ML062720126

From kanterella
Jump to navigation Jump to search
Final - Confirmatory Survey Results for the Turbine and Containment Building Excavations, the Backfill Soil Pile, and Portions of Backfilled Survey Units and Class 3 Impacted Areas at Big Rock Point
ML062720126
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 09/25/2006
From: Adams W
Oak Ridge Institute for Science & Education
To: James Shepherd
NRC/NMSS/DWMEP
References
ORISE 06-1166
Download: ML062720126 (60)


Text

OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION Scptember 25, 3006 hlr. James Shepherd Ihvision of Decomrmssioiimg/Waste Management U S Nuclcar Regulatory Commission 1 lvo \\liite Fhnt North, Mad Stop: 7F27 11535 RocLdle Pike l<oclxille, ha> 20852-3738

SUBJECT:

FINAL-CONFIRMATORY SURVEY RESCLTS FOR T H E TURBINE AND CONTAINMENT BUILDING EXCAVATIONSyT H E BACKFILL SOIL PILE, AND PORTIONS OF BACKFILLED SURVEY UNITS AND CLASS 3 IMPACTED AREAS AT T H E BIG ROCK POINT RESTORATION PROJECT, CHARLEVOIX, MICHIGAN (DOCKET N O .

50-0155, RFTA NO.06-009)

Ilear ITr. Shepherd:

'l'lie O a k k d g e Institute for Science and Education (ORISE) performed conilrmatoi? sumey activities for the Turbine and Containment Builduig Excavations, the Backfill So11Pile, and portions o f backfilled survey units and Class 3 Impacted Areas a t the Big Rock Point Restoration Project in Charlevois, Michigan during the periods of September 20, 2005 and J u n e 13 through 16, 2006.

These survey activities were requested and approved by the U.S. Nuclear Regulacoy Comnissiori QXRC). The survey activities included gamma surface scans and soil sampling. Enclosed is the final confirmatoiy sun-ey report documenting these survey activities.

If you hare any questions or comments, please dlrect them to me a t 865.576.0065 or!. Scott IGrk a t 865.574.0685.

Sincerely,

\Yadc C. Adams I Icalth Physicist/Project Jxader Survey Projects

\'i%=\ :d b I-hclosurc C: T. McI,aughlin, NRC/NMSS/TWFN T-7E18 E. ;\belquist, ORISE B. \Vatson, NRC/h'hlSS/TCWN T-7E18 S. Kirk, ORISIT E. I<nos-Davin, IYRC/NMSS/TWFN 8A23 File/ 1710 W. Snell,NRC/Region 111 Phone: 865.576.0065 Fax: 865.241.3497 RECEIVED SEP 2 6 2006

' h e Oak Ridge Institute for Science and Education (ORISE) is a U.S. Department of Energy facility focusing on scientific initiatives to research health risks from occupational hazards, assess environmental cleanup, respond to radiation medical emergencies, support national security and emergency preparedness, and educate the next generation of scientists. ORISE is managed by Oak Ridge Associated Universities. Established in 1946, ORAU is a consortium of 91 colleges and universities.

NOTICES The opinions expressed herein do not necessarily reflect the opinions of the sponsoring institutions of Oak Ridge Associated Universities.

This report was prepared as an account of work sponsored by the United States Government. Neither the United States Government nor the U.S. Department of Energy, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe on privately owned rights.

Reference herein to any specific commercial product, process, or service by trade name, mark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement or recommendation, or favor by the U S . Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the US. Government or any agency thereof.

ORISE 06-1166 CONFIRMATORY SURVEY RESULTS FOR T H E TURBINE AND CONTAINMENT BUILDING EXCAVATIONS, T H E BACKFILL SOIL PILE, AND PORTIONS OF BACKFILLED SURVEY UNITS AND CLASS 3 IMPACTED AREAS AT T H E BIG ROCK POINT RESTORATION PROJECT CHARLEVOIX, MICHIGAN Prepared by W. C. Adams Independent Environmental Assessment and Verification Oak Ridge Institute for Science and Education Oak Ridge, Tennessee 37831-0117 Prepared for the Division of Decommissioning/Waste Management US.Nuclear Regulatory Commission FINAL REPORT SEPTEMBER 2006 This report is based on work performed under an Interagency Agreement (NRC Fin. No. J-5403) between the U.S. Nuclear Regulatory Commission and the U.S. Department of Energy. The Oak h d g e Institute for Science and Education performs complementary work under a contract with the E.S. Department of Energy.

