IR 05000213/2005003
ML060390475 | |
Person / Time | |
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Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
Issue date: | 02/07/2006 |
From: | Mark Miller Decommissioning Branch I |
To: | Norton W A Connecticut Yankee Atomic Power Co |
References | |
IR-05-003 | |
Download: ML060390475 (14) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I475 ALLENDALE ROADKING OF PRUSSIA, PENNSYLVANIA 19406-1415 February 7, 2006Docket No.05000213License No.DPR-61 Mr. Wayne A. NortonPresident Connecticut Yankee Atomic Power Company 362 Injun Hollow Road East Hampton, CT 06424-3099
SUBJECT: INSPECTION 05000213/2005003, CONNECTICUT YANKEE ATOMIC POWERCOMPANY, EAST HAMPTON, CONNECTICUT
Dear Mr. Norton:
On January 26, 2006, the NRC completed an integrated inspection at the Haddam Neck Plant,which began on October 1, 2005. The inspection findings were discussed with you and members of your staff upon the conclusion of our onsite inspections on September 22, 2005 and November 10, 2005, and with Mr. Bourassa and your staff during a telephone conversation on February 2, 2006. The enclosed report presents the results of this inspection.During this inspection period, we inspected your decommissioning operations related toorganization changes, self-assessments, decommissioning status, and radioactive effluent controls. We evaluated your decommissioning and remediation activities related to the former Primary Auxiliary Building (PAB) site and to an excavation site adjacent to the Spent FuelBuilding (SFB). Regarding the former PAB site and the excavation site adjacent to the SFB, NRC-selected samples of soil, bedrock, and concrete were analyzed by the NRCs' contractradioanalytical laboratory, Oak Ridge Institute for Science and Education (ORISE)
Environmental Survey and Site Assessment Program (ESSAP). The inspection consisted of selective examinations of procedures and representative records, interviews with personnel, observations by the inspectors, and independent direct radiation measurements made by the inspectors.Within the scope of this inspection, no violations were identified. We determined that youmaintained an effective program for decommissioning the site. The enclosed ORISE reports present the results of the above mentioned samples from the PAB site and the excavation site adjacent to the SFB.
W. Norton2In 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 enclosures will be placed in the NRC PublicDocument Room (PDR) and will be accessible from the NRC Web site athttp://www.nrc.gov/reading-rm/adams.html. No reply to this letter is required. Your cooperation with us is appreciated.
Sincerely,/RA/Marie Miller, Chief Decommissioning Branch Division of Nuclear Materials Safety
Enclosures:
1.NRC Inspection Report No. 05000213/20050032.Report for Analysis of Soil and Miscellaneous Samples from the Connecticut YankeeHaddam Neck Plant, Haddam, Connecticut (Docket No. 50-213, RFTA No.03-008)
[ADAMS Accession Number ML060320124]3.Revised Report for Analysis of Samples from the Connecticut Yankee Haddam NeckPlant, Haddam, Connecticut [Inspection Report No. DPR-61/2005003] [RFTA NO. 06-
001] [ADAMS Accession Number ML060310028]
cc:M. Thomas, Vice President and Chief Financial Officer K Heider, Vice President B Kenyon, Chief Executive Officer J Bourassa, Director, Nuclear Safety/Regulatory Affairs M Marston, Director, Project Support K Smith, Communications Manager G vanNoordennen, Manager, Regulatory Affairs G. Garfield, General Counsel R. Bassilakis, Citizens Awareness Network J. Brooks, CT Attorney General Office T. Bondi, Town of Haddam E. Woollacott, NEAC H. Curley, CDAC State of Connecticut W. Norton3Distribution
- S. Collins, RA M. Dapas. DRA C. Miller, OEDO M. Johnson, OE T. Madden, OCA D. Gillen, NMSS C. Craig, NMSS T. Smith, NMSS B. Watson, NMSS D. Schmidt, NMSS D. Screnci, PAO N. Sheehan, PAO D. Holody, ORA J. Wray, ORA M. Miller, DNMSDOCUMENT NAME: E:\Filenet\ML060390475.wpdSISP Review Complete: LKauffmanAfter declaring this document "An Official Agency Record" it will be released to the Public.To receive a copy of this document, indicate in the box:
