing decommissioning activities. Management oversight was effective for the activities conducted. The licensee maintained an adequate surveillance and corrective action program to identify and resolve issues.
 
===2. Status of Decommissioning Performance and Inspection of Final Status Surveys===
 
====a. Inspection Scope====
IPs 71801 and 83801 The inspector evaluated the status of decommissioning activities and the final status survey (FSS) program to verify that the licensee was conducting decommissioning activities in accordance with the License Termination Plan (LTP). The inspector conducted site tours and discussed the decommissioning project status and the final status survey activity schedule. The inspector observed the licensee collect four soil samples from Survey Unit (SU) 9512-0000. The inspector reviewed the associated FSS Plan and Radiation Protection Manual (RPM) procedure, Collection of Sample Media for FSS, (RPM 5.1-3) to assess sampling technique and methodology and verify appropriate use and calibration of survey instrumentation. The inspector followed-up with the Spent Fuel Building basement fill dose model calculation discussion and the two confirmatory inspections conducted by ORISE in April and August 2006.
 
====b. Observations and Findings====
No findings of significance were identified.


oversight of overall decommissioning and plant support activities. The inspector assessed the effectiveness of management oversight through discussions with CY managers and staff regarding organization changes and observations of managers and staff in the field and during staff meetings.The inspector evaluated three Quality Surveillance Reports (QSRs) and five ConditionReports (CRs) from October through December 2006 to determine the licensee's ability to identify, resolve, and prevent the recurrence of conditions that could degrade the safety or quality of decommissioning activities. The inspector reviewed the QSRs for the following activities:  trans-loading concrete rubble at the Worcester, MA facility; Radiation Protection Release Program of equipment, material, and vehicles; and guidance for preparing Final Status Survey Release Records. The inspector reviewed CRs for issues related to the following:  the final status survey program, the radiation protection program, and the radioactive waste and transportation of radioactive materials programs.b.Observations and FindingsNo findings of significance were identified.
Decommissioning activities were conducted in accordance with the LTP. The inspector noted that the FSS Plan and RPM 5.1-3 procedure were adequate but contained limited guidance to ensure reproducible representative soil samples consistent with industry practices. The licensee initiated corrective actions to improve the FSS Plan and sample procedure. This issue will be reviewed during a subsequent inspection. The inspector determined through interviews and observations that the technicians were knowledgeable in the use of the survey instruments and the sampling procedures. The technicians were using appropriate and calibrated survey instruments.


The inspector noted a reduction of approximately 100 management and staff positionssince the last inspection. The reductions were proportional to the decrease in decommissioning activities. The inspector also noted that managers continued to be directly involved in the implementation of decommissioning activities. The managers conducted site tours and verification checks in the field, making themselves accessible to the staff for oversight support. The surveillance activities performed by the licensee were sufficiently detailed and thorough to identify areas of declining performance. A review of selected CRs indicated that the licensee continued to maintain a program for reporting potential safety issues. The licensee generated CRs when deficiencies were noted. The CRs were entered into the Corrective Action Program to be dispositioned and corrected. The inspector determined that the CR issues did not impact safety and were corrected.c.ConclusionsThe licensee's organization was adequate to support ongoing decommissioningactivities. Management oversight was effective for the activities conducted. The 2Enclosurelicensee maintained an adequate surveillance and corrective action program to identifyand resolve issues.2.
In Section 3.1 of the previous inspection report (NRC Inspection Report No.


Status of Decommissioning Performance and Inspection of Final Status Surveysa.Inspection Scope IPs 71801 and 83801The inspector evaluated the status of decommissioning activities and the final statussurvey (FSS) program to verify that the licensee was conducting decommissioning activities in accordance with the License Termination Plan (LTP). The inspector conducted site tours and discussed the decommissioning project status and the final status survey activity schedule. The inspector observed the licensee collect four soil samples from Survey Unit (SU) 9512-0000. The inspector reviewed the associated FSS Plan and Radiation Protection Manual (RPM) procedure, "Collection of Sample Media for FSS," (RPM 5.1-3) to assess sampling technique and methodology and verify appropriate use and calibration of survey instrumentation. The inspector followed-up with the Spent Fuel Building basement fill dose model calculation discussion and the two confirmatory inspections conducted by ORISE in April and August 2006.b.Observations and FindingsNo findings of significance were identified.
05000213/2006002, dated December 19, 2006; ADAMS Accession Number ML063560253), the inspector stated that the results of the NRCs review regarding the Spent Fuel Building (SFB) basement fill dose model calculations would be discussed with the licensee in December 2006. Notwithstanding, the discussion of the basement fill dose model calculations for the SFB will be conducted at a later date and concurrent with the NRCs review of the associated FSS Report.


