ML100880265

Nasa, Submittal of Final Status Survey Report, Reactor Office and Laboratory Building, for the Plum Brook Reactor Facility to Be Reviewed

ML100880265
Person / Time
Site:	Plum Brook
Issue date:	03/25/2010
From:	Peecook K US National Aeronautics & Space Admin (NASA), John H. Glenn Research Ctr at Lewis Field
To:	Document Control Desk, NRC/FSME
References
Download: ML100880265 (129)

Text

National Aeronautics and Space Administration John H. Glenn Research Center Lewis Field Plum Brook Station Sandusky, OH 44870 March 25, 2010 Reply to Attn of: QD U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555

Subject:

Final Status Survey Report, Attachment 1, Reactor Office and Laboratory Building, for the Plum Brook Reactor Facility, Licenses Nos. TR-3, Docket No. 50-30 and R-93, Docket No, 50-185 Enclosed for your review is the first in a series of reports on the Final Status Surveys supporting eventual termination of the licenses for the Plum Brook Reactor Facility.

As previously discussed with members of the NRC Staff, the complete Final Status Survey Report will consist of series of Attachments. Each attachment addresses an individual survey area or group of survey areas or environmental areas as described in our NRC approved Final Status Survey Plan. The final submission will be the main body of the Final Status Survey Report. It will consolidate and summarize the details presented in the Attachments. We committed to the staff to submit the Attachments as they were generated to allow easier staff review of the reports over a period of time.

This first in the series of Attachments addresses the Final Status Survey of the Reactor Office and Laboratory Building (Building 1141). It supports our conclusion that radiological remediation of the building has been completed and the structure meets the criteria for unrestricted release specified in 10 CFR 20.1402.

Should you have any questions or need additional information, please contact me a NASA Plum Brook Station, 6100 Columbus Avenue, Sandusky, Ohio 44870, or by telephone at (419) 621-3277.

Sincerely, Keith M. Peecook NASA Decommissioning Program Manager w~fso(

Enclosure

1. Plum Brook Reactor Facility Final Status Survey Report, Attachment 1, Reactor Office and Laboratory Building, revision 0, dated March 25, 2010 cc:

USNRC/C. J. Glenn (FSME)

USNRC/J. Webb (FSME)

USNRC/W. G. Snell RIII/DNMS/DB ODHi/M. J. Rubadue

Plum Brook Reactor Facility Final Status Survey Report Attachment 1 Revision 0 Reactor Office and Laboratory Building (Building 1141) i

FINAL STATUS SURVEY REPORT ROUTING AND APPROVAL SHEET Document

Title:

Final Status Survey Report, Attachment 1 Reactor Office and Laboratory Building (Building 1141)

Revision Number: 0 ROUTING SIGNATURE DATE Prepared By B. Mann j/'qw5 .3

_ t__

Prepared By N/A REVIEW & CONCURRE5qJ9, 4 _

Independent Technical Reviewer R. Case 'S1/ ,6 0 Other Reviewer, QA Manager J. Thomas ,3/b 5" Other Reviewer N/A FSS/Characterization Manager W. Stoner ,31./d/O S NASA Project Radiation Safety Officer W. Stoner 3/257/ta ii

NASA PBRF DECOMMISSIONING PROJECT CHANGE/CANCELLATION RECORD DOCUMENT TITLE: Final Status DOCUMENT NO: NA REVISION NO: 0 Survey Report, Attachment 1, Reactor Office and Laboratory Building (Building 1141)

Revision 0: Initial issue of Report Form AD-0 1/3 Rev 1 iii

Plum Brook Reactor Facility FSSR Attachment 1, Rev. 0 LIST OF EFFECTIVE PAGES DOCUMENT NO: NA REVISION NO: 0 Page No. Revision Level Page No. Revision Level Page No. Revision Level Cover Page 0 Routing & Approval 0 Sheet Change/Cancellation 0 Record LOEP 0 TOC 0 List of Tables & List 0 of Figures List of Acronyms & 0 Symbols, 2 pages Text, pages 1 through 0 30 Appendix A 0 17 pages Appendix B 72 pages________ 0 ________________

4 .4.

I d I.

I AD-01/5 Form Rev 2 I

iv

Plum Brook Reactor Facility FSSR Attachment 1, Rev. 0 TABLE OF CONTENTS 1.0 Introduction .................................................................................................................... 1 2.0 RO LB D escription ................................................................................................. 2 2.1 Building Construction .............................................................................................. 2 2.2 Building System s and Services ................................................................................ 4 2.3 Building M odifications ............................................................................................ 5 2.4 Final Configuration and Scope ................................................................................ 6 3.0 ROLB History and Operations with Radioactive Materials .................................. 6 3.1 Chronology .................................................................................................................... 6 3.2 O perations w ith Radioactive M aterials ..................................................................... 7 3.3 D isposition of M aterials in the Post-Shutdow n Period ............................................ 8 3.4 D ecom m issioning ................................................................................................... 10 4.0 Survey Design and Implementation for the ROLB ............................................... 11 4.1 FSS Plan Requirem ents ......................................................................................... 12 4.2 A rea C lassification and Survey U nit Breakdow n .................................................... 13 4.3 N um ber of M easurem ents and Sam ples ................................................................. 16 4.4 Instrum entation and Measurem ent Sensitivity ...................................................... 19 5.0 RO LB Survey R esults .............................................................................................. 21 5.1 Surveys and Investigations ..................................................................................... 21 5.2 Fixed M easurem ents and Tests .............................................................................. 24 5.3 A LA RA Evaluation ............................................................................................... 26 5.4 Com parison w ith EPA Trigger Levels ................................................................. 28 5.5 Conclusions ............................................................................................................ 28 6.0 References ..................................................................................................................... 29 7.0 Appendices .................................................................................................................... 30 A ppendix A - Exhibits ...................................................................................................... 30 Appendix B - Survey Unit Maps and Tables Showing Measurement Locations and Results

......................................................................................... *.................................................... 30 V

Plum Brook Reactor Facility FSSR Attachment 1, Rev. 0 LIST OF TABLES Table 1, R O LB Sum ps ........................................................................................................... 5 Table 2, Contaminated Areas Identified in ROLB Decommissioning Surveys ........................... 11 Table 3, ROLB Radionuclide Activity Fractions and Gross Activity DCGLs ......................... 12 Table 4, Class-Based Survey Scan Coverage and Action Level Requirements ....................... 13 Table 5, ROLB Survey Units for FSS ...................................................................................... 13 Table 6, ROLB Survey Unit Breakdown by Major Elevation ................................................. 15 Table 7, ROLB Survey Unit Breakdown by MARSSIM Classification .................................. 15 Table 8, ROLB Survey Design Sum m ary ................................................................................ 17 Table 9, VSP Sensitivity Analysis Results for Survey Unit RO-2-1 Design ............................ 18 Table 10, Detection Sensitivities of Field Instruments ............................................................. 20 Table 11, Scan Survey R esults ................................................................................................. 22 Table 12, ROLB Total Surface Beta Activity Measurement Summary and Test Results ........ 25 Table 13, Screening Level Values for ROLB and Radionuclide Activity Fractions ................ 27 LIST OF FIGURES Figure 1, PBRF NW Area Showing Reactor Building, ROLB and Support Buildings .............. 3 vi

Plum Brook Reactor Facility FSSR Attachment 1, Rev. 0 LIST OF ACRONYMS & SYMBOLS alpha; denotes alpha radiation, also type I error probability in hypothesis testing A Area, also detector open area AEMC Area corresponding to the area factor calculated using the scan MDC AEC Atomic Energy Commission ALARA As Low As Reasonable Achievable AF Area Factor beta; denotes beta radiation, also type 1I error probability in hypothesis testing bi background counts in observation interval BR Background count rate BPL Byproduct License CFR Code of Federal Regulations cm centimeters cm2 square Centimeters cpm counts per Minute A delta, DCGLw - LGBR d' Scan surveyor sensitivity index DCGL Derived Concentration Guideline Level DCGLEMC DCGL for small areas of elevated activity, used with the Elevated Measurement Comparison test (EMC)

DCGLW DCGL for average concentrations over a survey unit, used with statistical tests.

(the "W" suffix denotes "Wilcoxon)"

dpm disintegrations per minute Ei Detector, or instrument efficiency E, Surface efficiency Et Total efficiency EMC Elevated Measurement Comparison EPA US Environmental Protection Agency FH Fan House, Building 1132 FSS Final Status Survey FSSP Final Status Survey Plan FSSR Final Status Survey Report 7 gamma g gram HTD Hard To Detect HL Hot Laboratory, Building 1112 HRA Hot Retention Area i observation counting interval during scan surveys in. inch HVAC Heating, ventilation and air conditioning LMI Ludlum Measurements, Inc.

LBGR Lower Bound of the Gray Region m2 square meters MARSSIM Multi-Agency Radiation Survey and Site Investigation Manual vii

Plum Brook Reactor Facility FSSR Attachment 1, Rev. 0 LIST OF ACRONYMS & SYMBOLS. Continued MDC Minimum Detectable Concentration MDCscan Minimum Detectable Concentration for scanning surveys MDCstatic Minimum Detectable Concentration for static surface activity measurements MDCR Minimum Detectable Count Rate mrem millirem MW Megawatt MWH Montgomery Watson Harza, Inc.

NASA National Aeronautics and Space Administration N Number of FSS measurements or samples established in a survey design NA Not Applicable Nal Sodium Iodide NRC US Nuclear Regulatory Commission OW&R Outside Walls and Roof PBRF Plum Brook Reactor Facility PNL Pacific Northwest Laboratory (D Standard normal distribution function p surveyor efficiency for scan surveys pCi/g picocuries per gram

% percent QC Quality Control RESRAD RESidual RADioactive - a pathway analysis computer code developed by Argonne National Laboratory for assessment of radiation doses. It is used to derive cleanup guideline values for soils contaminated with radioactive materials RESRAD-BUILD A companion code to RESRAD for evaluating indoor building contamination and developing site-specific DCGLs ROB Reactor Office Building, Building 1142 ROLB Reactor Office and Laboratory Building, Building 1141 s seconds G generic symbol for standard deviation of a population S+ Sign Test statistic SEB Reactor Service Equipment Building, Building 1131 SNM Special Nuclear Materials SNL Sandia National Laboratory SR Survey Request STMA Surface Measurement Test Area ts background count time tb sample count time TBD Technical Basis Document P Mean activity concentration UCM Unusual Condition Measurement UL Upper limit of the confidence interval about the mean VSP Visual Sample Plan Z1.1 Proportion of standard normal distribution values less than I -a ZI-0 Proportion of standard normal distribution values less than 1-3 0Mathematical symbol for infinity viii

Plum Brook Reactor Facility FSSR Attachment 1, Rev. 0 1.0 Introduction This report presents the results of the final status radiological survey of the Plum Brook Reactor Facility (PBRF) Reactor Office and Laboratory Building (ROLB, Building 1141). It is Attachment I of the PBRF Final Status Survey Report (FSSR) 1. This attachment describes the ROLB, its operational history and final condition for the final status survey (FSS). It describes the methods used in the FSS and presents the results of the survey measurements.

As stated in the PBRF Final Status Survey Plan (FSSP) [NASA 2007], the goal of the decommissioning project is to release the facility for unrestricted use in compliance with the criteria in US NRC 10CFR20 Subpart E. The principal criterion is that the dose to future site occupants will be less than 25 mrem/y. Subpart E also requires that residual contamination be reduced to levels as low as reasonably achievable (ALARA). A Derived Concentration Guideline Level (DCGL) for residual surface contamination has been established for the ROLB. Considering the radionuclide mixture established for the ROLB, the gross beta DCGL is 27,166 dpm/100-cm 2 . The DCGLs for soil beneath the ROLB are: Co-60, 3.8 pCi/g; Sr-90, 5.4 pCi/g and Cs-137, 14.7 pCi/g.

The survey measurement results and supporting information presented herein demonstrate that residual contamination levels in each survey unit of the ROLB are well below the DCGL.

Additionally, it is shown that residual contamination has been reduced to levels that are consistent with the ALARA requirement. Therefore, the ROLB meets the criteria for unrestricted release.