"C" = Copy w/o attach/encl "
E" = Copy w/ attach/encl "
N" = No copyOFFICEDNMS/RI NDNMS/RIDNMS/RIDNMS/RINAMELKauffmanJKottanMMillerGpangburn FMCDATE2/7/062/7/062/7/062/7/06OFFICIAL RECORD COPY EnclosureU.S. NUCLEAR REGULATORY COMMISSIONREGION IINSPECTION REPORTInspection No.05000213/2005003Docket No.05000213 License No.DPR-61 Licensee:Connecticut Yankee Atomic Power Company Location:362 Injun Hollow Road East Hampton, CT 06424-3099Inspection Dates:October 1, 2005 - January 26, 2006 Inspectors:Laurie A. Kauffman, Health PhysicistDecommissioning Branch (DB)
Division of Nuclear Materials Safety (DNMS), Region I (RI)James Kottan, Senior Health PhysicistDB, DNMS, RIApproved By:Marie Miller, ChiefDB, DNMS, RI iiEXECUTIVE SUMMARYConnecticut Yankee Atomic Power Company (CYAPCO)NRC Inspection Report No. 05000213/2005003This integrated inspection report includes aspects of decommissioning activities regardingdismantlement and decommissioning of the facility. The report covers a four-month period ofannounced safety inspections conducted by two regional inspectors and contractor assistance provided by the Oak Ridge Institute for Science and Education (ORISE) Environmental Survey and Site Assessment Program (ESSAP). The report covers reviews and assessments of decommissioning operations related to organization changes, self-assessments, decommissioning status, and radioactive effluent controls. The report also covers an evaluation of decommissioning and remediation activities related to the former Primary Auxiliary Building(PAB) site and to an excavation site adjacent to the Spent Fuel Building (SFB).Decommissioning Operations The licensee's organization was adequate to support ongoing decontamination anddecommissioning activities. Management oversight was adequate for the activities conducted.The licensee maintained an adequate audit, self-assessment, and corrective action program(CAP) to identify, resolve, and prevent recurrence of conditions and issues that degrade safety and the quality of decommissioning activities.The licensee conducted decommissioning activities in accordance with the approved LicenseTermination Plan (LTP) requirements. Regarding the former PAB site, surveys and sample analysis did not identify any radiological contamination in excess of NRC-approved releasecriteria. The soil samples, bedrock, and concrete core samples analyzed for hard-to-detect radionuclides, such as tritium and Sr-90, were below the Derived Concentration Guideline Limits (DCGL) listed in the licensee's approved LTP. The analytical results of samples from the excavated area adjacent to the SFB indicated that the licensee's characterization of theradioactive contamination in the samples related to the SFB excavation was in agreement with the NRC's characterization. Based on the results, there was no significant contribution to onsite and offsite doses.Plant Support The licensee effectively controlled effluent releases from the SFB, in accordance with theRadiological Environmental Monitoring Offsite Dose Calculation Manual (REMODCM) and Quality Assurance Program (QAP) requirements.
EnclosureREPORT DETAILS1.0Decommissioning Operations1.1Organization, Management, and Cost Controlsa.Inspection Scope (Inspection Procedure (IP) 36801)The scope of this inspection area was to evaluate recent decommissioning organizationchanges to determine the effectiveness of the Connecticut Yankee (CY) management oversight on waste management and overall decommissioning activities. The inspector assessed the effectiveness of management oversight through observations in the field, attendance at staffing meetings, and interviews with management and staff.b.Observations and FindingsNo significant findings were identified.