Decommissioning activities were conducted in accordance with the LTP. The inspectornoted that the FSS Plan and RPM 5.1-3 procedure were adequate but contained limited guidance to ensure reproducible representative soil samples consistent with industry practices. The licensee initiated corrective actions to improve the FSS Plan and sample procedure. This issue will be reviewed during a subsequent inspection. The inspector determined through interviews and observations that the technicians were knowledgeable in the use of the survey instruments and the sampling procedures. The technicians were using appropriate and calibrated survey instruments.In Section 3.1 of the previous inspection report (NRC Inspection Report No. 05000213/2006002, dated December 19, 2006; ADAMS Accession Number ML063560253), the inspector stated that the results of the NRC's review regarding the Spent Fuel Building (SFB) basement fill dose model calculations would be discussed with the licensee in December 2006. Notwithstanding, the discussion of the basement fill dose model calculations for the SFB will be conducted at a later date and concurrent with the NRC's review of the associated FSS Report.On April 25-26, 2006, ORISE conducted surface gamma scans and collected soilsamples in SUs 9527-0001 through 9527-0004. On August 22-23, 2006, ORISE conducted surface gamma scans and collected soil samples in SUs 9304-0001 and 9304-0002, they conducted surface gamma scans in SUs 9530-0001 through 9530-0004, and conducted a second survey including surface gamma scans and soil samples in SUs 9527-0003 and 9527-0004 (originally discussed in NRC Inspection 3EnclosureReport No. 05000213/2006002, dated December 19, 2006; ADAMS Accession NumberML063560253).The details of the ORISE analysis are contained in the following ORISE Reports:"Confirmatory Survey Results for the East Mountain Side at the Connecticut Yankee Haddam Neck Plant, Haddam, Connecticut, dated July 18, 2006, and "Confirmatory Survey Results for Survey Units 9304, 9527, and 9530 at the Connecticut Yankee Haddam Neck Plant, Haddam, Connecticut, dated September 25, 2006, which are enclosed.  [ADAMS Accession Numbers ML070320448 and ML070320450, respectively.]c.ConclusionsThe licensee conducted decommissioning activities in accordance with the approvedLTP requirements and adequately implemented sampling and survey procedures and protocols to support the final status survey program.3.
On April 25-26, 2006, ORISE conducted surface gamma scans and collected soil samples in SUs 9527-0001 through 9527-0004. On August 22-23, 2006, ORISE conducted surface gamma scans and collected soil samples in SUs 9304-0001 and 9304-0002, they conducted surface gamma scans in SUs 9530-0001 through 9530-0004, and conducted a second survey including surface gamma scans and soil samples in SUs 9527-0003 and 9527-0004 (originally discussed in NRC Inspection Report No. 05000213/2006002, dated December 19, 2006; ADAMS Accession Number ML063560253).


Radiation Protection Programa.Inspection Scope IP 83750The inspector assessed the radiation control program to verify the adequacy of surveysnecessary to post and control high radiation and radiation areas and to verify the proper use of personal contamination monitors such as friskers, including consideration of hotparticle contamination. The inspector also reviewed the program to verify the adequacy of survey practices, including selected survey records, technical awareness of limitations of the survey instruments, and the calibration records of selected survey and monitoring instruments. The inspector conducted interviews with the cognizant personnel and reviewed the following procedures to evaluate the program:  "Radiological Posting and Labeling" (RPM 2.2-27); "Personnel Monitoring, Survey and Decontamination" (RPM 2.7-3); "Control and Accountability of Portable Survey Instruments for Final Status Surveys" (RPM 5.1-04); "Calibration of the Ludlum Model 3" (RPM 4.1-19); "Calibration of the Eberline E-140 with Frisker Probe" (RPM 4.2-3); "Small Article Monitor Calibration and Relocation" (RPM 4.4-6); "Calibration of the Bicron NE MicroRem" (RPM 4.8-5); and "Portable Health Physics Instrument Source/Response Check" (RPM 2.2-10).
The details of the ORISE analysis are contained in the following ORISE Reports:
Confirmatory Survey Results for the East Mountain Side at the Connecticut Yankee Haddam Neck Plant, Haddam, Connecticut, dated July 18, 2006, and Confirmatory Survey Results for Survey Units 9304, 9527, and 9530 at the Connecticut Yankee Haddam Neck Plant, Haddam, Connecticut, dated September 25, 2006, which are enclosed. [ADAMS Accession Numbers ML070320448 and ML070320450, respectively.]