Section 2.0 of the report provides a description of the ROLB. This includes the building layout, its relation to other PBRF buildings and facilities, design and materials of construction, building contents and use, systems and services, building modifications, final configuration of the ROLB for the FSS and scope of the FSS for this building.

A brief history of operations is presented in Section 3.0. A chronology of significant milestones is followed by history of operations with radioactive materials. Post shutdown and decommissioning activities are summarized.

Section 4.0 presents the FSS design for the ROLB. This section includes FSS Plan requirements applicable to the ROLB, breakdown into survey units and assignment of MARSSIM classification to each, the survey design approach, and instrumentation used for the FSS and measurement sensitivities.

Survey results are presented in Section 5.0. This section includes a summary of the FSS measurements performed in the ROLB survey units, comparison to the DCGL, tests performed and an evaluation of residual contamination levels relative to the ALARA criterion.

Supporting information is contained in Appendices. Appendix A contains photos and schematics to supplement the text. Survey design maps and tables of coordinates for the measurement locations in each survey unit are provided in Appendix B.

1 The PBRF Final Status Survey Report comprises the report main body and several attachments. The attachments present survey results for individual buildings and open land areas. The entire final report will provide the basis for requesting termination of NRC Licenses TR-3 and R-93 in accordance with IOCFR50.82 (b) (6).

1

Plum Brook Reactor Facility FSSR Attachment 1, Rev. 0 2.0 ROLB Description The ROLB is a three story, 27,000 ft 2 (floor area) structure located immediately west of the Reactor Building. The ROLB, identified as Building 1141, is shown on the PBRF site map in Figure 1.

Exhibit 1, Appendix A, shows the building, viewed from the west with the Reactor Building at the rear in 2009. The ROLB contained offices, a conference room, a classroom, a library, repair shops, health physics offices, a first aid facility, instrument calibration shop, new fuel vault, equipment calibration facility, and radiochemistry laboratories. The east wall of the ROLB abuts the west wall of the Reactor Building. The east end of the ROLB extends 53 ft. south from the northwest corner of the Reactor Building along the west wall. The buildings are structurally independent. Exhibits 2-4,. of Appendix A, show the I st floor, 2 nd floor and basement layouts.

The ROLB was initially occupied in early 1959, prior to Plum Brook Test Reactor criticality in June 1961. It was occupied through the entire period of reactor operations and during the post-shutdown period until July 1, 1973.

Most PBRF management and technical staff occupied offices in the ROLB until completion of the Reactor Office Building (ROB, Building 1142) in 1965. During the period from 1959 to 1965, the ROLB housed about 75 NASA managers, technical staff (scientists and engineers) administrative staff and technical support staff. Technical support staff included electronics technicians, mechanics, machinists and contractor Health Physics personnel. The number of personnel occupying the ROLB was reduced somewhat when ROB office space became available. The ROLB occupancy remained at approximately 60 until 1968 when NASA budget cuts resulted in minor reduction of reactor staff housed in the building. Beginning in January 1973, with termination of reactor operations, ROLB occupancy ramped down until the end of June 1973 when the building was vacated.

The elevation of the ROLB first floor is at grade level, corresponding to Reactor Building 0 ft.

elevation (625 ft. above mean sea level). Other major elevations are: basement, -15 ft.; second floor, 12 ft. and roof, 24 ft. 3 in. The ROLB connects to the Reactor Building through doorways at the basement, first and second floor levels. The Reactor Building roof is accessible from the ROLB roof.

2.1 Building Construction The building is constructed of poured concrete floors supported by concrete and steel columns and beams. Basement walls are poured concrete. First and second floor exterior walls are concrete block with brick veneer. The roof is of composite construction - a concrete slab covered with light concrete fill, rigid insulation and a tar-stone mixture. The roof was modified in the mid 1980's (and possibly a second time in the 1990's) with the addition of foam sealant to eliminate in-leakage to the building [PBRF 2009].2 A variety of surface and finish materials were used in ROLB construction and many remain at present. Door and window frames are steel, windows are of steel-framed glass construction.

Interior doors are mostly wood, except for a metal door on the new fuel vault. The three 2 The foam sealant was removed in 2009 to provide access to the original roof surface for the Final Status Survey.

2

Plum Brook Reactor Facility FSSR Attachment 1, Rev. 0 double doors connecting the ROLB and Reactor Buildings and several exterior entrance doors are of metal construction. The first and second floors were covered with asbestos tile. Interior wall coverings included painted concrete, metal lath and plaster, drywall and paneling.

Figure 1, PBRF NW Area Showing Reactor Building, ROLB and Support Buildings 5EB 5ERVICE5 EQUIPMENT BUILDING L PH - FAN I1OU5E WlIB - WA5TE HANDLING BUILDINGU PH- PRIMARY' PUMP IiOU5E KOL1 - REACTOR O~ffICE 4 LA50RATORY BUILDING MRA - HOT RETENTION AREA I 3

Plum Brook Reactor Facility FSSR Attachment 1, Rev. 0 2.2 Building Systems and Services The ROLB systems included standard laboratory building services as well as radioactive air and liquid waste handling systems. Systems in the ROLB are briefly described to provide background information and to identify contaminated systems and the building areas potentially impacted by them. It is noted that most of the process systems and utility services at the PBRF serviced multiple buildings, including the ROLB.

The ROLB first and second floor rooms were cooled by individual room heating/air conditioning units. Basement cooling was handled by a 4500 cfm, multi-zone unit with fresh air makeup. Cooling air exhaust from the basement was tied in to the 16-inch experimental waste air main in the Reactor Building -15 ft. elevation. The 16-inch waste air line exhausted through the PBRF stack via the Fan House. The second floor laboratory area was supplied with forced air at 6000 cfm from the second floor office area HVAC surplus. There were four roof ventilators, one from the basement, one from the washrooms, one from the first and second floor office area and one from a filter unit which exhausted surplus air from the laboratory work area. Exhaust air from laboratory hoods in the ROLB was routed through individual HEPA filter units to exhaust fans located on the roof where the air was discharged to the atmosphere.

High-pressure steam for room heating and domestic hot water was supplied to the ROLB by two boilers located in the Service and Equipment Building (SEB). Domestic water was supplied to the ROLB and the other PBRF buildings from the Sandusky water treatment plant.

Fire protection system water was supplied to the ROLB as part of an 8 in. piping loop which delivered raw Lake Erie water from Plum Brook Station Storage Reservoir No. I to the Reactor Building, Hot Laboratory (HL) Building and the ROLB. The HL, Building 1112, is adjacent to the Reactor Building south side as shown in Figure 1.

De-ionized water to the PBRF buildings, including the ROLB was supplied from mixed bed deionizers located in the SEB. Water from the PBRF Process Water System was also supplied to the ROLB via a 2 inch line that entered the basement from the Reactor Building -15 ft.

elevation. If deionized water was unavailable, water from the Process Water System was used for equipment cleaning, and dilution water. Secondary cooling water was used for equipment cooling by heat transfer and dissipation through the PBRF cooling tower.

Service and instrument air was supplied to laboratories and test areas in the ROLB from the utility air system in the SEB. Natural gas was supplied to the PBRF buildings including the ROLB by the Columbia Gas Company. A 2 in. line tied in to an 8 in. main supply line at the SEB entered the ROLB basement. Gas was supplied to individual laboratories by one-inch lines.

Bottled gas was supplied to ROLB laboratories from supply tank cylinders connected to a manifold located in the ROLB basement. Seventeen 1/2 inch diameter lines from the manifold supplied the individual laboratories. Commonly available gases included helium, argon, CO 2 and nitrogen.

4

Plum Brook Reactor Facility FSSR Attachment 1, Rev. 0 The ROLB contained collection sumps for radioactive and non-radioactive process waste water and sanitary waste. These are summarized in Table 1.

Table 1, ROLB Sumps System Description Hot Drain The hot sump collected radioactively "hot" drainage from the radiochemistry Sump laboratories (primarily sinks and laboratory eye washes) and other locations where wastewater drainage originated directly or indirectly from radioactively contaminated areas. Sump output was routed to the Hot Retention Area through the Hot Laboratory Hot Pipe Tunnel for storage decay, cleanup or controlled release.

Hot-Cold The hot-cold sump collected potentially contaminated water from the above sources Sump plus second floor area floor drains, including the rest rooms and locker room.

Cold The cold sump collected wastewater from all uses that were not likely to be Sump contaminated. This included the It floor rest room floor drains.

Sewage The sewage sump collected all wastewater from the lavatory areas (toilets, showers, Sump sinks, etc.), except the floor drains.

2.3 Building Modifications As described in Section 2.1, the ROLB was constructed as a multipurpose office and laboratory building. As such, modifications occurred throughout the 1960-1973 period. Some equipment was installed during original construction and other equipment was added in response to new or revised mission requirements. For example, a radiation detector/instrumentation calibration facility was added outside the northwest corner of the basement in the 1961 timeframe. Access to the calibration facility was provided through a passage from the radiation instrument repair room. Modifications to the ROLB were made to add analytical equipment to the second floor radiochemistry laboratories. Emergency showers and eye wash stations were installed (in 1963-64).

Other modifications were made to improve safety and efficiency of laboratory operations.

These included adding filter housings, cabinets, fume hoods and shielded glove boxes.

Research equipment was upgraded and new replacements installed (mass spectrometer, spectro-photometer, infrared analyzer, etc.) in the late 1960s. Some office areas were modified; primarily wall partition rearrangements during the operations phase to facilitate organizational changes. Room rearrangements in the electronics shops, health physics and radiochemistry laboratories areas were also made in this period.

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Plum Brook Reactor Facility FSSR Attachment 1, Rev. 0 2.4 Final Configuration and Scope Configuration of the ROLB for the FSS and the period until license termination is controlled by PBRF decommissioning and FSS procedures. The structure remains intact with utilities and services limited to temporary lighting. All furniture, furnishings and equipment have been removed. Most floor coverings, wall coverings and false ceilings have been removed.

Electrical conduit, drains, HVAC ducts, hood ventilation ducts and plumbing fixtures have been removed. All piping was drained and removed and all sumps deactivated, except for the north sump which is maintained to control groundwater intrusion. Exhibits 5 through 15 of Appendix A, show the condition and configuration of representative rooms and areas in the ROLB at the time of the final status survey.

The scope of FSS measurement results reported in this attachment includes building interior and exterior surfaces and the surface soil beneath the basement crawl space. It includes surface attachments, temporary safety covers and small embedded fixtures, for example pipe and conduit stubs such as shown in Exhibit 15 of Attachment A. It does not include FSS measurement results for piping embedded in ROLB concrete or buried beneath or adjacent to the building. The results for these commodities are reported in separate attachments to the FSS Report.

3.0 ROLB History and Operations with Radioactive Materials A chronology of ROLB milestones is given below. This is followed by a discussion of building operations, post-shutdown and decommissioning activities. Emphasis is on operations with 3

radioactive materials that could affect the final building condition and final status survey.

3.1 Chronology 1956 - September, groundbreaking for PBRF 1957 - ROLB construction initiated 4 1959 - Jan-Feb. Initial ROLB occupancy 1961 - June, 60 Mw Test Reactor critical 3 Information sources for the history and pre-decommissioning period include, construction photos, construction drawings, PBRF operating cycle reports, Radiochemistry periodic reports, PBRF Annual Reports, Unusual Occurrence Files, memoranda and other historical files maintained by PBRF Document Control.

4 Construction photos show that the ROLB was under construction in 1958. It is believed that construction began about one year after Reactor groundbreaking. One photo shows that the building was nearly complete except for window installation in November 1958 [PBRF 2009].

6

Plum Brook Reactor Facility FSSR Attachment 1, Rev. 0 1973- January 5 h, Reactor shutdown 1973 - June 30, ROLB vacated and placed in "standby condition". New Reactor Fuel and radioactive sources removed.

1984 - Major roof repair to prevent water in-leakage 1985 - Initial radiological characterization, Teledyne Isotopes Inc.

1989 - Follow-up radiological characterization, GTS-Duratek 2002 - Decommissioning Plan approved. Equipment and cabinets removed; initial building decontamination.

2003- 2005 - Temporary storage of contaminated equipment in ROLB during D&D of the PBRF.

2006- 2007 - Remediation of contaminated areas and preparation for FSS.