Effective September 19, 2005, the Director of Decommissioning was temporarilyassigned to Yankee Rowe. The position remains vacant, but the responsibilities wereassumed by the President, CYAPCO. Managers continued to conduct site tours and verification checks in the field, and managers and supervisors were directly involvedwith the implementation of jobs, to ensure safe worker practices were being utilized by workers conducting demolition and excavation activities.c.ConclusionsThe licensee's organization was adequate to support ongoing decontamination anddecommissioning activities. Management oversight was adequate for the activities conducted.1.3Self-Assessment Auditing and Corrective Action Program a.Inspection Scope (IP 40801)The scope of this inspection area included an evaluation of the QAP and CAP and thelicensee's ability to identify, resolve, and prevent recurrence of conditions and issuesthat degrade safety and the quality of decommissioning activities.b.Observations and FindingsNo significant findings were identified.
The audit and surveillance reports performed by the licensee were thorough andsufficiently detailed to identify areas of declining performance or programmatic weaknesses in decommissioning program areas. A review of selected condition reports Enclosure 2(CR) indicted that the licensee had in place a program for reporting safety issues,appropriately classifying the issues, and providing appropriate management review to resolve this issues.c.ConclusionsThe licensee maintained an adequate audit, self-assessment, and CAP to identify,resolve, and prevent recurrence of conditions and issues that degrade safety and the quality of decommissioning activities.1.4Decommissioning Performance and Status Review a.Inspection Scope (IP 71801)The scope of this inspection area included site tours and discussions with the licenseeto evaluate the status of decommissioning activities and to verify whether the licensee was conducting decommissioning activities in accordance with the LTP. Specifically, the inspector observed decommissioning and remediation activities relatedto the former PAB site and to an excavation site adjacent to the SFB. The inspectors reviewed the analysis results, conducted independent surveys, conducted a visual inspection of the exterior SFB concrete wall below grade, and selected samples to be independently analyzed by the NRC's contractor, ORISE.b.Observations and FindingsNo significant findings were identified.
The licensee demolished most of the buildings and facilities, and excavated the formerPAB down to bedrock and conducted characterization surveys and remediated contaminated areas. As of April 2005, the licensee had completed Radiological Assessments (RA) and backfilled most of the excavated areas. Between May andOctober 2005, the licensee completed RA's in the PAB-Center, which included the residual heat removal (RHR) pit, and had determined that portions of the remainingPAB-East required blasting and additional remediation activities. In August 2005, the inspector had selected bedrock from the PAB-Northeast excavation area, concrete cores from the cable vault and containment areas, and soil from the PAB-Center excavation for independent analysis by ORISE. The NMSS staff and the Regional inspectors discussed these results with the licensee prior to backfilling the areas. Specific details of the ORISE analysis are contained in the ORISE Report, "Report forAnalysis of Soil and Miscellaneous Samples from the Connecticut Yankee Haddam Neck Plant, Haddam, Connecticut (Docket No. 50-213, RFTA No.03-008)", which is enclosed. [ADAMS Accession Number ML060320124]During characterization of onsite areas using a geo-probe (a device used to collect deepcore samples in the ground), the licensee had identified an area adjacent to