Additionally, the inspector reviewed the licensee's contamination control program, including implementation of "Contamination Control Program" (RPM 2.7-0). The review was a follow-up from the previous inspection period regarding the licensee's implementation to ensure the control of equipment and materials were released properly from the Radiologically Controlled Area (RCA) for unrestricted use.b.Observations and FindingsNo findings of significance were identified.
====c. Conclusions====
The licensee conducted decommissioning activities in accordance with the approved LTP requirements and adequately implemented sampling and survey procedures and protocols to support the final status survey program.


Radiation Protection (RP) technician performance for conducting radiological surveys ofpersonnel, tools, equipment, and shipping boxes containing demolition debris exiting the 4EnclosureRCA was adequate. The licensee performed effective surveys in accordance with theContamination Control Program. The licensee completed survey records as required by the survey procedures. RP technicians were cognizant of the potential for contaminated tools and hot particles and the licensee clearly and accurately documented survey results as required. Technicians demonstrated the appropriate level of understanding of the use and limitations of the survey instrumentation, including friskers, to conduct effective surveys. Radiation areas were posted appropriately. No high radiation areas existed on site during this inspection period.Technicians used calibrated survey instrumentation. The calibration records of surveyinstruments were complete and accurate. The RP instrument technician is responsible for calibrating instruments and has an appropriate level of technical understanding for calibrating survey instrumentation. Calibration and source check results for the survey instrumentation were within the acceptance criteria as defined in the procedures. The licensee used check sources that were traceable to the National Institute of Standards and Technology.c.ConclusionsThe licensee maintained an effective radiation control program, including the surveyinstrument calibration program and the contamination control program.4.
===3. Radiation Protection Program===


Radioactive Waste Treatment and Transportation Programsa.Inspection Scope IP 86750The scope of this inspection area was to evaluate the Solid Radioactive WasteManagement and Transportation programs and to determine whether the licensee properly processed, packaged, stored, and shipped radioactive materials. The inspector reviewed selected Low Specific Activity radioactive waste shipments from September through December 2006, including dry active waste and low-level radioactive demolition debris. The inspector observed the licensee conducted surveys and prepared shipments for transport.b.Observations and FindingsNo findings of significance were identified.
====a. Inspection Scope====
IP 83750 The inspector assessed the radiation control program to verify the adequacy of surveys necessary to post and control high radiation and radiation areas and to verify the proper use of personal contamination monitors such as friskers, including consideration of hot particle contamination. The inspector also reviewed the program to verify the adequacy of survey practices, including selected survey records, technical awareness of limitations of the survey instruments, and the calibration records of selected survey and monitoring instruments. The inspector conducted interviews with the cognizant personnel and reviewed the following procedures to evaluate the program: Radiological Posting and Labeling (RPM 2.2-27); Personnel Monitoring, Survey and Decontamination (RPM 2.7-3); Control and Accountability of Portable Survey Instruments for Final Status Surveys (RPM 5.1-04); Calibration of the Ludlum Model 3" (RPM 4.1-19); Calibration of the Eberline E-140 with Frisker Probe (RPM 4.2-3); Small Article Monitor Calibration and Relocation (RPM 4.4-6); Calibration of the Bicron NE MicroRem (RPM 4.8-5); and Portable Health Physics Instrument Source/Response Check (RPM 2.2-10).


The selected radioactive waste shipment records included completed copies ofCharacterization Reports, Waste Manifest Shipping papers, Emergency Response Information, Survey Record Forms, and related documentation, including shipment inspection plans and truck inspection records. The licensee met the applicable radiation and transportation requirements for the shipments reviewed.
Additionally, the inspector reviewed the licensees contamination control program, including implementation of Contamination Control Program (RPM 2.7-0). The review was a follow-up from the previous inspection period regarding the licensees implementation to ensure the control of equipment and materials were released properly from the Radiologically Controlled Area (RCA) for unrestricted use.