2008 - FSS measurements completed in ROLB interior.

2009 - Roof covering removed.

2009 - FSS measurements of ROLB roof and exterior walls completed.

3.2 Operations with Radioactive Materials The US Atomic Energy Commission (AEC) authorized operations and use of radioactive materials at the PBRF under several licenses. 5 License No.TR-3 (Docket 50-30) authorized the 60 MW test reactor. The 100 KW mock-up reactor was licensed under License No.R-93.

A broad byproduct license (BPL) No. 34-06706-03, authorized possession and use of radioactive materials (byproduct material) produced by the Plum Brook 60MW and Mockup reactors and other radioactive materials. This license also covered Hot Laboratory operations and related analytical activities in the radiochemistry laboratories. Special Nuclear Materials license SNM 605 covered the right to possess and irradiate limited quantities of source and special nuclear materials.

A wide variety of radioactive liquids, gases and solids were stored, handled in the ROLB and analyzed in the ROLB laboratories during the operations period. Typically, radioactive materials were transported from the Reactor Building, Containment Vessel, Hot Laboratory, Primary Pump House and other PBRF locations to the radiochemistry and metallurgy laboratories in the ROLB. Items such as primary reactor coolant samples, flux wires from the Plum Brook test reactor and the Mock-up reactor, PBRF reactor vessel material specimens, 5 Authority for the PBRF reactor and radioactive materials licenses was assumed by the US Nuclear Regulatory Commission in 1975.

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Plum Brook Reactor Facility FSSR Attachment 1, Rev. 0 small experiment specimens (such as irradiated space- related experiment samples, moon rocks, corn, coal, petroleum samples, etc.) were routinely carried in lead casks or other shielded containers for counting and analysis in the ROLB labs.

Controls for radioactive materials included inventory records of radioactive materials at the PBRF, including the ROLB. These recorded receipts, storage, transfer and disposition of individual sources. Radionuclides recorded. on inventory sheets included tritium, C-14, Na-22, P-32, Sc-46, Cr-51, Mn-54, Fe-55, Fe-59, Co-60, Ni-63, Zn-65, Kr-85, Sr-90, Ru-106, Cd-109, Ag-110m, Cd-i 15, Ba-133, Ce-144, Cs-137, Nd-147, Pm-147, Eu-152, Eu-154, Ta-182, W-185, Hg-203, TI-204, Po-210, mixed fission products, Radium, Uranium (natural, depleted and enriched), Am-Be neutron sources and Np-237. Most of the source inventory was disposed as radioactive waste during operations (1961-73) and during the transition to "mothball" status in 1973. The remainder Was transferred to other licensees, returned to the AEC, or stored on-site for potential future use.

During operations, activities within PBRF facilities involving radioactive materials were well documented in PBRF cycle reports, radiochemistry periodic and special reports, PBRF annual reports, and experiment results reports. These included activities involving the radiochemistry and metallurgical laboratories, counting rooms, etc. pertinent to the Test Reactor, the Mock-up Reactor, associated experimental programs and Hot Laboratory operations.

The PBRF Procedure, ADM-1402-6, Inventory and Control of Radioactive Materials, outlined the process for controlling radioactive materials, including sealed sources and other radioactive materials (on-site reactor generated), except nuclear fuel for the two PBRF reactors. On several occasions, incidents involving loss of control of radioactive materials in the ROLB were reported. These were recorded in Operations Cycle reports. Most of the reported events occurred in or near the 2 nd Floor radiochemistry laboratories. They included spills and airborne release of un-encapsulated radioactive material. Radionuclides involved in these reported events included tritium gas, Co-60, W-185 and Np-237.

3.3 Disposition of Materials in the Post-Shutdown Period Notification was received on January 5, 1973 that NASA was terminating all nuclear related operations at PBRF due to budget constraints. 6 The test reactor, mock-up reactor, hot laboratory and all associated operations were to be placed in standby condition by June 30, 1973. This included termination of the reactor facility operations staff.

Following notification, the test reactor (60 MW) was immediately shutdown on January 5 .

A Master Plan was developed to address the activities associated with terminating the operating licenses for PBRF and placing the facility in a standby status. End condition statements were developed. These specified the final conditions for all buildings, structures and equipment on the PBRF site as of June 30, 1973. Both the initial Master Plan and the End Condition Statements were subject to revision as activities progressed or conditions changed.

6 This section is adapted from the December 2009 memorandum to file prepared by J. L. Crooks and Don Young, PBRF retirees [PBRF 2009].

8

Plum Brook Reactor Facility FSSR Attachment 1, Rev. 0 The ROLB status was included in the plans and statements described above. These indicated that the majority of the equipment in the offices and some of the equipment and other items in the ROLB laboratories were removed. Equipment remaining in the laboratories included fume hoods, sinks, drains (hot and cold), etc. The roof openings for all laboratory hood vents were covered and sealed per Shutdown Procedure OSY-3301-S04. Services to the building were terminated with the exception of electricity and the operation of three sumps in the basement.

Sanitary systems and water were cut off, the heating system was secured, and laboratory hoods were tagged and the access doors cabled shut to prevent entry.

All source (i.e., natural uranium) and special nuclear material were to be removed from the facility (including the ROLB); except for calibration sources covered by general licenses per 10CFR70 and 10CFR40. Materials removed included fuel elements (new and spent, MTR-type 93 per cent enriched uranium aluminum alloy), fission chambers, plutonium-beryllium neutron sources for MUR startup and neutron calibration. Also removed were sealed and unsealed byproduct sources (such as a polonium-beryllium neutron source), Ce-144, Au-198, Cs- 137, Co-60 and others. The items for removal were identified and either disposed of as radioactive waste, transferred to other licensed facilities, returned to the AEC for credit or stored for calibration of radiation monitoring equipment. The latter were to be used for site and environmental monitoring during the protected safe storage mode. Some sources were also temporarily stored in safes in the ROLB for possible use while future test reactor or mock-up reactor restart was considered. Any known sources of contamination such as hot drain lines were tagged and labeled.

Following the final reactor shutdown in January 1973, the remaining new fuel was transferred to Oak Ridge National Laboratory (118 standard and 26 control rod fuel elements). A final inventory for the ROLB vault, dated May 1973, is available in the Shutdown Team records.

The disposition records for all sources and special nuclear materials located within the ROLB can be found, or referred, to in the Shutdown Team records and AEC Material Transfer Form 740 series records.

Beginning in mid-1973, activities at PBRF were controlled according to modified AEC/NRC possession only licenses TR-3, R-93 and BPL No. 34-060706-03. The by-product license No.

34-060706-03 was terminated in May, 1982. Licenses TR-3 and R-93 controlled and authorized possession only of the remaining radioactive materials on-site, i.e., no facility operations were permitted until decommissioning was authorized in 2002. During 1973 to 2002, selected equipment, materials, and waste (both low-level radioactive and non-radioactive) were removed to other locations or discarded as the projected long-term considerations for the facility changed from possible restart to standby to decommissioning.

For a brief history of the activities during this period see the NASA PBRF Decommissioning Plan, Section 1.2.1 Decommissioning Historical Overview [NASA 2007a].

Two radiological characterization efforts were conducted at PBRF during the post shutdown period prior to active decommissioning. A 1985 characterization survey performed by Teledyne Isotopes, Inc. covered the buildings and grounds at PBRF that were thought to be likely contaminated. The ROLB floors and inside wall surfaces at all elevations, including basements, were surveyed. In 1998, GTS Duratek conducted a confirmatory radiological survey on portions of PBRF to support planning for decommissioning and license termination activities. In this survey, only the easily detected radionuclides were analyzed in various 9

Plum Brook Reactor Facility FSSR Attachment 1, Rev. 0 material samples and quantified by gamma spectroscopy. A summary of the 1985 study indicated that removable surface alpha contamination in the ROLB ranged from 0 to 4 dpm/100-cm 2 . Removable surface beta-gamma contamination ranged from 0 to 137 dpm/100-cm 2 , and direct radiation levels averaged less than 0.02 mR/hr.

The 1998 confirmatory study generally confirmed the 1985 Teledyne results. In this survey 120 direct beta measurements were performed and 120 smears collected in the building.

However, additional contamination in four ROLB laboratories (Rooms 207, 209, 210 and 213A) was measured. Direct beta contamination levels of up to 68,000 dpm/100-cm2 were measured (the four highest measurements were: 6,100, 9300, 49,000 and 68,000 dpm/1 00-cmr2 ). All the remaining direct beta measurements were less than 2,000 dpm/100-cm 2). Of the removable surface alpha activity results, three of 120 measurements were > MDA (MDAs were 7 to 8 dpm/1 00-cm 2). The positive results were: 70, 118 and 162 dpm/100-cm2 . All beta removable surface activity measurements were < MDA (14 dpm/100-cm 2).

3.4 Decommissioning After NRC approval of the Decommissioning Plan in 2002, the ROLB was cleared of readily removable items such as desks, storage cabinets, and laboratory equipment (hoods, analytical equipment, etc.). Most piping, pumps and HVAC equipment were removed. This included waste disposal of radioactively contaminated items.

In addition to removal of bulk equipment and furnishings, D&D activities focused on decontamination of known contaminated areas identified in the initial decommissioning characterization surveys. Also, surface coverings and fixtures that could mask contamination or physically interfere with surface activity measurements were removed. This included floor tiles, ceiling acoustic tile and wall coverings. Hazardous materials and many building features, except structural components, have been removed from the building to facilitate the Final Status Survey. Recyclable items were segregated where possible.

Radiological surveys were performed throughout the decommissioning process. The objective of the final post-remediation survey was to ensure that the ROLB could satisfy the release criteria with a high probability of success. A summary of the areas in the ROLB where contamination was measured and remediated during D&D is provided in Table 2. These results do not include surveys of contaminated equipment or bulk contaminated items that were removed and disposed of as radioactive waste.

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Plum Brook Reactor Facility FSSR Attachment 1, Rev. 0 Table 2, Contaminated Areas Identified in ROLB Decommissioning Surveys Room No. or Contamination levels Radionuclides Results, Survey ID Location Measured Date (Month-Year)

New Fuel Vault Up to 36,000 dpm/100- Co-60, Cs-137 & U- MWH C 1141 206C1, cm 2 alpha 235(y spec. of smears) Oct-03, Remediated (2)

New Fuel Vault 9 of 24 alpha No sample analysis MWH C 1141 206C2, -

measurements > 200 reported Feb-04, Widespread dpm/1 00-cm 2 alpha contamination Remediated (2)

Basement level Up to 39,000 dpm/100- No sample analysis MWH C 1141 206C1, Men's room cm 2 beta reported Oct-03 Basement level Up to 34,000 dpm/100- No sample analysis SR-31 Oct-06, post Men's room cm 2 beta reported remediation survey, Remediated (2)

Second Floor E-W Up to 251,000 dpm/100- Co-60, Nb-94, Cs- 137, MWH C 1141 214C1, Hallway labs and cm 2 beta U-235 (Gamma spec. Sep-03 offices (1) of smears)

Second Floor E-W Up to 297,000 dpm/100- No sample analysis MWH C 1141 214C2, Hallway labs and cm 2 beta, Up to 4900 reported Nov-04, Remediated (2) offices (1) dpm/100-cm 2 alpha Room 210 Up to 9900 dpm/100-cm2 No sample analysis SR-31 Oct-06, post beta reported remediation survey, Remediated (2)

Southeast 6400 dpm/100-cm 2 (spot No sample analysis MWH C 1141 205C1, Stairwell on 3 rd step above Ist floor reported Oct-04, Remediated foyer)

Table 2 Notes:

1. Alpha and beta surface contamination was measured in Rooms 207, 209, 210, 211, 213A, 214 and 215.

2. Remediation goals varied somewhat through the decommissioning period, but were generally lowered to < 5500 dpm/100-cm 2 total surface beta activity and < 20 dpm/100-cm 2 total surface alpha activity during final post-remediation surveys.

4.0 Survey Design and Implementation for the ROLB This section describes the method for determination of the number of fixed measurements and samples for the FSS of the ROLB. Requirements of the FSS Plan applicable to the ROLB are summarized. These include the DCGLw7 , the gross activity DCGL that applies to the ROLB, scan survey coverage and action-investigation levels, classification of areas and breakdown of the ROLB survey units. The radiological instrumentation and their detection sensitivities are discussed.