the SFB Enclosure 3with slightly elevated levels of radioactivity compared to other areas of the site. As partof the decommissioning process, the licensee excavated the suspect area, and sampled and analyzed the soil, bedrock, and the below grade concrete wall of the SFB. The licensee suspected that the source of the radioactivity could have been either a possibleleak from the spent fuel pool or a spill, which may have occurred during plantoperations. While excavating the area, the licensee had noted a white substance onthe exterior of the SFB wall below grade. The licensee conservatively assumed the substance was boron (an indication of a possible leak from the spent fuel pool) and prior to analyzing the substance, notified the State of Connecticut, as required, that a leakmay have occurred during plant operations. The licensee also notified the Regional inspectors.The licensee had collected and analyzed all of the white substance from the SFB walland determined that the substance was not boron. The licensee was unable todetermine the exact chemical composition of the material but, was able to determine that the substance was a mineral or a salt-like crystalline material that is naturallyextracted from bedrock via ground water flows. Over time, the mineral was likely deposited onto the exterior concrete wall due to ground water flow toward the wall.On November 7, 2005, the inspectors conducted a visual inspection of the exterior SFBconcrete wall. No evidence of significant segmentation of the concrete wall was identified. No evidence of an active leak was identified. No evidence of a previous or a recent leak through the concrete was identified. No evidence of additional mineral or salt-like material was identified.The inspectors surveyed the excavated area and the exterior SFB wall. Contact doserate surveys of the SFB wall were made with attention to the core holes and any visible cracks. The contact dose rates were in the range of 20-30 microR/hr, with oneexception. The dose rate for one concrete hole (related to core sample number 9801-0000-009-1C-RAEXV-01) was 75 microR/hr. The dose rates obtained by the inspectors were in good agreement with the licensee's dose rates.The inspectors split two soil samples (9801-0000-028-RAE-XV and9801-0000-029-RAE-XV), two concrete core samples (9801-0000-009-1C-RAEXV and 9801-0000-018-1C-RAEXV), and three crushed bedrock samples (9801-0000-025-RA-EXV, 9801-0000-026-RA-EXV, and 9801-0000-027-RA-EXV) with the licensee. The samples were independently analyzed by the NRC's contractor,ORISE.The results of the split samples indicated that the soil samples contained very low levelsof detectable cesium-137 (Cs-137) and no detectable strontium-90 (Sr-90) or tritium (H-3); the bedrock samples contained very low levels of either Cs-137 or Sr-90 and no H-3; and the concrete samples all contained low levels H-3, Sr-90, and Cs-137. A comparison of the licensee's results to the NRC's results are presented in the table and figure below. A plot of the ratios indicated that the licensee's characterization of the radioactive contamination in the samples related to the SFB excavation was generally in agreement with the NRC's characterization. For these split samples, a ratio of between Enclosure 40.1 and 10 is considered acceptable for intercomparison for the purpose ofcharacterization of the material sampled. This criteria is judgmental in nature based on the fact that the samples which were split: soil, bedrock, and concrete were not homogeneous samples, and, in addition, were not used to demonstrate compliance with
NRC regulatory requirements. Both the NRC and the licensee arrived at the sameconclusion regarding characterization of the sampled material from their independent sample analyses. Specific details of the ORISE analysis are contained in the ORISE Report, "RevisedReport for Analysis of Samples from the Connecticut Yankee Haddam Neck Plant, Haddam, Connecticut [Inspection Report No. DPR-61/2005003] [RFTA NO. 06-001]",