Big Rock Point Restoration Project 1710/Reports/200GO9-07Final Confirmatory Survey Report

CONFIRMATORY SURVEY RESULTS FOR THE T U R B I N E AND CONTAINMENT BUILDING EXCAVATIONS, THE BACKFILL SOIL PILE, AND PORTIONS OF BACKFILLED SURVEY UNITS AND CLASS 3 IMPACTED AREAS AT THE BIG ROCK POINT RESTORATION PROJECT CHARLEVOIX, MICHIGAN Prepared by:

W. C. Adams, Project Leader Independent Environmental Assessment and Verification J. S. Kwk, Survey Projects Manager Independent Environmental Assessment and Verification Reviewed by: '

R. D. Condra, Laboratory Manager Independent Environmental Assessment and Vedcation Reviewed by:

. A. Payne, Quality Man&er Independent Environmental Assessment and Verification Reviewed by:

E. W. Abelquist, Pro Independent Enviro and Verification Big Rock Point Restoration Project 171O/Repom/2CIO6-09-O7 Final Confmatory S w e y Repon

ACKNOWLEDGMENTS The author would like to acknowledge the sipficant contributions of the following staff members:

FIELD STAFF T. L. Brown T. D. Herrera E. Montalvo A. J. Youghn LABORATORY STAFF R. D. Condra W. I?. h e y J. S. Cox W. F.Smith CLERICAL STAFF D. K.Boody K. L. Pond A. Ramsey E. S . Seaton ILLUSTRATOR T. D. Herrera 1710/Repom/2006-09-07 Final Confirmatory Sunrey Report Big Rock Point Restoration Project

TABLE OF CONTENTS PAGE L s t of Figures .................................................................................................................................................... ii List of Tables..................................................................................................................................................... u Abbreviations and Acronyms ......................................................................................................................... iv Introduction and Site %story .......................................................................................................................... 1 Site Description ................................................................................................................................................. 2 Objectives ........................................................................................................................................................... 3 Document Review ............................................................................................................................................. 3 Procedures .......................................................................................................................................................... 3 Sample Analysis and Data Interpretation ...................................................................................................... 6 Findings and Results ......................................................................................................................................... 6 Comparison of Results with Guidelines ...................................................................................................... 11 Summary ........................................................................................................................................................... 11 Figures ............................................................................................................................................................... 13 Tables ................................................................................................................................................................ 36 References......................................................................................................................................................... 43 Appendrces:

Appendm A: Major Instrumentation Appendix B: Survey and Analpcal Procedures Big Rock Pomt Restoration Project i 1710/Reports/2006-09-07 Final Confmatory Survey Report

LIST OF FIGURES PAGE FIGURE 1: Location of the Big Rock Point Restoration Project. Charlevoix. bfichgan .............. 14 FIGURE 2: Big Rock Point Restoration Project Owner Controlled Area ....................................... 15 FIGURE 3: Big Rock Point Restoration Project-- Plot Plan ............................................................... 16 FIGURE 4: Turbine Building Excavation-Surface Scans and Soil Samphg Locations ............... 17 FIGURE 5: Containment Buildmg Excavation-Surface Scans and Soil S a m p h g Locations ...... 18 FIGURE 6: Survey Unit 1-Surface Scans ............................................................................................. 19 FIGURE 7: Survey Unit 2-Surface Scans ............................................................................................. 20 FIGURE 8: Siwey Unit 3-Surface Scans and Soil Sampling Locations .......................................... 21 FIGURE 9: Survey Unit 4-Surface Scans and Soil S a m p h g Locations .......................................... 22 FIGURE 10: Survey Unit 5(1)-Surface Scans and Soil Sampling Locations ..................................... 23 FIGURE 11: Survey Unit 5(2)-Surface Scans a d Soil Samphg Locations ..................................... 24 FIGURE 12: Survey Unit 6-Surface Scans and Soil Samphg Locations .......................................... 25 FIGURE 13: Survey Unit 7-Surface Scans and Soil Sampling Locations .......................................... 26 FIGURE 14: Survey Unit 8-Surface Scans ............................................................................................. 27 FIGURE 15: Survey Unit +Surface Scans and Soil Sampling Locations .......................................... 28 FIGURE 16: Survey Unit 1O-Surface Scans and Soil S a m p h g Locations ........................................ 29 FIGURE 17: Survey Unit 12-Surface Scans and Soil Samphg Locations ........................................ 30 FIGURE 18: Survey Unit 14-Surface Scans and Soil Sampling Locations ........................................ 31 FIGURE 19: Survey Unit 15, Septic Drainfield [15(1)] and Waste Area [15(2)]-Surface Scans ....32 FIGURE 20: Survey Unit 16-Surface Scans and Soil Sampling Locations ........................................ 33 FIGURE 21: Survey Unit 59 Acres-Surface Scans and Soil Sampling Locations............................. 34 FIGURE 22: Access and Power Line Roads-Surface Scans and Soil Samphg Locations ............. 35 Big Rock Point Restoration Project u lflO/Repom/XX)6-09-07 Fmal C o n f m t o r y Survey Report