7 The convention used in the MARSSIM is to identify the DCGL used as the benchmark for evaluating survey unit measurement results, as the DCGLw. The "W" subscript denotes "Wilcoxon", regardless of the particular test used (Wilcoxon Rank Sum Test, or Sign Test).

II

Plum Brook Reactor Facility FSSR Attachment 1, Rev. 0 4.1 FSS Plan Requirements The DCGLs for individual radionuclides were obtained for PBRF structures considering exposure to future site occupants from two potential pathways. Single radionuclide DCGLs were calculated using RESRAD-BUILD Version 3.22 for a building reuse scenario. Single radionuclide volumetric DCGLs were calculated for subsurface structures using RESRAD Version 6.21 for a resident farmer scenario. 8 The volumetric DCGLs (in pCi/g) were converted to "effective surface" DCGLs (in dpm/100-cm 2) using surface-to-volume ratios for the assumed volume of contaminated subsurface concrete. The DCGL calculations are described in the FSSP, Attachment B. To obtain the DCGLs for PBRF structures, the smaller of the two DCGLs calculated for each of the radionuclides of concern were selected.

For structural surfaces in the PBRF, where multiple radionuclides are potentially present in residual contamination, the DCGL for FSS design and implementation is a gross activity DCGL. The gross activity DCGL accounts for the presence of multiple radionuclides, including beta-gamma and alpha emitters. The gross activity DCGL can also include so-called hard-to-detect (HTD) radionuclides. The latter are not detected, or detected with very low efficiency, by the beta detectors selected for the FSS of structures.

The gross activity DCGL for the ROLB is calculated using equations in the FSSP for gross beta, gross alpha and surrogate DCGLs, based on the radionuclide mixture in residual contamination. Activity fractions and gross activity DCGLs for the ROLB are shown in Table

3. The default DCGL for PBRF structures, 27,166 dpm/100-cm 2., is applied to the ROLB.

Table 3, ROLB Radionuclide Activity Fractions and Gross Activity DCGLs Radionuclides DCGLw Location H-3 Co- Sr- I- Cs- Eu- U- U- (dpm/100 60 90 129 137 154 234 235 cm2)

Activity Fractions Assigned to ROLB l New Fuel 0.3902 0.0076 0.0421 0.0287 0.1755 0 0.3438 0.0121 30,831 Vault (2)

All Other 0.2707 0.0965 0.0788 0.0142 0.4671 0.0012 0.0698 0.0017 27,166 Rooms Table 3 Notes:

1. Activity profiles and gross activity DCGLs for structures are reported in the Technical Basis Document PBRF-TBD-07-001 [PBRF 2007]. Only a small fraction of characterization smear and material samples from the ROLB showed detectable activity. Thus, the ROLB was assigned the default radionuclide mixture using fractions obtained as the averages of the radionuclide activity fractions in 18 characterization samples.

2. For conservatism, the default DCGL, 27,166 dpmr/100-cm 2, was used in the survey design for the New Fuel Vault.

8 Potential exposure to future occupants from subsurface structures could occur from contaminated concrete rubble placed as fill and from contaminated intact structures such as the below-grade portion of the Reactor Bioshield 12

Plum Brook Reactor Facility FSSR Attachment 1, Rev. 0 Survey designs must incorporate requirements for scan coverage and investigation levels derived from the MARSSIM classification of survey units. The values applicable to the ROLB are shown in Table 4.

Table 4, Class-Based Survey Scan Coverage and Action Level Requirements Static Measurement Classification Scan Survey Scan Investigation or Sample Result Coverage Levels Investigation Levels Class 1 100% >DCGLEMC >DCGLEMC Class 2 10 to 100% >DCGLw or >MDCscan if MDCscan is >DCGLw Class 3 Minimum of 10% >DCGLw or >MDCCan >50% of the DCGLw if MDCscan is >DCGLw - _ _

4.2 Area Classification and Survey Unit Breakdown The ROLB was divided into 87 areas for division into potential survey units and assigned initial MARSSIM classifications in the FSS Plan. This breakdown is shown in Table 2-1 of the FSS Plan. As part of the FSS implementation process, individual survey units are identified and their final MARSSIM classification established. The ROLB was divided into 60 survey units for the FSS. The 60 survey units comprise 59 structure survey units and one surface soil survey unit. Table 5 lists the individual survey units and their classification for the FSS. The table compares final classification of the survey units with FSS Plan Table 2-1 classifications. Table 5 was reviewed to ensure that no areas were classified "downward" from classifications assigned in the FSS Plan. Table 6 summarizes the survey unit breakdown by major elevation. Table 7 shows the survey unit breakdown by MARSSIM classification. 9 Table 5, ROLB Survey Units for FSS Survey Unit Description FSSP Classification (1) Class (Rm=Room; Fl=Floor; Lw=Lower wall; (2)(3)

Uw=Upper wall; Wl=Window ledges)

RO-1-1 I Rm 117/118-F1 1 RO-1-2 I Rm 117/118- Lw, W1 1 RO-1-3 I Rms119/120 - FI 1 RO-1-4 1 Rm l19/120-Lw, WI I RO-1-5 2 Rm 109 - III FI, Lw, WI, Rmll2 - 116 Fl, Lw, Uw, 2 WI. Rm l17-120Uw RO-1-6 2 Rm 121 - 126 Fl, Lw, WI, Restrooms, Closets, Phone 2 Booth Fl, Lw, Uw RO-1-7 2 N.E. Stairwell Fl, Lw, Uw, Ceiling S.E. Stairwell Fl, 2 Lw, Uw, Ceiling RO-I-8 2 East/West Hallway Fl, Lw, Uw 2 9 The calculations performed in preparation of this report are documented in a memorandum to the PBRF Decommissioning Project File [PBRF 2010].

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Plum Brook Reactor Facility FSSR Attachment 1, Rev. 0 Table 5, ROLB Survey Units for FSS Survey Unit Description FSSP Classification (1) Class (Rm=Room; Fl=Floor; Lw=Lower wall; (2)(3)

Uw=Upper wall; Wl=Window ledges)

RO-1-9 2 Rm 112-120, restrooms, closet, pipe chase, E.-W. 2 Hallway Ceiling RO-1-10 3 North/South Hallway Fl, Lw, Uw 3 RO-1-11 3 Lobby, Rml00-108 Fl, Lw, Uw, W1, Rm109-111, Rm 3 121-126 Uw RO-1-12 3 Lobby, Rml00-111, Rm 121-126, North/South 3 Hallway Ceiling RO-2-1 1 Room 207/207A/EW Hall Fl 1 RO-2-2 I Room 209-210 Fl 1 RO-2-3 I Room 211/212 F1 1 RO-2-4 I Room 213/213A Fl I RO-2-5 (4) 1 Room 214/215/NS Hall Fl Rms 215/215 = 1, NS Hall =3 RO-2-6 (4) 1 EW Hall FI 2 RO-2-7 (4) 1 Laboratory Area Columns NC RO-2-8 I Wall Section 1 - Room 207/207A Walls Lw, Uw, WI 1 Wall Section 2 - Room 207/207A/209/210/EW Hall Lw, Uw, WI RO-2-10 1 Wall Section 3 - Rooms 211-213/213A N Wall Lw, 1 Uw, WI RO-2-11 Wall Section 4 - Rooms 213A/214/215 West Wall Lw, 1 Uw, WI RO-2-12 (4) 1 Wall Section 5 - Room 215, NS Hall walls Lw, Uw Rm 215 1, NS Hallway = 3 RO-2-13 I Room 207/207A/East-West Hall Ceiling 1 RO-2-14 1 Room 209-210 Ceiling 1 RO-2-15 I Room 211/212 Ceiling 1 RO-2-16 I Room 213/213A Ceiling 1 RO-2-17 I Room 214/215/NS Hall Ceiling I RO-2-18 1 EW Hall Ceiling I RO-2-19 2 Class 2 areas Fl, Lw, Uw, WI, Ceiling 2 RO-2-20 3 Class 3 areas Fl, Lw, Uw, WI 3 RO-2-21 3 Class 3 areas Ceiling 3 RO-2-22 1 Class I Ceiling Beams Ceiling 1 RO-2-23 1 Class I Ceiling Beams Ceiling I RO-3-1 1 Area Way Fl I RO-3-2 1 Vestibule, Men's Room, Janitor Closet. Cold Test Area (west) Fl RO-3-3 1 Cold Test Area (center) Fl I RO-3-4 1 Cold Test Area (east) and Vault Fl I RO-3-5 1 Sump Room, Sumps, Elevator Sump Fl RO-3-6 1 Sump Room, Men's Room, Janitor Lw 1 RO-3-7 I Area Way and Vault Lw 1 RO-3-8 1 Cold Test Area and Vestibule Lw I RO-3-9 I Sump Room Ceiling 1 RO-3-10 I Sump Room Uw and Vestibule, Men's Room, Janitor 1 Ceiling RO-3-11 I Men's Room, Janitor, and Vault Uw and Vault Ceiling 1 RO-3-12 I Vestibule Uw and Area Way Ceiling 1 RO-3-13 1 Area Way Uw 1 RO-3-14 1 Cold Test Area and Columns Uw I RO-3-15 1 Cold Test Area (North) Ceiling I RO-3-16 1 Cold Test Area (North Central) Ceiling I RO-3-17 I Cold Test Area (South Central) Ceiling I RO-3-18 1 Cold Test Area (South) Ceiling 1 14

Plum Brook Reactor Facility FSSR Attachment 1, Rev. 0 Table 5, ROLB Survey Units for FSS Survey Unit Description FSSP Classification Class (Rm=Room; Fl=Floor; Lw=Lower wall; (2)(3)

Uw=Upper wall; WI=Window ledges)

RO-3-2522 Class 2 Area Ceiling not including the elevator shaft RO-3-26 2 Class 2 Area Ceiling not including the elevator 2 shaft RO-3-27 2 Class 2 Area Ceiling not including the elevator 2 shaft RO-3-28A 3 Crawl Space 3 RO-3-28BW 3 Crawl Space Soil NC RO-4-1 2 Roof 2 RO-4-2 3 Exterior walls 3 Table 5 Notes:

1. Reduction of 87 areas identified in FSSP Table 2-1 to 60 survey units was achieved by combining multiple areas in the FSS Plan breakdown (classification-based size limits were maintained).

2. The FSS Plan classifications were based on area history and available characterization data.

3. NC means not classified, or not specifically identified in the FSS Plan Table 2-1.

4. Denotes a survey unit whose classification was changed from that listed in the FSSP Table 2-1 or one that was not specifically identified (and classified) in Table 2-1, Table 6, ROLB Survey Unit Breakdown by Major Elevation Major No. of Surface  % of  % of Surface Elevation or Survey Area Survey Area Area Units (Mi2 ) Units 1 st Floor 12 5295 20.0 32.2 2 nd Floor 23 3940 38.3 24.0 Basement (1) 23 4637 38.3 28.2 OW&R (2) 2 2558 3.3 15.6 Total 60 16430 100 100 Table 6 Notes:

1. The basement survey units include one survey unit that is not a structure. RO-3-28B Crawl Space (soil). The surface area of this survey unit, 348.4 m2, is included in the total surface area, 16430 M2 .

2. OW&R - outside walls and roof.

Table 7, ROLB Survey Unit Breakdown by MARSSIM Classification No. of Surface  % of Survey  % of Surface Average Area of Class Survey Units Area (M2 ) Units Area Survey Units (M2) 1 42 3061 70.0 18.6 72.9 2 10 6826 16.7 41.5 682.6 3 8 6543 13.3 39.8 817.9 Total 60 16430 100 100 1 15

Plum Brook Reactor Facility FSSR Attachment 1, Rev. 0 4.3 Number of Measurements and Samples The number of measurements and samples for each ROLB survey unit was determined using the MARSSIM statistical hypothesis testing framework as outlined in the FSS Plan. The Sign Test is selected because background count rates of instruments to be used are equivalent to a small fraction of the applicable DCGLw. 10 Decision error probabilities for the Sign Test are set at a = 0.05 (Type I error) and P3= 0.10 (Type II error) in accordance with the FSSP.