5Enclosurec.ConclusionsThe licensee effectively implemented the solid radioactive waste management andtransportation programs.5.
====b. Observations and Findings====
No findings of significance were identified.


Exit MeetingThe inspector presented the inspection results to representatives of the licensee's staff at theconclusion of the onsite inspection on October 26, 2007, and in-office inspections on November 7, 2006 and December 5, 2006. On April 3, 2007, a summary of the inspection findings for the entire inspection period was presented to the licensee. Licensee representatives acknowledged the inspection findings. Although proprietary items were reviewed during the inspection, no proprietary information is presented in this report.
Radiation Protection (RP) technician performance for conducting radiological surveys of personnel, tools, equipment, and shipping boxes containing demolition debris exiting the RCA was adequate. The licensee performed effective surveys in accordance with the Contamination Control Program. The licensee completed survey records as required by the survey procedures. RP technicians were cognizant of the potential for contaminated tools and hot particles and the licensee clearly and accurately documented survey results as required. Technicians demonstrated the appropriate level of understanding of the use and limitations of the survey instrumentation, including friskers, to conduct effective surveys. Radiation areas were posted appropriately. No high radiation areas existed on site during this inspection period.


A-1
Technicians used calibrated survey instrumentation. The calibration records of survey instruments were complete and accurate. The RP instrument technician is responsible for calibrating instruments and has an appropriate level of technical understanding for calibrating survey instrumentation. Calibration and source check results for the survey instrumentation were within the acceptance criteria as defined in the procedures. The licensee used check sources that were traceable to the National Institute of Standards and Technology.
 
====c. Conclusions====
The licensee maintained an effective radiation control program, including the survey instrument calibration program and the contamination control program.
 
===4. Radioactive Waste Treatment and Transportation Programs===
 
====a. Inspection Scope====
IP 86750 The scope of this inspection area was to evaluate the Solid Radioactive Waste Management and Transportation programs and to determine whether the licensee properly processed, packaged, stored, and shipped radioactive materials. The inspector reviewed selected Low Specific Activity radioactive waste shipments from September through December 2006, including dry active waste and low-level radioactive demolition debris. The inspector observed the licensee conducted surveys and prepared shipments for transport.
 
====b. Observations and Findings====
No findings of significance were identified.
 
The selected radioactive waste shipment records included completed copies of Characterization Reports, Waste Manifest Shipping papers, Emergency Response Information, Survey Record Forms, and related documentation, including shipment inspection plans and truck inspection records. The licensee met the applicable radiation and transportation requirements for the shipments reviewed.
 
====c. Conclusions====
The licensee effectively implemented the solid radioactive waste management and transportation programs.
 
===5. Exit Meeting===
 
The inspector presented the inspection results to representatives of the licensees staff at the conclusion of the onsite inspection on October 26, 2007, and in-office inspections on November 7, 2006 and December 5, 2006. On April 3, 2007, a summary of the inspection findings for the entire inspection period was presented to the licensee. Licensee representatives acknowledged the inspection findings. Although proprietary items were reviewed during the inspection, no proprietary information is presented in this report.