LIST OF TABLES PAGE TABLE 1: Analytical Comparison of CEC-Collected Soil Samples................................................ 37 TABLE 2: Tritium Concentrations in Confirmatory Soil Samples. Turbine Buildmg Excavation ............................................................................................................................ 37 TABLE 3: Radonuclide Concentrations in C o n b a t o r y Soil Samples ........................................ 38 TABLE 4: Summary of Soil DCGLs from Table 6-10 of the license Termination Plan ...........42 Btg Rock Point Restoration Project ... 1710/Reports/2006-09-07Final C o n f m a t o F S w e g Report Lu

ABBREVIATIONS AND ACRONYMS AEC Atomic Energy Commission BKG background BMO biological material oxidizer BRP Big Rock Point BRPRP Big Rock Point Restoration Project CB Containment Building CEC Consumers Energy Company CFR Code of Federal Regulations cm centimeter CPm counts per minute DCGL derived concentration guldehe level DOE Department of Energy FSS final status survey FSSP hnal status survey plan HSA hstorical site assessment ISFSI Independent Spent Fuel Storage Installation ISM integrated safety management ITP Intercomparison Testing Program kg kilogram LLRW low-level radioactive waste LTP license termination plan MAPEP Mured Analyte Performance Evaluation Program MARSSIM Multi-Agency Radiation Survey and Site Investigation Manual MDC minimum detectable concentration MeV d o n electron volts Mw megawatt NaI sodum iodide NIST National Institute of Standards and Technology NRC U S . Nuclear Regulatory Commission NRIP NIST Radiochemistry Intercomparison Program OM Open Land Area ORISE Oak Ridge Institute for Science and Education pwg picocuries per gram ROC radionuclides-of-concern su survey unit TAP total absorption peak TB Turbine Building TEDE total effective dose equivalent Big Rock Polnt Restoration Prolea iv 1710/Repom/2006-09-07 Final Confirmatory Survey Report

CONFIRMATORY SURVEY RESULTS FOR T H E TURBINE AND CONTAINMENT BUILDING EXCAVATIONSy T H E BACKFILL SOIL PILE, AND PORTIONS OF BACKFILLED SURVEY UNITS AND CLASS 3 IMPACTED AREAS AT THE BIG ROCK POINT RESTORATION PROJECT CHARLEVOIX, MICHIGAN INTRODUCTION AND SITE HISTORY The Big Rock Point (SW) Nuclear Plant was a 67-megawatt (MW) electric boiling water reactor located on the eastern shore of Lake Michgan. The site is owned by Consumers Energy Company (CEC). The operating license for BRP was granted by the Atomic Energy Commission (AEC) on August 30, 1962. Th.ts commercial nuclear electric generating station was the first in the state of hfichgan and the fifth in the United States. The hrst five years of plant operation were devoted to research and development as part of the AECs Power Reactor Demonstration Program. The plant was permanently shut down in August of 1997. It is currently being returned to its natural state @e.,

green field condttion). The final site release survey will be performed after the site has been returned to the green field condition. Guidance contained in the Multi-Agency Radtation Survey and Site Invesagation Manual (MARSSIhl) has been applied in preparation for the final status survey P S S (NRC 2000)l. CEC intends to demolish all of BRPs structures and release the demolition debris to a licensed landfill or other licensed radioactive disposal facllity prior to conducting the FSS (CEC 2004).

Currently, the BRP site is at an advanced stage of decommissioning. The demolition contractor occupies a portion of the site with temporary office space (trailers) which d be removed at the completion of the decommissioning activities. The remaining plant systems at the end of the decommissioning process will be those that support the Independent Spent Fuel Storage Installation (ISFSI), such as systems for potable water, sanitary sewers, electrical power, fire protection, and storm sewers. Plant operations, maintenance, and security personnel wdl continue to occupy portions of the site to support BFW ISFSI operations and maintenance.