The Visual Sample Plan (VSP) software was used to determine the number of FSS measurements in the ROLB. 11 When the Sign Test is selected, the VSP software uses MARSSIM Equation 5-2 to calculate the number of measurements. Equation 5.2 is shown below:

l2(Zia + ZI~ )2 N

N =1.2 (Z- l, 2(Equation 1)

Where:

1.2 = adjustment factor to add 20% to the calculated number of samples, per a MARSSIM requirement to provide a margin for measurement sufficiency, N = Number of measurements or samples, a = the type I error probability,

the type II error probability, ZI- = proportion of standard normal distribution < 1 - a (1.6449 for a

0.05),

ZI-p = proportion of standard normal distribution < I - 03(1.2816 for 13= 0.1),

D (A/a) = value of cumulative standard normal distribution over the interval -

oo, A/a, A = the "relative shift", defined as the DCGL - the Lower Bound of the Gray Region (LGBR), and a = the standard deviation of residual contamination in the area to be surveyed (or a similar area). This may include the variation in measured "ambient" background plus the material background (for total surface beta measurements).

10 Background count rates for the LMI 44-116 detector, the instrument of choice for FSS surface beta activity measurements on structures, are in the range of 300 cpm or less for most materials. This is equivalent to about 2500 dpm/100-cm 2; less than 10% of PBRF structure DCGLs (this assumes a detection efficiency of- 12%).

" The FSS Plan (Section 5.2.4) states that a qualified software product, such as Visual Sample PlanC [PNL 20 10], may be used in the survey design process.

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Plum Brook Reactor Facility FSSR Attachment 1, Rev. 0 The MARSSIM module of VSP requires user inputs for the following parameters: a, f3, A, a and the DCGLw. The number of measurements, N, for the 60 ROLB survey units were calculated in 10 survey designs. Table 8 summarizes the ROLB survey design calculations and liststhe values of the key VSP input parameters.

Table 8, ROLB Survey Design Summary Design DCGL (2)(3)

Class LGBR (2) A (2) )(3 A/a N No.l 1) Survey Units (2)

RO-1-1 through RO-1-4 1 27,166 25,920 1,246 415 3.0 11 RO-1-5 through RO-2 1-9 2 27,166 25,920 1,246 415 3.0 11 RO-I-10through 3 27,166 25,920 1,246 415 3.0 11 RO-1-12 RO-2-1 through RO-4 2-18, RO-2-22 & 1 27,166 24,987 2,179 726 3.0 11 RO-2-23 5 RO-2-19 2 27,166 24,987 2,179 726 3.0 11 RO-2-20 & RO-2-21 6 3 27,166 24,987 2,179 726 3.0 11 RO-3-1 through RO-7 3-18 1 27,166 11,261 15,905 5,302 3.0 11 RO3-18 trog 8 RO-3-25 RO-3-27 through 2 27,166 11,261 15,905 5,302 3.0 11 RO-3-28A &RO 9 28B 3 27,166 11,261 15,905 5,302 3.0 11 9 RO-3-28B (soil) (4) 3 388 312 76 25 3.0 11 34 RO-4-1 & RO-4-2 2,3 24,449 12,225 12,224 4,890 2.5 11 Table 8 Notes:

1. The data reported in Table 8 is taken from the Survey Design reports listed. They are maintained in the PBRF Document Control System.

2. Units are dpm/100-cm 2 , except in Survey Design No. 9, where the units are cpm.

3. Estimates of o are obtained from ROLB post-remediation and variability survey (SR-31) and MWH characterization survey material background study (G9000 401 B 1) measurements collected with LMI 44-116 beta detectors.

4. Survey design inputs for the ROLB Crawl Space soil survey unit (Design No.9) were derived from DCGLs expressed as soil activity concentrations in pCi/g. The gross activity soil DCGL was calculated to be 11.7 pCi/g. This considers the DCGLs for Cs-I 37, Sr-90 and Co-60, with Cs-I 37 used as the surrogate for Sr-90. The equivalent DCGL in net cpm for the LMI 44-10 Nal detector was calculated to be 388 cpm and the standard deviation of Nal measurements was estimated to be 25 cpm.

5. In Survey Design No. 34, survey units RO-4-1 and RO-4-2 (building exterior surfaces), the DCGLw, 24,449 dpm!l 00-cm2, was obtained by adjusting the default value, 27,166 dpm/100-cm 2, by a factor of 10% (2.5/25) to account for deselected "insignificant" radionuclides.

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Plum Brook Reactor Facility FSSR Attachment 1, Rev. 0 Selection of design input parameters followed guidance in the FSS Plan. The Plan states that "the LGBR is initially set at 0.5 times the DCGLw, but may be adjusted to obtain a value for the relative shift (A/a) between I and 3." It is seen in Table 8, that in the majority of ROLB designs, a relative shift value of 3.0 was used in the final calculations for determining N.

The VSP software automatically performs an analysis to examine the sensitivity of N, the number of samples, to critical input parameter values. The following is an example obtained from the VSP report for survey unit RO-2-1 in Design No. 4. The sensitivity of N was explored by varying the following parameters: standard deviation, lower bound of gray region (as % of DCGL), beta, probability of mistakenly concluding that the survey unit mean concentration, p, is greater than the DCGL and alpha, probability of mistakenly concluding that the survey unit mean concentration, p, is less than the DCGL. Table 9 summarizes this analysis. The region of critical sensitivity is for a = 0.05 (required to be fixed), 3 = 0.10 (may be adjusted) and the LGBR set equal to 90% of the DCGL. In this region, N is only moderately sensitive to an increase of 100% in the value of a. In this case, N changes from 11 to 12. The sensitivity of N to an incorrect conclusion that the survey unit will pass (regulator's risk) is quite low; increasing a from 0.05 to 0.10 and 0.15 shows that the number of measurements is 11 or fewer in all cases except one. These results show that N = 11 represents a conservative design.

Table 9, VSP Sensitivity Analysis Results for Survey Unit RO-2-1 Design Number of Samples DCGL=27,166 c=0.05 x (2) a=0. 10 a=0.15

-_=1,452 a=726 a=1,452 o=726 o=1,452 a=726 LBGR=90% ( 4 P0.05 1) 13=)(4 16 14 12 11 11 10 P3=0.10 12 11 10 9 9 8 03=0.15 11 10 9 8 6 6 LBGR=80% 13=0.05 14 14 11 11 10 10 13=0.10 11 11 9 9 8 8 O3=0.15 10 10 8 8 6 6 LBGR=70% 13=0.05 14 14 11 11 10 10

[3=0.10 11 11 9 9 8 8 L3=0.15 10 10 8 8 6 6 Table 9 Notes:

1. Units of DCGL, a and LGBR are dpm/100-cm 2.

2. a = alpha, probability of mistakenly concluding that p < DCGL.

3. a = Standard Deviation.

4. LBGR = Lower Bound of Gray Region (as % of DCGL)

5. 03= beta, probability of mistakenly concluding that p > DCGL Visual Sample Plan was also used to determine the grid size, the random starting location coordinates (for Class I and 2 survey units) and to display the measurement locations on survey unit maps drawn to scale. Refer to Appendix B for location coordinate tables and scale VSP maps showing measurement locations for each ROLB survey unit.

The survey designs also specify scan survey coverage and action levels based on the MARSSIM classification listed in Table 4. If the scan sensitivity of the detectors used in Class I survey units is below the DCGLw, the number of measurements in each survey unit is 18

Plum Brook Reactor Facility FSSR Attachment 1, Rev. 0 determined solely by the Sign Test. If the scan sensitivity is not below the DCGLw, the number of measurements is increased as determined by the Elevated Measurement Test. As discussed in the next section, the scan sensitivities of instruments used in the FSS of the ROLB are below the DCGLw, and no increase in the number of measurements calculated using the Sign Test was required.

4.4 Instrumentation and Measurement Sensitivity Instruments to be used in the FSS of each survey unit are selected in each survey design.

Their detection sensitivities must be sufficient to meet the required action levels for the MARSSIM class of each survey unit. Minimum detection sensitivities for static alpha and beta measurements are calculated using the following equation:

• /'bts 3 +3.29 BRt,(1 +7 MDCstatic = , (Equation 2) t 1E1100 where:

MDCstatic = Minimum Detectable Concentration (dpm/100-cm 2),

BR = Background Count Rate (cpm),

tb = Background Count Time (min),

t, Sample Count Time (min),

A = Detector Open Area (cm 2) and Etot = Total Detection Efficiency (counts per disintegration). The total efficiency equals the product of Detector Efficiency, E, and Surface Efficiency, E,.

Scan sensitivities for detectors which measure alpha and beta surface activity are determined using the following equation:

d'b 60 MDCscan = 1 , (Equation 3)

EIES*-* A 100 Where:

MDC,,an = Minimum Detectable Concentration (dpm/1 00-cm 2),

d' = Index of sensitivity related to the detection decision error rate of the surveyor, from Table 6.5 of MARSSIM [USNRC 2000],

i = observation counting interval, detector width (cm) / scan speed (s),

bi = background counts per observation interval, Ej = Detector Efficiency (counts per disintegration),

Es = Surface Efficiency, typically 25% for alpha and 50% for beta (ISO 7503-1, Table 2 [ISO 1988],

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Plum Brook Reactor Facility FSSR Attachment 1, Rev. 0 p = Surveyor efficiency (typically 50%) and A Detector Open Area (cm 2 ).

In accordance with the FSS Plan, scan sensitivities of Nal detectors for surface scans of soil and outdoor areas may be obtained from Table 6.7 of the MARSSIM [USNRC 2000]. For conditions other than those covered in the MARSSIM table, a modified form of Equation 3 is used.

A summary of the a' priori detection sensitivities of instruments used in the FSS of the ROLB is provided in Table 10.

Table 10, Detection Sensitivities of Field Instruments Detector MDCscan Net cpm Detector Model Efficiency (dpm/1 00-cm 2) Equivalent to MDCstatic 2

(2)(3) MDCSCa, (dpm/100-cm )

LMI 44-116 (4)5() 0.12 2336 188 616 LMI 43-37(6 ) 0.145 798 352 NA LMI 44-10 (7) NA 3.47 388 NA Table 10 Notes:

1. The detector efficiencies listed are total efficiency, i. e., E, = Ej + E,.

2. A' priori scan sensitivities for the LMI 44-116 & LMI 43-37 detectors are calculated using Equation 3.

3. The scan MDC for Nal detector is in units of pCi/g (Cs-137). The instrument is set up using an energy window to count only gamma rays centered on the Cs-137 660 kev photopeak.

4. The static MDC for the LMI 44-116 detector is calculated using Equation 2 with background count rate = 236 cpm, Ej = 0.242 and E, = 0.5 (detector-to-surface distance = 0.5 in.)

5. The scan MDC for the LMI 44-116 is from Survey Design No.1, Aft. 5-2. The background count rate is 236 cpm; scan speed is 10 cm/s, Ej = 0.242, E, = 0.5, efficiency correction factor = 0.8349 to compensate for concrete roughness (detector-to-surface distance 0.5 in.)

6. The scan MDC for the LMI 43-37 is from Survey Design No.1, Aft. 5-3. The background count rate is 483 cpm; scan speed is 30 cm/s, Ej = 0.29, E, = 0.5, detector-to-surface distance 0.5 in.

7. The scan MDC for the LMI 44-10 is obtained from Survey Design No. 73, Aft. 5-4, with a background count rate of 130 cpm (Cs-137 window) and a scan speed of 25 cm/s.

20

Plum Brook Reactor Facility FSSR Attachment 1, Rev. 0 Modifications to survey instructions are adjusted to account for unusual measurement conditions. Modified detection sensitivities may be applied taking into account adjustments in detector efficiency. Scan speeds may be reduced to ensure that required scan sensitivities are achieved. The bases for adjustments due to non-standard conditions are provided in PBRF Technical Basis Documents.

special measurement 12 Examples of areas or locations in ROLB survey units where conditions apply are shown in Exhibits 14 and 15 of Appendix A.