=SUPPLEMENTAL INFORMATION=
=SUPPLEMENTAL INFORMATION=
PARTIAL LIST OF PERSONS CONTACTED
PARTIAL LIST OF PERSONS CONTACTED
Licensee*
Licensee
: [[contact::J. Arnold]], Executive Staff Assistant  
*
: [[contact::J. Arnold]], Executive Staff Assistant
: [[contact::B. Couture]], Project Support, Resource Conservation and Recovery Act Coordinator
: [[contact::B. Couture]], Project Support, Resource Conservation and Recovery Act Coordinator
: [[contact::J. Fan]], Project Support and Engineering Manager
: [[contact::J. Fan]], Project Support and Engineering Manager
Line 81: Line 150:
: [[contact::J. Wagner]], FSS Supervisor, FSS
: [[contact::J. Wagner]], FSS Supervisor, FSS
*
*
: [[contact::G. van Noordennen]], Manager, Nuclear Safety/Regulatory Affairs*These individuals participated in the exit briefing held on April 3, 2007.INSPECTION PROCEDURES USED36801Organization, Management, and Cost Controls40801Self-Assessment, Auditing, and Corrective Action
: [[contact::G. van Noordennen]], Manager, Nuclear Safety/Regulatory Affairs
60855Operation of Independent Spent Fuel Storage Installation
*These individuals participated in the exit briefing held on April 3, 2007.
2801Maintenance and Surveillance
INSPECTION PROCEDURES USED
71801Decommissioning Performance and Status Reviews
36801  Organization, Management, and Cost Controls
83750Occupational Radiation Exposure
40801  Self-Assessment, Auditing, and Corrective Action
83801Inspection of Final Status Surveys
60855  Operation of Independent Spent Fuel Storage Installation
86750Solid Radioactive Waste Management and Transportation of Radioactive Materials
2801  Maintenance and Surveillance
A-2ITEMS OPEN, CLOSED, AND DISCUSSEDItems Opened:
71801  Decommissioning Performance and Status Reviews
NoneItems Closed:
83750  Occupational Radiation Exposure
NoneItems Discussed:
83801  Inspection of Final Status Surveys
NoneLIST OF ACRONYMS USEDCRCondition ReportsCY Connecticut Yankee
86750  Solid Radioactive Waste Management and Transportation of Radioactive Materials
FSSFinal Status Survey
ITEMS OPEN, CLOSED, AND DISCUSSED
IPInspection Procedure
Items Opened:
LTPLicense Termination Plan
None
ORISEOak Ridge Institute for Science and Education
Items Closed:
QSRQuality Surveillance Reports
None
RCARadiologically Controlled Area
Items Discussed:
RPRadiation Protection
None
RPMRadiation Protection Manual
LIST OF ACRONYMS USED
SFBSpent Fuel Building
CR          Condition Reports
SUSurvey Unit
CY          Connecticut Yankee
FSS          Final Status Survey
IP          Inspection Procedure
LTP          License Termination Plan
ORISE        Oak Ridge Institute for Science and Education
QSR          Quality Surveillance Reports
RCA          Radiologically Controlled Area
RP          Radiation Protection
RPM          Radiation Protection Manual
SFB          Spent Fuel Building
SU          Survey Unit
}}
}}

Revision as of 07:30, 23 November 2019

IR 05000213-06-003, on 10/01/2006 - 03/30/2007, Connecticut Yankee Atomic Power Company, East Hampton, Connecticut Site
ML071010460
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 04/11/2007
From: Hansell S
Decommissioning Branch I
To: Norton W
Connecticut Yankee Atomic Power Co
References
IR-06-003
Download: ML071010460 (12)
v • d • e


Text

UNITED STATES ril 11, 2007

SUBJECT:

INSPECTION 05000213/2006003, CONNECTICUT YANKEE ATOMIC POWER COMPANY, EAST HAMPTON, CONNECTICUT SITE

Dear Mr. Norton:

On March 30, 2007, the United States Nuclear Regulatory Commission completed an announced inspection at your Haddam Neck facility. The enclosed report (Enclosure 1)

documents the inspection results which were discussed with Mr. G. van Noordennen and other members of your staff on April 3, 2007.

The inspection examined your decommissioning activities as they relate to safety and compliance with the Commissions rules and regulations. The inspector reviewed selected procedures and records, interviewed personnel, and observed activities. The report also includes two survey reports (Enclosures 2 and 3) conducted by the Oak Ridge Institute for Science and Education (ORISE). With respect to these inspection areas, we noted that you maintained effective programs for decommissioning the site and for the safe storage of spent fuel.

Based on the results of this inspection, no violations were identified.

In accordance with Section 2.390 of the NRCs Rules and Practices, Part 2, Title 10, Code of Federal Regulations, a copy of this letter and its enclosure will be placed in the NRC Public Document Room (PDR) and will be accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. No reply to this letter is required. Your cooperation with us is appreciated.