The CEC has to dlspose of low-level radioactive waste (LLRW) generated during decommissioning activities at a site(s) permitted/licensed in accordance with federal, state and local regulations. CEC has not performed on-site burial, dlsposal or incineration of any LLRW.

Big Rock Point Restorahon Prqect 1710/Reports/2006-09-07 Final Confirmatory Survey Report

Residual radioactive materials that may remain on site after completion of decommissioning operations will meet the criteria for unrestricted use in accordance with Title 10, Code of Federal Regulations (CFR), Part 20.1402 and as described in the license termination plan (LTI?) for the Big Rock Point Restoration Project (BRPRP) (CEC 2004).

To support regulatory acdons/assessments needed to terminate BRPs operating license, the Nuclear Regulatory Commission (NRC) has requested that the Oak Ridge Institute for Science and Education (ORISE) perform conhtmatory surveys of the subject areas at the BRPRP.

SITE DESCRIPTION The BRPRP is located in Charlevoix County, LMchqpn, approximately four d e s northeast of Charlevoix, Mtchgan and approximately eleven miles west of Petoskey, Michlgan (Figure 1). The physical address is 10269 US 31 North, Charlevoix, Michigan, 49720. The site consists of approximately 560 acres exclusive of the US 31 nght-of-way.

As specified in the LTP, the site has been subdivided into Non-Impacted and Impacted areas to support the FSS (Figures 2 and 3). The Non-Impacted area consists of approximately 430 acres and is the portion of the site that is Owner-Controlled Area with no evidence or reasonable potential for the presence of radiological contamination resulting from plant operations. The remaining approximately 130 acres have been classified as Impacted Areas, for whch residual radoactivity attributable to plant operations may exist. As stated in the LTP, the Impacted Area extends over one mile along the Lake Michgan shorelme with the majority of the Impacted Area having little probabiltty of containing residual contamination fiom the plant based on its remoteness from plant operational activities. Locations with the potenaal to be contaminated from past operations are conhned to the Industrial Area consisting of approximately 20 acres includmg the Plant Protected Area, the Radwaste Compound, and material transport routes and radoactive material storage locations.

The Non-Impacted portion of the BRP site consists of low wetlands with standmg water to mature forested uplands and can be characterized by h c k forest and uneven terrain. The remaining site area is largely undeveloped/un&sturbed land ttacts with the topography rangmg fiom rocky, open spaces to steep, rocky Msides that are heavily wooded and overgrown with brush in many locations.

Big Rock Paint Restoration Project 2 Final Confirmatory Survey Report 1710/Reports/2006-09-07

OBJECTIVES The objectives of the confirmatory surveys were to: (1) provide independent contractor field data reviews; and (2) collect independent radlological data for use by the NRC in determining the adequacy and accuracy of the licensees procedures and FSS results.

DOCUMENT REVIEW ORISE has reviewed the licensees survey classification supporting documentation for adequacy and appropriateness talung into account the commitments contained in the LTP and MARSSIM (CEC 2004 and NRC 2000, respectively). The FSS data have not been provided; therefore, ORISE has not reviewed the FSS data for the survey units (SU) for which ORISE performed c o n h a t o r y surveys.

Various aspects of the measurement process that may affect the quality of environmental data results were also evaluated with a soil sample analytical comparison between the licensees contractor and ORISE laboratories.

PROCEDURES A survey team from ORISE visited the BRPRJ? and performed visual inspections, and measurement and s a m p h g activities. The confirmatory survey activities were conducted in accordance with site-specific survey plans and with the OFUSE Survey Procedures and Quality Assurance Manuals (ORISE 2005a, 2006a, 2004, and 200Sb). The confirmatory surveys of the Turbine Bulldmg were performed on September 20, 2005; the survey results were reported in a letter report dated November 17,2005 and are also included in this report (ORISE 2005~).Survey activities for the remaining areas were performed during the period of June 13 through 16,2006; those results are also w i h t h s report.

SURVEY UNIT CLASSIFICATION The FSS process described in MARSSIM includes use of characterization surveys and site hstory to

&vide the site into properly classified SUs based on their appropriate physical characteristics.

Modifications to the SU classification can be made based on new survey findmgs or information.