5.0 ROLB Survey Results Results of the ROLB FSS are presented in this section. This includes scan survey frequencies (% of areas covered) for each survey unit and occurrence of events where scan investigation levels were exceeded. Investigations performed and the results are summarized. Fixed measurement results for each survey unit and the results of comparison tests of survey unit maximum and average values with the DCGLw are reported. As discussed below, no statistical tests were required. It is shown that levels of residual contamination have been reduced to levels that are ALARA. Soil activity concentrations are compared to EPA trigger levels in accordance with the 2002 Memorandum of Understanding between the NRC and EPA [USEPA 2002]. This section closes with a summary which concludes that applicable criteria for release of the ROLB for unrestricted use are satisfied and all FSS Plan requirements are met.

5.1 Surveys and Investigations Scan survey results were reviewed to confirm that the scan coverage requirement (as % of survey unit area) was satisfied for all survey units. The results of QC replicate surveys were also reviewed to confirm that the minimum coverage requirement of 5% was satisfied. Results of the ROLB scan surveys are compiled in Table 11. The table shows that scan coverage requirements were satisfied for all survey units. The table also shows that scan investigation levels were exceeded in two survey units (both Class 1). The results of the investigations are summarized below.

12 The PBRF-TBD-07-004 [PBRF 2007a] presents efficiency correction factors developed for the LMI 44-116 detector.

The correction factors are presented as a function of detector-to-surface distance. Application of the factors requires empirical measurements of the effective detector-to-surface distance for areas with non-standard surface conditions as part of the survey unit inspection process. The PBRF-TBD-09-002 [PBRF 2009a] calculates LMI 44-10, Nal detector scan MDC values for various survey conditions, including non-standard sized areas of elevated activity. The PBRF-TBD-09-006 [PBRF 2009b] evaluates the LMI 44-10 response when performing soil scans in water covered areas. It is shown that the effect of water covering the soil scan area can be compensated for by modifying the scan survey technique, primarily by decreasing the detector-to-surface distance.

21

Plum Brook Reactor Facility FSSR Attachment 1, Rev. 0 Table 11, Scan Survey Results Survey Scan Survey QC Replicate Investigation SUrvey Scas Seraey(%) Scan Coverage Level Exceeded Unit( Class Coverage (%) ( )2) (3)

RO-1-1 1 100 30 No RO-1-2 1 100 30 No RO-1-3 1 100 30 No RO-1-4 1 100 30 No RO-1-5 2 53 16 No RO- 1-6 2 56 6 No RO- 1-7 2 53 15 No RO-1-8 2 52 7 No RO- 1-9 2 51 9 No RO-1-10 3 26 13 No RO-1-11 3 14 7 No RO-1-12 3 11 8 No RO-2-1 1 100 21 No RO-2-2 1 100 21 Yes RO-2-3 1 100 21 No RO-2-4 1 100 21 No RO-2-5 1 100 21 No RO-2-6 1 100 21 No RO-2-7 1 100 7 No RO-2-8 1 100 7 No RO-2-9 1 100 7 No RO-2-10 1 100 7 No RO-2-11 1 100 7 No RO-2-12 1 100 7 No RO-2-13 1 100 6 No RO-2-14 1 100 6 No RO-2-15 1 100 6 No RO-2-16 1 100 6 No RO-2-17 1 100 6 No RO-2-18 1 100 6 No RO-2-19 2 51 8 No RO-2-20 3 12 12 No RO-2-21 3 12 18 No RO-2-22 1 100 6 No RO-2-23 1 100 6 No RO-3-1 1 100 10 No RO-3-2 1 100 10 No RO-3-3 1 100 10 No RO-3-4 1 100 10 No RO-3-5 1 100 10 No RO-3-6 1 100 6 No RO-3-7 1 100 6 No RO-3-8 1 100 6 No RO-3-9 1 100 6 No RO-3-10 1 100 6 No RO-3-11 1 100 6 No RO-3-12 1 100 6 No RO-3-13 1 100 6 No RO-3-14 1 100 6 Yes 22

Plum Brook Reactor Facility FSSR Attachment 1, Rev. 0 Table 11, Scan Survey Results Survey Scan Survey QC Replicate Investigation Unit) Class Coverage (1) Scan Coverage Level Exceeded

(%) (1)(2) (3)

RO-3-15 1 100 6 No RO-3-16 1 100 6 No RO-3-17 1 100 6 No RO-3-18 1 100 6 No RO-3-25 2 65 8 No RO-3-26 2 55 8 No RO-3-27 2 52 8 No RO-3-28A 3 13 7 No RO-3-28B 3 13 8 No RO-4-1 2 53 5 No RO-4-2 3 11 7 No Table 11 Notes:

1. Scan % coverage values are rounded to the nearest whole per cent. Values reported with the first decimal as 5, e. g., 5.5, are rounded downward.

2. The % scan coverage is given as the % of the area scanned in the initial survey.

3. Replicate QC scan results are reported for multiple survey units in many Survey Requests.

The QC scan percentages are reported as % of the scanned area of the survey units combined. So the same % coverage value is assigned to all of the survey units reported in a Survey Request..

Review of ROLB release records indicates that during the FSS of the ROLB, investigations were performed in two survey units. In survey unit RO-2-2, Rooms 209-2 10, Laboratory area floors, a class 1 survey unit, two localized areas were observed to have activity above background during the scan survey. The areas were bounded and investigations performed of each.

The first location, designated as IM- 1, was found to contain fixed activity with measured gross surface activity of 13,465 dpm/100-cm 2 . This is well below the DCGLw (27,166 dpm/100-cm 2), and no further action was required.

The second location investigated in RO-2-2, designated as IM-2, was found to consist of a small area of fixed activity < 2x2 cm in area. A static measurement with an LMI 44-116 detector recorded 54,477 dpm/1 00-cm 2 . The EMC test was performed by comparing this measurement to the a'priori DCGLEMC, 82,708 dpm/100-cm , established in the survey design for this survey unit. A core bore sample was collected that encompassed this small area of elevated activity. The core was cut into one-half inch slices, which were analyzed by gamma spectroscopy. Only the top slice showed measured activity concentrations above the MDA for Cs-137. The concentrations of two measurements (top surface and bottom surface facing the detector) were 616 and 387 pCi/g, respectively. Both slices were < MDA for Co-60 (1.7E-01 pCi/g). Scans of the bore hole and the floor in the vicinity after removal of the core indicated no activity above background. From this result and the success in passing the EMC test, it was concluded that no further action was required.

The release record for survey unit RO-3-14, Cold Test Area upper walls, a class 1 survey unit, also reported an investigation. A scan alarm was observed on the top of an upper wall surface.

23

Plum Brook Reactor Facility FSSR Attachment 1, Rev. 0 A small area, less than a detector area (125 cm 2), was defined and a direct measurement yielded 15,900 dpm/1 00-cm 2, well below the DCGLw. No further action was required.

As both of these survey units were class 1, no reclassification was required as a result of these investigations.

5.2 Fixed Measurements and Tests Results of the assessment of ROLB FSS total surface beta measurements are presented in Table 12 (individual measurements in each survey unit are reported in Appendix B). The table presents the number of measurements, maximum, average and standard deviation for each survey unit. Table 12 compares the maximum activity measured in each survey unit to the DCGLw. It is demonstrated that that all measured activity values are less than the DCGLw, thus all survey units meet the 25 mrem/y release criterion. The mean activity of each survey unit is also compared to the DCGLw, and as expected, are all less than the DCGLw. The average of 650 total surface beta measurements reported in the ROLB release records is: 503 2

+/- 408 dpm/100-cm (one standard deviation) [PBRF 2010]. 13 Removable surface activity measurements were also performed at each fixed activity measurement location and counted for gross alpha and gross beta activity. A review of the ROLB Release records was conducted to ensure that all smear counting results were less than 10% of the gross activity DCGL. The requirement for PBRF laboratory smear counting instruments is that the MDAs be < 10% of the applicable gross activity DCGL 14. Gross beta and gross alpha counts for all ROLB smears were less than MDA.

The survey unit, RO-3-28B, covered surface soil beneath the basement crawl space. This survey unit was designated as class 3. Eleven surface soil samples were collected and analyzed by gamma spectroscopy by the PBRF laboratory. The highest sample activity was 0.12 pCi/g Cs-137, slightly above the MDA; all other sample results were < MDA for all PBRF gamma emitting radionuclides. By considering PBRF soil radionuclide activity ratios, it is determined based on the Cs-137 results, that the Sr-90 DCGL (5.4 pCi/g) is also satisfied. 15 13 It is noted that in converting total surface activity measurements in cpm to dpm/100-cm 2, the detector background response from surface materials is not subtracted. As a result, the total surface activity measurement results are biased high.

14 Typical MIDAs for PBRF low background smear counting instruments are 14 dpm for alpha and 18 dpm for beta.

Smears cover 100 cm 2 , so these MDA values are equivalent to dpm/100-cm 2.

'5 The Sr-90 to Cs-137 activity ratio for soil reported in the FSS Plan is 0.09. Therefore the surrogate DCGL for Sr-90 based on using Cs-137 soil sample measurements is 11.8 pCi/g, obtained using Equation 2.

24

Plum Brook Reactor Facility FSSR Attachment 1, Rev. 0 Table 12, ROLB Total Surface Beta Activity Measurement Summary and Test Results Survey No. of Maximum Test Result: Average Standard Deito Test Result:

Avrg<

Deviation Average <

Unit ID Measurements (1) DCGLw <

Maximum (1)

(1) (2) DCGLw RO-1-1 11 913 Yes 599 136 Yes RO-1-2 11 354 Yes 65 182 Yes RO-1-3 11 890 Yes 634 257 Yes RO-1-4 11 409 Yes 145 182 Yes RO-1-5 11 693 Yes 225 282 Yes RO- 1-6 11 2500 Yes 1069 880 Yes RO-1-7 11 1159 Yes 252 367 Yes RO-1-8 11 1000 Yes 420 320 Yes RO- 1-9 11 1031 Yes 576 206 Yes RO-1-10 11 1960 Yes 425 545 Yes RO-1-1 1 11 1306 Yes 349 406 Yes RO-1-12 11 1000 Yes 516 207 Yes RO-2-1 11 640 Yes 411 231 Yes RO-2-2 11 1100 Yes 788 160 Yes RO-2-3 11 1021 Yes 778 151 Yes RO-2-4 11 728 Yes 295 339 Yes RO-2-5 11 824 Yes 568 298 Yes RO-2-6 11 812 Yes 603 235 Yes RO-2-7 .11 890 Yes 658 191 Yes RO-2-8 11 551 Yes 197 216 Yes RO-2-9 11 1537 Yes 138 497 Yes RO-2-10 11 335 Yes 167 139 Yes RO-2-11 11 293 Yes 125 128 Yes RO-2-12 11 535 Yes 124 213 Yes RO-2-13 11 642 Yes 489 96 Yes RO-2-14 11 1489 Yes 705 360 Yes RO-2-15 11 1679 Yes 847 514 Yes RO-2-16 11 1051 Yes 588 277 Yes RO-2-17 11 708 Yes 516 133 Yes RO-2-18 11 971 Yes 593 183 Yes RO-2-19 11 2204 Yes 523 769 Yes RO-2-20 11 697 Yes 292 335 Yes RO-2-21 11 908 Yes 680 230 Yes RO-2-22 11 839 Yes 550 188 Yes RO-2-23 11 584 Yes 419 123 Yes RO-3-1 11 1265 Yes 1015 138 Yes RO-3-2 11 985 Yes 568 348 Yes RO-3-3 12 1250 Yes 906 167 Yes RO-3-4 11 927 Yes 646 170 Yes RO-3-5 11 1045 Yes 795 211 Yes RO-3-6 11 1331 Yes 362 348 Yes RO-3-7 11 1375 Yes 779 339 Yes RO-3-8 11 694 Yes 293 198 Yes RO-3-9 11 659 Yes 470 139 Yes 25

Plum Brook Reactor Facility FSSR Attachment 1, Rev. 0 Table 12, ROLB Total Surface Beta Activity Measurement Summary and Test Results Test Result: tnad Ts eut Survey No. of Maximum Average Standard Test Result:

(1) Maximum < (1) Deviation Average <

Unit ID Measurements DCGLw (1)(2) DCGLw RO-3-10 11 597 Yes 283 166 Yes RO-3-11 11 1559 Yes 678 474 Yes RO-3-12 11 659 Yes 116 300 Yes RO-3-13 11 887 Yes 604 189 Yes RO-3-14 11 435 Yes 122 166 Yes RO-3-15 11 690 Yes 448 156 Yes RO-3-16 11 613 Yes 446 552 Yes RO-3-17 11 645 Yes 414 159 Yes RO-3-18 11 573 Yes 344 173 Yes RO-3-25 11 891 Yes 641 194 Yes RO-3-26 11 908 Yes 416 352 Yes RO-3-27 11 1099 Yes 602 271 Yes RO-3-28A 11 1140 Yes 676 237 Yes RO-4-1 11 1420 Yes 435 461 Yes RO-4-2 11 2440 Yes 1208 1077 Yes Table 12 Notes:

1. The units for: maximum, average and standard deviation are dpm/100-cm2 .

2. Standard deviations of the measurements in each survey unit are reported for comparison to the values used in the survey design (see Table 8). In all the ROLB structural survey units, values of o obtained from the FSS measurements are less (usually much less) than values used in the survey designs.