Sincerely,

/RA/

Samuel Hansell, Chief Decommissioning Branch Division of Nuclear Materials Safety Enclosure:

1. NRC Region I Inspection Report No. 05000213/2006003 2. Confirmatory Survey Results for the East Mountain Side at the Connecticut Yankee Haddam Neck Plant, Haddam, Connecticut, dated July 18, 2006 [ADAMS Accession Number ML070320448]

3. Confirmatory Survey Results for Survey Units 9304, 9527, and 9530 at the Connecticut Yankee Haddam Neck Plant, Haddam, Connecticut, dated September 25, 2006, which are enclosed [ADAMS Accession Number ML070320450]

cc w/encls:

T. Smith, Executive Director of Business Operations G. van Noordennen, Director, Nuclear Safety/Regulatory Affairs C. Pizzella, Treasurer J. Fay, General Council R. Capstick, Communications Manager R. Bassilakis, Citizens Awareness Network J. Brooks, CT Attorney T. Bondi, Town of Haddam E. Woollacott, NEAC H. Curley, Chair, SFAC State of Connecticut

EXECUTIVE SUMMARY

Connecticut Yankee Atomic Power Company

NRC Inspection Report No. 05000213/2006003 This integrated inspection includes aspects of decommissioning activities regarding dismantlement and decommissioning of the facility, and storage of spent fuel. The report covers announced safety inspections conducted by one regional inspector. The report includes evaluations of your decommissioning activities related to organization, management oversight, the surveillance program, the corrective action program, the decommissioning performance and final status survey programs, the radiation protection program, and the solid radioactive waste treatment and transportation programs. The report also includes two Oak Ridge Institute for Science and Education (ORISE) Reports regarding two confirmatory inspections conducted in April and August 2006.

Organization, Management Oversight, Surveillances, and Corrective Action The licensees organization was adequate to support ongoing decommissioning activities.

Management oversight was effective for the activities conducted. The licensee maintained an adequate surveillance and corrective action program to identify and resolve issues.

Status of Decommissioning Performance and Inspection of Final Status Surveys The licensee conducted decommissioning activities in accordance with the approved License Termination Plan requirements, and adequately implemented sampling and survey procedures and protocols to support the final status survey program.

Radiation Protection Program The licensee maintained an effective radiation protection program, including the survey instrument calibration program and the contamination control program.

Radioactive Waste Treatment and Transportation Programs The licensee effectively implemented the solid radioactive waste management and transportation programs.

ii

REPORT DETAILS

1. Organization, Management Oversight, Surveillances, and Corrective Action Program

a. Inspection Scope

Inspection Procedures (IPs) 36801 and 40801 The inspector reviewed the decommissioning organization changes since September 2006 to determine the effectiveness of the Connecticut Yankee (CY) management oversight of overall decommissioning and plant support activities. The inspector assessed the effectiveness of management oversight through discussions with CY managers and staff regarding organization changes and observations of managers and staff in the field and during staff meetings.

The inspector evaluated three Quality Surveillance Reports (QSRs) and five Condition Reports (CRs) from October through December 2006 to determine the licensees ability to identify, resolve, and prevent the recurrence of conditions that could degrade the safety or quality of decommissioning activities. The inspector reviewed the QSRs for the following activities: trans-loading concrete rubble at the Worcester, MA facility; Radiation Protection Release Program of equipment, material, and vehicles; and guidance for preparing Final Status Survey Release Records. The inspector reviewed CRs for issues related to the following: the final status survey program, the radiation protection program, and the radioactive waste and transportation of radioactive materials programs.

b. Observations and Findings

No findings of significance were identified.

The inspector noted a reduction of approximately 100 management and staff positions since the last inspection. The reductions were proportional to the decrease in decommissioning activities. The inspector also noted that managers continued to be directly involved in the implementation of decommissioning activities. The managers conducted site tours and verification checks in the field, making themselves accessible to the staff for oversight support. The surveillance activities performed by the licensee were sufficiently detailed and thorough to identify areas of declining performance. A review of selected CRs indicated that the licensee continued to maintain a program for reporting potential safety issues. The licensee generated CRs when deficiencies were noted. The CRs were entered into the Corrective Action Program to be dispositioned and corrected. The inspector determined that the CR issues did not impact safety and were corrected.

c. Conclusions

The licensees organization was adequate to support ongoing decommissioning activities. Management oversight was effective for the activities conducted. The licensee maintained an adequate surveillance and corrective action program to identify and resolve issues.