The SUs are h t e d in size based on their classification, exposure pathway modeling assumptions and site-specific conditions. The licensee has asslgned each Open Land SU with an initial Big Rock Pomt Restoration Project 3 1710/Repom/2006-09-07 Final Confirmatory Survey Report

classification based on the historical site assessment (HSA), operational radiation surveys, and additional measurements/samples obtained during decommissioning activities that were used to c o n h the classification of these areas (CEC 2004).

As specified in MARSSIM, the level of survey effort required for a given SU is determined by the potential for residual contamination as indicated by the classification delineation. The SUs with a higher classification, and thus having a hgher potential of containing elevated quantities of radoactivity, received a tugher degree of survey effort. Accordingly, the licensee used the following MARSSIM classifications for the Open Land Area (OM) SUs:

. Non-Impacted: Areas where there is no reasonable possibihty of residual contamination from site operations.

. Impacted Areas: Areas with a possibility of containing residual contamination in excess of natural background or fallout levels. Impacted areas include Class 1,2, and 3 Areas.

Class 1: Areas that have, or had prior to remediation, a potential for radoactive contamination (based on site hstory) or known contamination (based on previous surveys) above the moddied derived concentration gudelme levels (DCGLJ. Areas containing residual contamination in excess of the DCGL, prior to remedation should be classified as Class 1 areas.

. Class 2: Areas that have, or had prior to remedution, a potentd for radioactive contamination or known contamination, but are not expected to exceed the D C G L .

. Class 3: Any impacted areas that are not expected to contain any residual radoactivity, or are expected to contain levels of residual activity at a small fraction of the DCGL, based on site operating history and previous radiological surveys.

In general, the licensee had deslgnated classification delineation for all assigned SUs. Accordmgly, the SUs located withm the confines of the Industrial Area (consisting of the Protected Area, the Radwaste Compound, and all material transport routes and storage locations) had been assigned a Class 1 status. In addition, the impacted areas immediately outside the Class 1 areas had been designated as Class 2 SUs. These buffer zones are areas where radionuclides may have migrated Btg Rock Pomt Restoration Project 4 1710/Reporn/2006-09-07 Fmd Confrmatory Survey Report

beyond the Class 1 SU boundaries. All remaining impacted areas had been assigned by the licensee as Class 3 SUs.

The majority of the land surroundmg the industrial area of the site had been classified as Non-Impacted (comprising approximately 430 acres). These Non-Impacted areas were not surveyed because these areas had no reasonable possibility of containing licensed radoactive materials.

REFERENCE SYSTEM Measurements and sampltng locations were recorded on site plot plans and referenced to the existing BRPRP grid system.

SURFACESCANS Surface scans for gamma radiation were performed w i h accessible portions of selected SUs and were dependent upon SU condltions such as, if area contained backfill soil, concrete pads, or gravel roadways. Surface scans were also performed at judgmentally selected locations in all selected OLA SUs where radioactivity may have concentrated during operations. These locations included transport routes, drainage areas, streambeds, and areas of known radiologcal releases.

Additional area scans were performed, dependmg on findmgs as the survey progressed and project time-constraints. Particular attention was gven to cracks and fissures in the surfaces, areas of known radiological releases from the BRP, and other locations where material may have accumulated.

Gamma scans were performed over a minimum of 20% and a maximum of 80% of the accessible ground surfaces in the available SUs. Scans were performed using so&um iodide (NaI) scinttllation detectors for direct gamma radiation coupled to ratemeters with audlble indlcators. Locations of elevated h e c t radiation were marked for further investigation.

SOIL SAMPLING CEC provided ORISE with three characterization soil samples for comparison analyses. These samples represent several locations on the site with varying degrees of activity. These samples allowed ORISE to more fully assess the quality of the licensees radioanalytical procedures. As such, these sample locations are not indicated on the figure and were not part of the c o n h a t o r y surveys Big Rock Point Restoration Project 5 1710/Repons/2006-09-07F d Confirmatory Survey Report

of the selected SUs. ORISE collected surface (0 to 15 cm) soil samples at 46 judgmentally selected locations from w i h the SUs that were selected for confirmatory survey activities. Selected sample locations focused on the Impacted North Area, the Turbine and Containment Buildmg Excavations and the major transport, shoreline, and trafficked areas. Adhtionally, locations exhibiting gamma radiation distinguishable from background were selected for sampling.