3. In the FSS design calculation for survey unit RO-3-3 developed using VSP, 12 fixed measurement locations were established. When "fitting" the calculated grid size onto the survey unit layout, extra measurement locations (grid nodes) are sometimes added.

5.3 ALARA Evaluation It is shown that residual contamination in the ROLB has been reduced to levels that are ALARA, using a method acceptable to the NRC. The NRC guidance on determining that residual contamination levels are ALARA includes the following:

"In light of the conservatism in the building surface and surface soil generic screening levels developed by the NRC, NRC staff presumes, absent information to the contrary, that licensees who remediate building surfaces or soil to the generic screening levels do not need to provide analyses to demonstrate that these screening levels are ALARA. In addition, if residual radioactivity cannot be detected, it may be presumed that it had been reduced to levels that are ALARA. Therefore the licensee may not 16 need to conduct an explicit analysis to meet the ALARA requirement."

Screening level values published by the NRC for the mix of radionuclides in structural surface residual contamination potentially present in the ROLB are shown in Table 13. Since 16 This guidance was initially published in Draft Regulatory Guide DG-4006, but has been reissued in NUREG-1757 Volume 2, Appendix N.

26

Plum Brook Reactor Facility FSSR Attachment 1, Rev. 0 individual radionuclide activity concentrations are not measured in the FSS of structures, a direct comparison of residual contamination levels to screening level values is not possible. A comparison can be made by converting the nuclide-specific screening level values to an appropriate gross activity DCGL. This is accomplished using activity fractions used in development of the ROLB gross activity DCGL. A screening level value that is equivalent to the gross activity DCGL was calculated using the equations in Section 3.6 of the FSS Plan

[PBRF 2010]. The activity fractions listed in Table 3 (also shown in Table 13) were used in the calculation. The screening level equivalent DCGL for the ROLB is 1,188 dpm/100-cm2 .

As reported in Section 5.2, the average total surface beta activity measured in the FSS of the ROLB is 503 +/- 408 dpm/100-cm 2 (one standard deviation). The upper limit of 9 5 th%

confidence interval of this mean value is 534.4 dpm/100-cm 2 .17 This value is well below the screening level gross activity DCGL of 1,188 dpm/100-cm 2 .

Applicable NRC surface soil screening values are: Co-60, 3.8; Sr-90, 1.7 and Cs-137, 11 (all in pCi/g). The single ROLB soil sample result that was > MDA was 0.12 pCi/g, Cs-137. Since Cs-137 is the surrogate for Sr-90 and the Sr-90: Cs-137 activity ratio is only 0.09, the activity concentration of Sr-90 is also well below the screening level. Thus all soil sample results are below their respective screening level values. From these comparisons, it is concluded that the ALARA criterion is satisfied.

Table 13, Screening Level Values for ROLB and Radionuclide Activity Fractions Screening Level Value ROLB Activity Radionuclide (dpm/ 00-cm 2) Fraction %

H-3 1.2 E+08 27 Co-60 7.1E+03 (1) 9.7 Sr-90 8.7E+03 (1) 7.9 1-129 3.5E+04(') 1.4 Cs-137 2.8E+04 (1) 46.7 Eu-154 1.2E+04(2) 0.1 U-234 9.1E+01 (2) 7.0 U-235 9.8E+0112 1 0.2 Table 13 Notes.

1. Values from NUREG-1757 Vol. 2, Table H.1 [USNRC 2006].

2. Values from NUREG/CR-5512, Vol. 3, Table 5.19 [SNL 1999]. These are 90th percentile values of residual surface activity corresponding to 25 mrem/y to a future building occupant.

17 Theupper limit of the confidence interval, 9 5 th percentile value, is calculated as: UL = mean + 1.96 /hn,where n =

650 measurements.

27

Plum Brook Reactor Facility FSSR Attachment 1, Rev. 0 5.4 Comparison with EPA Trigger Levels The PBRF license termination process includes a review of residual contamination levels in groundwater and soil, as applicable, in accordance with the October 2002 Memorandum of Understanding (MOU) between the US NRC and the US Environmental Protection Agency (EPA) [USEPA 2002]. Concentrations of individual radionuclides, identified as "trigger levels" for further review and consultation between the agencies, are published in the MOU.

The trigger levels applicable to the PBRF for residual soil concentrations of the radionuclides of concern are:

" Co-60, 4 pCi/g,

" Sr-90 (plus daughter activity), 23 pCi/g and

• Cs-137 (plus daughter activity), 6 pCi/g.

For the ROLB soil survey unit, RO-3-28B, only one sample showed positive results (>MDA; the MDA is < 10% of the DCGL). That result was 0.12 pCi/g, Cs-137. This value is well below the EPA trigger level of 6 pCi/g. Since Cs-137 is the surrogate for Sr-90 and the Sr-90:

Cs-137 activity ratio is only 0.09, the activity concentration of Sr-90 is also well below the trigger level.

5.5 Conclusions The results presented above demonstrate that the ROLB satisfies all FSS Plan commitments and meets the release criteria in I OCFR20 Subpart E. The principal conclusions are:

• Scan surveys were performed in all 60 ROLB survey units with scan coverage in excess of the percentage requirements for all three classes of survey units.

" Residual surface contamination above investigation levels was detected in only two of 60 survey units. A small area of elevated activity above the DCGLw was measured in one survey unit. The EMC test was conducted and was satisfied.

• All total surface activity measurements are less than the applicable DCGLw, 27,166 dpm/1 00-cm 2 , except in one survey unit as noted above.

" All soil sample radionuclide activity concentrations in the single soil survey unit are below their respective DCGLw values.

" All survey unit mean fixed measurement results (total surface beta activity) are below the DCGLw, hence no statistical tests were required.

• All removable surface activity measurements are less than 10% of the DCGLw.

• Residual surface activity and soil concentration measurement results are shown to be less than NRC screening level values - demonstrating that the ALARA criterion is satisfied.

• Residual activity concentrations measured in the soil survey unit were compared to, and found to be less than EPA trigger levels.

28

Plum Brook Reactor Facility FSSR Attachment 1, Rev. 0 0 Only minor changes from what was proposed in the FSS Plan were made - the classification of three survey units was increased above what was proposed in the Plan.

• There were no changes from initial assumptions (in the FSS Plan) regarding the extent of residual activity in the ROLB. Only one measurement in excess of the DCGL occurred (in a class I survey unit) and no reclassification of survey units was required as a result of FSS measurements and investigations.

6.0 References ISO 1988 International Organization for Standardization, Evaluation of Surface Contamination,Part1: Beta Emitters andAlpha Emitters, ISO-7503-1, 1988.

NASA 2006 NASA Safety and Mission Assurance Directorate, Plum Brook Reactor Facility, DecommissioningProject QualityAssurance Plan, QA-0 1, Revision 2, February 2006.

NASA 2007 NASA Safety and Mission Assurance Directorate, FinalStatus Survey Planfor the Plum Brook Reactor Facility,Revision 1, February 2007.

NASA 2007a NASA Safety and Mission Assurance Directorate, DecommissioningPlanfor the Plum Brook Reactor Facility, Revision 6, July 2007.

PBRF 2007 Plum Brook Reactor Facility Technical Basis Document, Adjusted Gross DCGLsfor StructuralSurfaces, PBRF-TBD-07-001, June 2007.

PBRF 2007a Plum Brook Reactor Facility Technical Basis Document, Efficiency Correction Factor,PBRF-TBD-07-004, November 2007.

PBRF 2009 Plum Brook Reactor Facility, Memorandum to Project File, J. L. Crooks, Don Young, FSS FinalReport Background Information- ROLB, Reactor Office and LaboratoryBuilding (1141), December 2, 2009.

PBRF 2009a Plum Brook Reactor Facility Technical Basis Document, 44-10 Detector MDCscan Values for Various Survey Conditions, PBRF-TBD-09-002, June 2009.

PBRF 2009b Plum Brook Reactor Facility Technical Basis Document, An Evaluation of the 2350-1/44-10 NaI Detector Response in Water CoveredAreas, PBRF-TBD-09-006, October 2009.

PBRF 2010 Plum Brook Reactor Facility Decommissioning Project Office, Memorandum to Project File, EngineeringRecordfor FinalStatus Survey Report, Attachment 1 Calculations.March 24, 2010.

USNRC 2000 US Nuclear Regulatory Commission, Multi-Agency RadiationSurvey and Site Investigation Manual (MARSSIM), NUREG-1575, Rev.1, August 2000.

29

Plum Brook Reactor Facility FSSR Attachment 1, Rev. 0 USNRC 2006 US Nuclear Regulatory Commission, ConsolidatedDecommissioningGuidance, Characterization,Survey and Determinationof RadiologicalCriteria,NUREG 1757, Vol. 2, Rev.1, September 2006.

PNL 2010 Battelle Pacific Northwest Laboratories (PNL), Visual sample Plan, Version 5.9, 2010.

SNL 1999 Sandia National Laboratories (SNL), for US Nuclear Regulatory Commission, Residual Radioactive ContaminationFrom Decommissioning,ParameterAnalysis, NUREG/CR-5512, Vol.3, Oct. 1999.

USEPA 2002 Memorandum of Understanding, US Environmental Protection Agency and US Nuclear Regulatory Commission, Consultationand Finality on Decommissioning and Decontaminationof ContaminatedSites, October 9, 2002.

7.0 Appendices Appendix A - Exhibits Appendix B - Survey Unit Maps and Tables Showing Measurement Locations and Results 30

Final Status Survey Report Attachment 1 Reactor Office and Laboratory Building (Building 1141)

Revision 0 Appendix A Exhibits

Plum Brook Reactor Facility FSSR, Attachment I Appendix A, Rev. 0, Page 2 of 17 List of Exhibits Exhibit 1, View of PBRF Showing ROLB and Reactor Building ............................. 3 Exhibit 2, Reactor Office and laboratory Building First Floor Survey Units .................................. 4 Exhibit 3, Reactor Office and Laboratory Building Second Floor Survey Units .......................... 5 Exhibit 4, Reactor Office and Laboratory Building Basement Survey Units .................................. 6 Exhibit 5, Room 117-118 Electronics Lab (SU RO-I-1, Class 1) ................................................. 7 Exhibit 6, Room 116 Floor and Lower Wall Showing Penetrations (RO-1-5, Class 2) ................. 8 Exhibit 7, Room 109 Floor and Lower Wall (RO-1-1 1, Class 3) ................................................... 9 Exhibit 8, Room 209-210 Laboratory Floor Showing Remediated Area & Penetration (RO-2-2, C la ss 1)................................................................................................................................................ 10 Exhibit 9, Rooms 213A-215, Laboratory Area (RO-2-1 1, Class 1) ...................... 1 11....