2. Status of Decommissioning Performance and Inspection of Final Status Surveys

a. Inspection Scope

IPs 71801 and 83801 The inspector evaluated the status of decommissioning activities and the final status survey (FSS) program to verify that the licensee was conducting decommissioning activities in accordance with the License Termination Plan (LTP). The inspector conducted site tours and discussed the decommissioning project status and the final status survey activity schedule. The inspector observed the licensee collect four soil samples from Survey Unit (SU) 9512-0000. The inspector reviewed the associated FSS Plan and Radiation Protection Manual (RPM) procedure, Collection of Sample Media for FSS, (RPM 5.1-3) to assess sampling technique and methodology and verify appropriate use and calibration of survey instrumentation. The inspector followed-up with the Spent Fuel Building basement fill dose model calculation discussion and the two confirmatory inspections conducted by ORISE in April and August 2006.

b. Observations and Findings

No findings of significance were identified.

Decommissioning activities were conducted in accordance with the LTP. The inspector noted that the FSS Plan and RPM 5.1-3 procedure were adequate but contained limited guidance to ensure reproducible representative soil samples consistent with industry practices. The licensee initiated corrective actions to improve the FSS Plan and sample procedure. This issue will be reviewed during a subsequent inspection. The inspector determined through interviews and observations that the technicians were knowledgeable in the use of the survey instruments and the sampling procedures. The technicians were using appropriate and calibrated survey instruments.

In Section 3.1 of the previous inspection report (NRC Inspection Report No.

05000213/2006002, dated December 19, 2006; ADAMS Accession Number ML063560253), the inspector stated that the results of the NRCs review regarding the Spent Fuel Building (SFB) basement fill dose model calculations would be discussed with the licensee in December 2006. Notwithstanding, the discussion of the basement fill dose model calculations for the SFB will be conducted at a later date and concurrent with the NRCs review of the associated FSS Report.

On April 25-26, 2006, ORISE conducted surface gamma scans and collected soil samples in SUs 9527-0001 through 9527-0004. On August 22-23, 2006, ORISE conducted surface gamma scans and collected soil samples in SUs 9304-0001 and 9304-0002, they conducted surface gamma scans in SUs 9530-0001 through 9530-0004, and conducted a second survey including surface gamma scans and soil samples in SUs 9527-0003 and 9527-0004 (originally discussed in NRC Inspection Report No. 05000213/2006002, dated December 19, 2006; ADAMS Accession Number ML063560253).

The details of the ORISE analysis are contained in the following ORISE Reports:

Confirmatory Survey Results for the East Mountain Side at the Connecticut Yankee Haddam Neck Plant, Haddam, Connecticut, dated July 18, 2006, and Confirmatory Survey Results for Survey Units 9304, 9527, and 9530 at the Connecticut Yankee Haddam Neck Plant, Haddam, Connecticut, dated September 25, 2006, which are enclosed. [ADAMS Accession Numbers ML070320448 and ML070320450, respectively.]

c. Conclusions

The licensee conducted decommissioning activities in accordance with the approved LTP requirements and adequately implemented sampling and survey procedures and protocols to support the final status survey program.

3. Radiation Protection Program

a. Inspection Scope

IP 83750 The inspector assessed the radiation control program to verify the adequacy of surveys necessary to post and control high radiation and radiation areas and to verify the proper use of personal contamination monitors such as friskers, including consideration of hot particle contamination. The inspector also reviewed the program to verify the adequacy of survey practices, including selected survey records, technical awareness of limitations of the survey instruments, and the calibration records of selected survey and monitoring instruments. The inspector conducted interviews with the cognizant personnel and reviewed the following procedures to evaluate the program: Radiological Posting and Labeling (RPM 2.2-27); Personnel Monitoring, Survey and Decontamination (RPM 2.7-3); Control and Accountability of Portable Survey Instruments for Final Status Surveys (RPM 5.1-04); Calibration of the Ludlum Model 3" (RPM 4.1-19); Calibration of the Eberline E-140 with Frisker Probe (RPM 4.2-3); Small Article Monitor Calibration and Relocation (RPM 4.4-6); Calibration of the Bicron NE MicroRem (RPM 4.8-5); and Portable Health Physics Instrument Source/Response Check (RPM 2.2-10).

Additionally, the inspector reviewed the licensees contamination control program, including implementation of Contamination Control Program (RPM 2.7-0). The review was a follow-up from the previous inspection period regarding the licensees implementation to ensure the control of equipment and materials were released properly from the Radiologically Controlled Area (RCA) for unrestricted use.

b. Observations and Findings

No findings of significance were identified.