SAMPLE ANALYSIS AND DATA INTERPRETATION Samples and data'were returned to ORISE's laboratory in Oak kdge, Tennessee for analysis and interpretation. Samples were analyzed in accordance with the ORISE Laboratory Procedures Manual (ORISE 2006b). Soil and sedunent samples were analyzed by gamma spectroscopy and results reported in picocuries per gram @Ci/g). The radionuclides of interest were CO-60 and (3-137; however, spectra were also reviewed for other gamma-emitting fission and activation products associated with the BRPRP, and other identitiable total absorption peaks (TAPS).Tritium analyses were performed on the five soil samples collected from the Turbine Building Excavation.

The data generated were compared with the applicable site-specific guidelmes established for the BWRP site (CEC 2004).

FINDINGS AND RESULTS COMPARISON ANALYSES Three samples that CEC had analyzed at the on-site laboratory were analyzed by ORISE. The analyacal results for the comparative evaluation of the CEC characterization samples are provided in Table 1 and inhcated that the CEC contractor laboratory data, within the parameters of sample preparation and analytical procedures, were comparable with ORISE's analyacal results.

TURBINE BUILDINGEXCAVATION: CLASS 1 The results for the confirmatory survey activities within the Turbine Buildmg Excavation were provided in a previous report (ORISE 200%). Gamma scans, performed over 90% of accessible portions of the Turbine Butldmg ('IB)Excavation, did not identify any locations of elevated duect gamma radiation on the soil surfaces. Ambient gamma scan radtation levels ranged from 800 to 1,600 counts per minute (cpm). Soil samples were collected from five locations within the TB Big Rock Point Restoration Project 6 1710/Repom/2006-09-07 Final C o n h t o l y Survey Report

excavation (Figure 4). The range of radionuclide concentrations for the five confirmatory soil samples collected by ORISE from the TB excavation are as follows:

H-3 Mn-54 CO-60 cs-l37 Eu-152 Eu-154 Eu-155

-1.6 to 2.5 0.00' to 0.01 -0.01 to 0.02 0.00 to 0.01 -0.02 to 0.01 -0.01 to 0.01 0.00 to 0.04 A complete listing of the TB confirmatory sample results is presented in Tables 2 and 3; the tritium results are provided in Table 2 and the results for the major gamma-emitting radionuclides are provided in Table 3.

CONTAWMENT BUILDING EXCAVATION: CLASS 1 Gamma scans, performed over 80% of accessible portions of the Containment B d d m g (CB)

Excavation, did not identdy any locations of elevated direct gamma radation on the soil surfaces.

Gamma scan radlation levels ranged from 1,000 to 2,000 cpm. Soil samples were collected from six locations w i h the CB excavation (Figure 5). The range of radionuclide concentrations for the six confirmatory soil samples collected by ORISE from the CB excavation are as follows:

Mn-54 CO-60 cs-l37 Eu-152 Eu-154 Eu-155

-0.01 to 0.01 -0.02 to 0.03 0.00a to 0.06 -0.02 to 0.02 -0.02 to 0.09 0.01 to 0.03 A complete listing of the CB confirmatory sample results is presented in Table 3.

IMPACTED NORTH h E A SURVEY UNITS: CLASS 1 The Class 1 Impacted North Area Survey Units selected for c o n h a t o r y surveys were SUs 1 through 10. Gamma scan coverage varied from 20 to 60% of accessible portions of these SUs and was dependent upon site conditions such as, if that area contained backfill soil, concrete pads, or gravel roadways. Gamma scans identified two locations of elevated gamma radiation w i h SU 5(2)

Big Rock Pomt Restoration Project 7 1710/Repom/2006-09-07 Find Confirmatory Survey Report

that were 25,000 and 50,000 cpm, respectively. The area containing these two locations was identified by CEC personnel as an area that had not been survyed; CEC identified two pieces of concrete that contained the elevated gamma radlation during their remediation efforts. Gamma scans of the remaining accessible portions of SUs 1 through 10 did not identify any other locations of elevated duect gamma radiation on the soil surfaces. Gamma scan radlation levels ranged from 800 to 3,000 cpm. Soil samples were collected Gom 18 judgmentally selected locations withLn these SUs (Figures 6 to 16); soil samples were not collected from the two elevated gamma radiation level locations as these locations were being remedtated while ORISE was on site. The ranges of radionuclide concentrations for the 18 confkmatory soil samples collected by ORISE from these SUs are as follows:

scan Survey Eu-154 Range Mn-54 CO-60 cs-l37 Eu-152 Eu-155 Unita (kcpm) 1 1.0 to 2.0 -2 __- _-- _-_ ___ -_-