which is enclosed. [ADAMS Accession Number ML060310028]Table 1Connecticut Yankee/NRC Analytical Comparison Results from the SFB Excavation SiteSampleIdentificationIsotopeNRC Value a(pCi/g)Licensee Value a(pCi/g)Ratio(Licensee/NRC)Soil9801-0000-028-RAE-XVCs-1370.16 +/- 0.048.99 +/- 1.896Sr-900.02 +/- 0.12Not Reported--H-30.3 +/- 1.8Not Reported--Soil 9801-0000-029-RAE-XVCs-1370.44 +/- 0.040.41 +/- 0.110.93Sr-90-0.04 +/- 0.12Not Reported--H-30.26 +/- 0.85Not Reported--Bedrock 9801-0000-025-RA-EXVCs-1370.33 +/- 0.030.128 +/- 0.0280.39Sr-90-0.01 +/- 0.110.0078 +/- 0.0079--H-32.2 +/- 1.8-0.272 +/- 0.896--Bedrock 9801-0000-026-RA-EXVCs-1370.02 +/- 0.020.038 +/- 0.030--Sr-900.23 +/- 0.120.0274 +/- 0.01070.12H-30.2 +/- 1.70.26 +/- 1.07--Bedrock 9801-0000-027-RA-EXVSr-90-0.06 +/- 0.090.0051 +/- 0.0122--H-32.9 +/- 1.8-0.56 +/- 0.81--
Enclosure 5SampleIdentificationIsotopeNRC Value a(pCi/g)Licensee Value a(pCi/g)Ratio(Licensee/NRC)Concrete9801-0000-009-1C-RAEXV-01Cs-137186.0 +/- 6.8100 +/- 70.54Sr-901.22 +/- 0.180.754 +/- 0.0260.62H-3128 +/- 13161 +/- 71.25Concrete 9801-0000-009-1C-RAEXV-02Cs-1370.24 +/- 0.070.227+/- 0.0390.94Sr-900.06 +/- 0.120.00334 +/- 0.00619--H-3223 +/- 22164 +/- 50.74Concrete 9801-0000-009-1C-RAEXV-03Cs-1370.50 +/- 0.070.138 +/- 0.0290.28Sr-900.04 +/- 0.120.000795 +/- 0.00288--H-3174 +/- 17128 +/- 50.74Concrete 9801-0000-009-1C-RAEXV-05Cs-1370.05 +/- 0.040.031 +/- 0.026--Sr-900.06 +/- 0.12-5.33E-5 +/- 0.0055--H-335.4 +/- 4.231.5 +/- 2.50.89Concrete 9801-0000-018-1C-RAEXV-01Cs-137325 +/- 12228 +/- 200.70Sr-905.07 +/- 0.361.88 +/- 0.060.37H-344.1 +/- 5.0105 +/- 32.38Concrete 9801-0000-018-1C-RAEXV-02Cs-13751.6 +/- 2.039.0 +/- 0.30.76Sr-901.11 +/- 0.180.388 +/- 0.0150.35H-3163 +/- 16242 +/- 61.48Concrete 9801-0000-018-1C-RAEXV-03Cs-13710.91 +/- 0.436.13 +/- 0.130.56Sr-900.33 +/- 0.130.098 +/- 0.0080.30H-3371 +/- 36339 +/- 90.91Concrete 9801-0000-018-1C-RAEXV-04Cs-1371.78 +/- 0.1211.0 +/- 0.86Sr-900.19 +/- 0.111.25 +/- 0.066H-3401 +/- 39382 +/- 100.95 a Uncertainties represent the 95% confidence level, based on total propagated uncertainties
.
Enclosure 6Sample Identification Num bSoil #28Soil #29Bdrk #25Bdrk #26Bdrk #27CC #9-01CC #9-02CC #9-03CC #9-05CC #18-01CC #18-02CC #18-03CC #10.1 1 10Cs-137Sr-90H-3Analytical ComparisonConnecticut Yankee Spent Fu eCs-137 60.930.390.540.940.28 0.70.760.56 6Sr-900.120.620.370.35 0.3 6H-31.250.740.740.892.381.480.91 0.9Figure 1c.ConclusionsThe licensee conducted decommissioning activities in accordance with the approvedLTP requirements. Regarding the former PAB site, surveys and sample analysis did not identify any radiological contamination in excess of NRC-approved release criteria. Thesoil samples, bedrock, and concrete core samples analyzed for hard-to-detect radionuclides, such as H-3 and Sr-90, were below the DCGL listed in the licensee's approved LTP. The analytical results of samples from the excavated area adjacent to the SFB indicated that the licensee's characterization of the radioactive contamination inthe samples related to the SFB excavation was generally in agreement with the NRC'scharacterization. Based on the results, there was no significant contribution to onsite and offsite doses.
Enclosure 72.0Plant Support2.1Radioactive Effluent Control Programa.Inspection Scope (IP 84750)The scope of this inspection area included an evaluation of the liquid effluent releasepermits, gamma analysis results, and chemistry controls for the liquid effluent releases from the SFB. The effluent releases were inspected against the REMODCM and QAP.b.Observations and FindingsNo significant findings were identified.