Radiation Protection (RP) technician performance for conducting radiological surveys of personnel, tools, equipment, and shipping boxes containing demolition debris exiting the RCA was adequate. The licensee performed effective surveys in accordance with the Contamination Control Program. The licensee completed survey records as required by the survey procedures. RP technicians were cognizant of the potential for contaminated tools and hot particles and the licensee clearly and accurately documented survey results as required. Technicians demonstrated the appropriate level of understanding of the use and limitations of the survey instrumentation, including friskers, to conduct effective surveys. Radiation areas were posted appropriately. No high radiation areas existed on site during this inspection period.

Technicians used calibrated survey instrumentation. The calibration records of survey instruments were complete and accurate. The RP instrument technician is responsible for calibrating instruments and has an appropriate level of technical understanding for calibrating survey instrumentation. Calibration and source check results for the survey instrumentation were within the acceptance criteria as defined in the procedures. The licensee used check sources that were traceable to the National Institute of Standards and Technology.

c. Conclusions

The licensee maintained an effective radiation control program, including the survey instrument calibration program and the contamination control program.

4. Radioactive Waste Treatment and Transportation Programs

a. Inspection Scope

IP 86750 The scope of this inspection area was to evaluate the Solid Radioactive Waste Management and Transportation programs and to determine whether the licensee properly processed, packaged, stored, and shipped radioactive materials. The inspector reviewed selected Low Specific Activity radioactive waste shipments from September through December 2006, including dry active waste and low-level radioactive demolition debris. The inspector observed the licensee conducted surveys and prepared shipments for transport.

b. Observations and Findings

No findings of significance were identified.

The selected radioactive waste shipment records included completed copies of Characterization Reports, Waste Manifest Shipping papers, Emergency Response Information, Survey Record Forms, and related documentation, including shipment inspection plans and truck inspection records. The licensee met the applicable radiation and transportation requirements for the shipments reviewed.

c. Conclusions

The licensee effectively implemented the solid radioactive waste management and transportation programs.

5. Exit Meeting

The inspector presented the inspection results to representatives of the licensees staff at the conclusion of the onsite inspection on October 26, 2007, and in-office inspections on November 7, 2006 and December 5, 2006. On April 3, 2007, a summary of the inspection findings for the entire inspection period was presented to the licensee. Licensee representatives acknowledged the inspection findings. Although proprietary items were reviewed during the inspection, no proprietary information is presented in this report.

SUPPLEMENTAL INFORMATION

PARTIAL LIST OF PERSONS CONTACTED

Licensee

J. Arnold, Executive Staff Assistant
B. Couture, Project Support, Resource Conservation and Recovery Act Coordinator
J. Fan, Project Support and Engineering Manager
R. Haight, Waste Management Coordinator, Waste Management, Decommissioning
J. McCarthy, Engineer, FSS
R. McGrath, Radiation Protection/FSS Manager
R. Mitchell, ISFSI/Unit Manager
W. Norton, President and Chief Executive Officer
C. Newson, Technical Support Supervisor/FSS
C. Young, Waste Management Engineer, Waste Management, Decommissioning
J. Wagner, FSS Supervisor, FSS
G. van Noordennen, Manager, Nuclear Safety/Regulatory Affairs
  • These individuals participated in the exit briefing held on April 3, 2007.

INSPECTION PROCEDURES USED

36801 Organization, Management, and Cost Controls

40801 Self-Assessment, Auditing, and Corrective Action

60855 Operation of Independent Spent Fuel Storage Installation

2801 Maintenance and Surveillance

71801 Decommissioning Performance and Status Reviews

83750 Occupational Radiation Exposure

83801 Inspection of Final Status Surveys

86750 Solid Radioactive Waste Management and Transportation of Radioactive Materials

ITEMS OPEN, CLOSED, AND DISCUSSED

Items Opened:

None

Items Closed:

None

Items Discussed:

None

LIST OF ACRONYMS USED

CR Condition Reports

CY Connecticut Yankee

FSS Final Status Survey

IP Inspection Procedure

LTP License Termination Plan

ORISE Oak Ridge Institute for Science and Education

QSR Quality Surveillance Reports

RCA Radiologically Controlled Area

RP Radiation Protection

RPM Radiation Protection Manual

SFB Spent Fuel Building

SU Survey Unit

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