2 1.2 to 2.2 ___ _-- --- --_ _-- ---

3 1.0 to 2.5 O.O@ to 0.01 0.01 to 0.03 0.15 to 0.24 -0.02 to 0.00 -0.07 to 0.00 -0.01 to 0.01 4 0.8 to 1.2 0.00 0.01 to 0.02 0.04 to 0.12 -0.01 -0.06 to -0.03 0.01 to 0.02 5(1) 1.0 to 2.0 0.00 to 0.02 0.05 to 0.20 0.04 to 0.37 0.00 to 0.01 0.00 to 0.02 0.01 to 0.03 5P) 1.0 to 2.0 -0.01 to 0.01 0.12 to 0.24 0.23 to 0.44 -0.02 to 0.02 -0.10 to 0.00 0.01 to 0.03 6 1.0 to 2.5 -0.01 to 0.00 0.01 to 0.03 0.03 to 0.07 0.00 to 0.01 -0.07 to 0.02 -0.01 to 0.02 7 1.1 to 2.2 0.00 to 0.01 0.03 to 0.07 0.08 to 0.09 -0.01 to 0.01 -0.02 to -0.01 -0.01 to 0.00 8 1.o to 2.2 --- --_ --_ -_- __- _--

9 1.0 to 2.0 0.00 0.00 to 0.01 0.00 to 0.01 -0.03 to 0.00 -0.09 to 0.00 0.02 to 0.06 10 1.0 to 2.0 0.01 0.01 0.05 -0.03 -0.05 -0.01 A complete listing of these confirmatory sample results is presented in Table 3.

Big Rock Point Restoration Project 8 1710/Reports/Z006-09-07Final Confmrory S w e y Report

IMPACTED NORTH AREA SURVEY UNITS: CLASS 2 The Class 2 Impacted North Area Survey Units selected for c o n h a t o r y surveys were SUs 12, 15 (Waste Area), 15 (Septic Drainfield) and 16. Gamma scan coverage varied from 20 to 80% of accessible portions of these SUs and was dependent upon site conditions such as, if that area was heavily vegetated or along the Lake Michigan shorehe. Gamma scans did not identify any locations of elevated du-ect gamma radiation on the soil surfaces. Gamma scan radlation levels ranged from 800 to 5,000 cpm. Soil samples were collected from seven judgmentally selected locations within these SUs (Figures 17,19 and 20). The range of radionuclide concentrations for the seven confirmatory soil samples collected by ORISE from these SUs are as follows:

I Range of Gamma Scan Radiation Levels and Radionuclide Concentrations in Class 2 Impacted Survey Scan Range North Area Survey Units Confirmatory Soil Samples (pCi/g)

Mn-54 coao cs-137 EU-152 EU-154 EU-155 unit= (kcpm)

~ ~~~~ ~~~~ ~

12 1.0 to 5.0 O.OOb to 0.01 0.00 to 0.44 0.11 to 0.35 -0.02 to 0.00 -0.08 to 0.01 -0.01 to 0.02 15 (Waste _-- _-- ---

0.8 to 1.2 Area)

I I I I 16 1.0 to 3.0 0.00 0.08 to 0.09 0.16 to 0.68 -0.02 to 0.00 -0.02 to 0.00 0.03 A complete listing of these confirmatory sample results is presented in Table 3 IMPACTED NORTH AREA SURVEY UNITS: CLASS 3 The Class 3 Impacted North Area Survey Units selected for confitmatory surveys were SUs 14 and 59 (59 Acres). Gamma scan coverage was 20% of accessible portions of these SUs and was dependent upon site conditions such as, if that area was heavily vegetated or along the Lake Michigan shoreline. Gamma scans did not identlfy any locations of elevated direct gamma radation on the soil surfaces. Gamma scan radlation levels ranged from 1,000 to 5,000 cpm. Soil samples were collected from five judgmentally selected locations w i h these SUs (Figures 18 and 21). The Big Rock Point Restoration Project 9 1710/Repom/2006-09-07 Find Confirmatory Survey Report

ranges of radtonuclide concentrations for the five confirmatory soil samples collected by ORISE from these SUs are as follows:

Survey Unita scan Range Mn-54 CO-60 cs-l37 Eu-152 Eu-154 Eu-155 W P 4 14 1.0 to 5.0 -0.01 to 0.02 0.01 to 0.02 0.05 to 0.21 O.OOb to 0.01 -0.04 to 0.00 -0.01 to 0.01 59 1.5 to 5.0 0.00 to 0.01 0.00 to 0.02 0.15 to 0.26 -0.01 to 0.03 0.02 to 0.03 -0.01 to 0.03 ACCESS AND POWER LINEROADS The Access and Power h e Roads were also surveyed. Gamma scan coverage was 20% of accessible portions of these roads (and in the immediate vicinity of these roads) and was dependent upon site conchtions such as, if that area was heavily vegetated or paved. Gamma scans dld not identify any locations of elevated dnect gamma rachation on the soil surfaces. Gamma scan rachation levels ranged from 1,000 to 3,000 cpm. Soil samples were collected from five judgmentally selected locations within these SUs (Figure 22). The range of radionuclide concentrations for the five confirmatory soil samples collected by OEUSE from these SUs are as follows:

Range of Gamma Scan Radiation Levels and Radionuclide Concentrations in Access and Power Line Roads Confirmatory Soil Samples (pCi/g)

Scan Range Survey Unit' Mn-54 CO-60 cs-137 Eu-152 Eu-154 Eu-155 (kcpm)

Access and Power Line 1.0 to 3.0 -0.01 to 0.01 0.01 to 0.05 0.12 to 0.50 -0.02 to 0.01 -0.03 to 0.12 0.01 to 0.06 Roads 59 Big Rock Pomt Restoration Project 10 1710/Reports/2006-09-07 Final C o n f m t o r y Survey Report

COMPARISON OF RESULTS WITH GUIDELINES The primary radionuclides-of-concern (ROC) for the BRPRP are beta-gamma emitters @.e.,fission and activation products) resulting from reactor operation. However, Cs-137 and CO-60have been identified during characterization as the predominant radionuclides present. The BRPW has developed site-specific derived concentration p d e l i n e levels (DCGLs) based on dose modehg to ensure that the average member of the critical group will not exceed an annual total effective dose equivalent PEDE) of 25 m i h e m , excluding background radoactivity. The DCGLs for soil d include the site-specific DCGLs of 3.21 pCi/g for CO-60and 13.2 pCi/g for Cs-137, in addtion to the application of the unity rule. Table 4 provides a summary of the soil DCGLs.

Of the 46 soil samples collected for confirmatory surveys, all were below the respective site-specific gmdehes for each ROC. A complete listing of the confirmatory soil sample results is presented in Table 3.

SUMMARY

At the request of the Division of Decommissioning/Waste Management, U.S. Nuclear Regulatory Commission, the Oak Ridge Institute for Science and Education conducted c o n h a t o r y surveys of the Big Rock Point Restoration Project during the periods of September 20,2005 and June 13 through 16,2006. The survey activities included visual inspections and radological surveys that included surface scans and soil samphg.

The results of the laboratory confirmatory analysis indcated that the CEC laboratory data were consistent and in agreement with ORISEs analpcal results.

ORISE noted that approximately 50% of the soil surfaces in several survey units had previously been backfilled; therefore, confirmatory survey activities were b t e d in those areas.

The results of the c o n h a t o r y surveys indxated that, with a couple of exceptions in Survey Unit 5(2) in an area that had not been previously surveyed by Consumers Energy Corporation personnel, gamma radiation levels were a t ambient background levels. The locations in Survey Unit 5(2) were being remeduted while ORISE was on site; however, ORISE did not resurvey or collect samples from these areas. All confirmatory sample results were well within the respective derived Big R o d Pomt Restoraclon Project 11 F 1710/Repom/2006-09-07 d Confirmatory Survey Report

concentration p d e l t n e levels (DCGLs) for the radionuclides-of-concern as specified in the License Termination Plan [L?p (CEC 2004)l.

Due to the percentage of backfilled areas w i t h the survey units selected for c o n h a t o r y activities, ORISE could not verify the miscellaneous excavations within selected survey units. However, ORISE was able to perform c o n h a t o r y surveys within the main excavations for the Turbine and Containment Buildings. ORISEs radiological survey data confirm that the radiologcal con&tions of the portions of the survey units that were surveyed are suitable for unrestricted use in accordance with the clean up criteria cited in the licensees LTP.

Big Rock Pomt Restoration Project 12 1710/Reports/2006-09-07Final Confirmatory Survey Report

FIGURES Bsg Rock Point Restorauon Project 1710/Reports/2006-09-07 Final Confmatory Survey Report