The licensee had drained a portion of the SPF pool water to verify a closed system (e.g.,no leaks) and to verify proper system configuration. The licensee drained approximately15,000 gallons of pool water to the Effluent Release tanks. The licensee processed and released the tank contents according to their effluent procedures. The licensee's effluent release permits and gamma analysis results indicated that the releases were below the effluent lower limits of detection. In addition, the inspector noted that thelicensee's water filtering system was effective in lowering the levels of turbidity andradioactivity from the pool water, prior to release.c.ConclusionsThe licensee effectively controlled effluent releases from the SFB, in accordance withthe REMODCM and QAP requirements.3.0 Exit MeetingThe inspectors presented the inspection results to representatives of the licensee's staffat the conclusion of onsite inspections on September 22 and November 10, 2005. On February 2, 2006, a summary of the inspection findings for the entire inspection period was presented to the licensee. Licensee representatives acknowledged the inspectionfindings. Although proprietary items were reviewed during the inspection, no proprietary information is presented in this report.
AttachmentA-1PARTIAL LIST OF PERSONS CONTACTEDLicensee* J. Arnold, Staff Assistant, Regulatory Affairs A. Barry, Nuclear Safety Engineer, Quality Assurance, Nuclear Safety and Regulatory Affairs S. Berger, Technical Support, Duratek
- J. Bourassa, Director, Nuclear Safety and Regulatory Affairs
- P. Clark, Regulatory Affairs Engineer, Regulatory Affairs E. Darois, Site Closure, Technical Support J. Fan, Manager, Project Support, Project Support and Engineering H. Farr, Manager, Radiation Protection, Nuclear Safety and Regulatory Affairs R. Haight, Waste Management Coordinator, Waste Management, Decommissioning
- R. Joshi, Regulatory Affairs Engineer, Regulatory Affairs J. Marchi, Manager, Quality Assurance, Nuclear Safety and Regulatory Affairs M. Marston, Director, Project Support and Engineering J. McCarthy, Engineer, Site Closure, Project Support and Engineering
- R. McGrath, Site Closure, Technical Support Manager R. Mitchell, Manager, Operations/Maintenance/ISFSI W. Norton, President, CYAPCO C. Newsome, Engineer, Site Closure, Project Support and Engineering R. Porter, Waste Management Supervisor, Waste Management, Decommissioning C. Young, Waste Management Engineer, Waste Management, Decommissioning
- J. Wagner, FSS Project Engineer, Site Closure, Project Support and Engineering
- G. vanNoordennen, Manager, Regulatory AffairsState of Connecticut* Firsick, Connecticut, DEP
- These individuals participated in the exit briefing held on February 2, 2006.INSPECTION PROCEDURES USED36801Organization, Management, and Cost Controls40801Self-Assessment Auditing and Corrective Action Program 71801Decommissioning Performance and Status Review 84750Radioactive Waste Treatment, Effluent and Environmental Monitoring AttachmentA-2ITEMS OPEN, CLOSED, AND DISCUSSEDItems Opened:NoneItems Closed:NoneItems Discussed:NoneLIST OF ACRONYMS USEDCAPCorrective Action ProgramCRCondition Reports Cs-137Cesium-137 CY Connecticut Yankee CYAPCOConnecticut Yankee Atomic Power Company DCGLDerived Concentration Guideline Levels ESSAPEnvironmental Survey and Site Assessment Program H-3Tritium IPInspection Procedure LTPLicense Termination Plan NMSSOffice of Nuclear Materials Safety and Safeguards ORISEOak Ridge Institute for Science and Education PABPrimary Auxiliary Building pCi/gPicoCuries per Gram QAPQuality Assurance Program QAQuality Assurance QSRQuality Assurance Surveillance Reports RARadiological Assessment RECPRadioactive Effluent Control Program REMODCMRadiological Environmental Monitoring Offsite Dose Calculation Manual RHR Residual Heat RemovalSFBSpent Fuel Building Sr-90Strontium-90 TS Technical Specifications