Exhibit 10, Sump Room North Wall Showing Penetrations (RO-3-10, Class 1) ........................ 12 Exhibit 11, New Fuel Vault Floor and Lower Walls (RO-3-4, Class 1) ................... 13 Exhibit 12, Basement Men's Room Showing Extensive Remediation (RO-3-6, Class 1) ............ 14 Exhibit 13, Basement Crawl Space Showing Poured Concrete Ceiling (RO-328A, Class3) ........ 15 Exhibit 14, Room 21 3A West Wall Showing Example of a Surface Measurement Test Area (SM T A ) .............................................................................................................................................. 16 Exhibit 15, Sump Room Showing Example of Unusual Condition Measurement (UCM) Area ...... 17

Plum Brook Reactor Facility FSSR, Attachment 1 Appendix A, Rev. 0, Page 3 of 17 Exhibit 1, View of PBRF Showing ROLB and Reactor Building 7-4

Plum Brook Reactor Facility FSSR, Attachment 1 Appendix A, Rev. 0, Page 4 of 17 Exhibit 2, Reactor Office and laboratory Building First Floor Survey Units ELECTRONICS ELECTRONICS ................

LABORATORY LABORATORY 119 & 120 117 & 110

[" 1 FLOORS AND LOWER WALLS Description yS (Rm.-Roomc Fn-Floor. Lw-"Lower wal P___ __w-Upper wall. WI-Window ledge s)

RO-I-I I Rm 11118 - n 1¢t1 I V-m I I "Ptl 12 - T- I.w l Kmu 109 -111 FI, Lw, WI. RUini - 116 FL Lw. Uw, WL Rmini--120Uw Rm 121 - 16 Fl. Lw, %1, Resrooms. (losets. Phime Booth FlI.w.Uw N.. stairwel Fl. Lw. Uw. Ceilif S.E. Stirwell Fl.

Lw. Uw. Cdeflif Rm 112-120. reatroons. coset. pipe chase.EX.-W.

Hallway Cell" Lobby. Rin][904108 JFL Lw. IUW.WL RadO9.I11. Ran 121-126 tUw Lobby. Rml00. 11 RKm 121.126. Noith/Sath Hallway coviial

Plum Brook Reactor Facility FSSR, Attachment I Appendix A, Rev. 0, Page 5 of 17 Exhibit 3, Reactor Office and Laboratory Building Second Floor Survey Units LABORATORY LABORATORY LABORATORY 213A 213 212 LABORATORY LABORATORY LABORATORY 211 210 209 I SECOND FLOOR OMEN ANA a 0 a a a OFFICE 214 EASTA-EST HALLWAY FIRE EXTINGUISHER--A.

2 Ii CUBBY HOLE2 215 OFFICE F  !

207 C(XmTj" 4

[ I CLAS 12 1 CLASS 2 FLOORS AND

- CLASS 3 C LOWER WALLS SM*Vv.%'Dextipile Unt Clams (RKAwioet II=Rocr Lwci'arundl RO-21-1 I_ Roxxi M712M.AEWV Ml R R0,12-2 I_ Rixun 3D9-210 R RO-2-3 II Rmon 211V212 M RD I_ Room 213/1W3A H R0-12-5 1_ Room 21-0215ML THW M!

RO0-2-6 I EWHallHF M

RO-2-7 1 LabotAcy -AreaCdiirns RO-?-g %VaiI Sectaic I -RWoni 207;:07A WaMlls Lw. M~.

RO'9 Wall Sectio 2 -Rom&i2 207,207V2I20VEW1 Hil

___Lw. 11w.,NM RO-32-I0 I Wall Sectiai 3 -Rou; 211-213,211A NWH 1w.

II RO-1 I Wall.3ccticu4 -Rocrnw 213.V214215WAUIi Lw.

RO-3414I R0,1~12 I Wall Sectig15 -Rcxxu215j 8blwa&LkwV[w RO-213 I IRomn3D'37WAEV HilCdIiu RO,114 I Romn -109-210CWbig RO.3.15 I_ Romn 1/.-12 C'~ft RO-2dr 6 1_ Rmcn 213/213A Cdbn RO-3-I' I RMoo214/a5M HMilCdbig RO-2-18 I MWtfflCedft RO-2-19 2 C1m 2 a ea Lw UW,^ Cdbw RO-3-20 3 Cho 3 arem LwImUwmN RO.2.21 3 Clam3wewmCd~hq RO-.122 1_ CLam I 0*WnBeaiu (~ng RO.,-23 1 Clam I Ceikiag Nw ('h~ug

Plum Brook Reactor Facility FSSR, Attachment I Appendix A, Rev. 0, Page 6 of 17 Exhibit 4, Reactor Office and Laboratory Building Basement Survey Units

ý-I VAULT 17 COLDTESTAREA MENS 4 VESTIKUI M L l CLASS I AREAWAY LOORS ANo

-CLASS SCLASS FLS

~' ) 2 1 3

LOWER WALLS SUI Surveym4.om Descriptinn lais Unit (Ilos~f Woor. Lw"'Loer wal.

JI;

____ UwmUp~ewal;AI. ThWiaowltedg)

RO-3-1 I Area WayF1 RO-32 1 Vesibulelden's Roan, Janitor Goset. CoddTest Arma R0-3-3 1 Cod Test Arm (canted F1 RO-3-4 I ColdTert Area(e#)asnd Vmh F1 I

RO-3-5 1 Sumnp Room. Sumps.Elevator Sur*Fl RO-3-6_ 1 Sunip Roonm Men ý Roan, Juantor Lw RO-3-7 1 Arma Way and VaultLaw RO-3-8 I _ColdTert Arma m~dVes~bul Lw RO-3-9 I Sum Room ceii.

RO-3-10O Sump Room 11w and Veuabile, )&ns Room. Janitor RO..3-11 1 Men's Roan. Imtatr. and Vua 11w and Vault Cadat RO-3-12 1 Vesktaale Uw and Area Way C.4iiu ROI-3-13 1 Area Way Uw RO-3-14 1 odd Tst Area dColamns 11 R 15 1 ColdTest Area Norlh) Caiin RO-3-16 I Cold Test Area (North Central) CuTm RO-3-12_ 1 _ d esArea (Southa d C

• O3-1 1_ ColdTest Aea(South) CM16 RO--2 2 ass2Ar eaznot IndtM knathe dewtorsbMft RO32 _ as2r - notcudnd t te derstarsbt I-R0_3-V 2 Area Oedlan not wduchux the dew" ah~

IROTZ3- 1 33 1 rw Spae O32B13-

- 1 awl *wce SodL

Plum Brook Reactor Facility FSSR, Attachment 1 Appendix A, Rev. 0, Page 7 of 17 Exhibit 5, Room 117-118 Electronics Lab (SU RO-1-1, Class 1)

Plum Brook Reactor Facility FSSR, Attachment I Appendix A, Rev. 0, Page 8 of 17 Exhibit 6, Room 116 Floor and Lower Wall Showing Penetrations (RO-1-5, Class 2)

Plum Brook Reactor Facility FSSR, Attachment 1 Appendix A, Rev. 0, Page 9 of 17 Exhibit 7, Room 109 Floor and Lower Wall (RO-1-11, Class 3)

Plum Brook Reactor Facility FSSR, Attachment I Appendix A, Rev. 0, Page 10 of 17 Exhibit 8, Room 209-210 Laboratory Floor Showing Remediated Area & Penetration (RO-2-2, Class 1)

Plum Brook Reactor Facility FSSR, Attachment I Appendix A, Rev. 0, Page 11 of 17 Exhibit 9, Rooms 213A-215, Laboratory Area (RO-2-11, Class 1)

Plum Brook Reactor Facility FSSR, Attachment 1 Appendix A, Rev. 0, Page 12 of 17 Exhibit 10, Sump Room North Wall Showing Penetrations (RO-3-10, Class 1)

Plum Brook Reactor Facility FSSR, Attachment 1 Appendix A, Rev. 0, Page 13 of 17 Exhibit 11, New Fuel Vault Floor and Lower Walls (RO-3-4, Class 1)

Plum Brook Reactor Facility FSSR, Attachment 1 Appendix A, Rev. 0, Page 14 of 17 Exhibit 12, Basement Men's Room Showing Extensive Remediation (RO-3-6, Class 1)

Plum Brook Reactor Facility FSSR, Attachment I Appendix A, Rev. 0, Page 15 of 17 Exhibit 13, Basement Crawl Space Showing Poured Concrete Ceiling (RO-328A, Class3)

Plum Brook Reactor Facility FSSR, Attachment I Appendix A, Rev. 0, Page 16 of 17 Exhibit 14, Room 213A West Wall Showing Example of a Surface Measurement Test Area (SMTA)

Plum Brook Reactor Facility FSSR, Attachment I Appendix A, Rev. 0, Page 17 of 17 Exhibit 15, Sump Room Showing Example of Unusual Condition Measurement (UCM) Area

Plum Brook Reactor Facility Final Status Survey Report Attachment 1 Reactor Office and Laboratory Building (Building 1141)

Revision 0 Appendix B Survey Unit Maps and Tables Showing Measurement Locations and Results

Plum Brook Reactor Facility FSSR, Attachment 1 Appendix B Rev. 0, Page 2 of 72, Index of ROLB Survey Unit Maps and Tables of Coordinates Description Survey Unit (Rm=Room; FI=Floor;Lw=Lower wall; Uw=Upper wall; Wl=Window Page Number ledges) Number of Pages RO-1-1 Rm 117/118 - Fl 4 1 RO-1-2 Rm 117/118- Lw, W1 5 1 RO- 1-3 Rms 119/120 - Fl 6 1 RO-1-4 Rm 119/120 - Lw, W1 7 1 RO-1-5 Rm 109 - 111 FI, Lw, W1. Rm112 - 116 F1, Lw, Uw, WI. Rm 117-120 Uw 8 1 RO-1-6 Rm 121 - 126 Fl, Lw, WI, Restrooms, Closets, Phone Booth Fl, Lw, Uw 9 1 RO-1-7 N.E. Stairwell Fl, Lw, Uw, Ceiling S.E. Stairwell Fl, Lw, Uw, Ceiling 10 1 RO-1-8 East/West Hallway Fl, Lw, Uw 11' 1 RO-1-9 Rm 112-120, restrooms, closet, pipe chase, E.-W. Hallway Ceiling 12 1 RO- 1-10 North/South Hallway Fl, Lw, Uw 13 1 RO-l-11 Lobby, Rml00-108 Fl, Lw, Uw, WI, Rm109-111, Rm 121-126 Uw 14 2 RO-1-12 Lobby, Rml00-1 11, Rm 121-126, North/South Hallway Ceiling 16 2 RO-2-1 Room 207/207A/E.-W. Hall Fl 18 1 RO-2-2 Room 209-2 10 Fl 19 1 RO-2-3 Room 211/212 Fl 20 1 RO-2-4 Room 213/213A Fl 21 1 RO-2-5 Room 214/215/NS Hall Fl 22 1 RO-2-6 EW Hall Fl 23 1 RO-2-7 Laboratory Area Columns 24 1 RO-2-8 Wall Section 1 - Room 207/207A Walls Lw, Uw, WI 25 1 RO-2-9 Wall Section 2 - Room 207/207A/209/210/EW Hall Lw, Uw, WI 26 1 RO-2-10 Wall Section 3 - Rooms 211-213/213A N Wall Lw, Uw, WI 27 1 RO-2-1 I Wall Section 4 - Rooms 213A/214/215 W Wall Lw, Uw, Wl 28 1 RO-2-12 Wall Section 5 - Room 215, N.-S. Hall walls Lw, Uw 29 1 RO-2-13 Room 207/207A/EW Hall Ceiling 30 1 RO-2-14 Room 209-210 Ceiling 31 1 RO-2-15 Room 211/212 Ceiling 32 1 RO-2-16 Room 213/213A Ceiling 33 1 RO-2-17 Room 214/215/N.-S. Hall Ceiling 34 1 RO-2-18 EW Hall Ceiling 35 1 RO-2-19 Class 2 areas Fl, Lw, Uw, Wl, Ceiling 36 3 RO-2-20 Class 3 areas Fl, Lw, Uw, Wl 39 4 RO-2-21 Class 3 areas Ceiling 43 1 RO-2-22 Class I Ceiling Beams Ceiling 44 1 RO-2-23 Class 1 Ceiling Beams Ceiling 45 1 RO-3-1 Area Way Fl 46 1 RO-3-2 Vestibule, Men's Room, Janitor Closet. Cold Test Area (west) Fl 47 1 RO-3-3 Cold Test Area (center) Fl 48 1 RO-3-4 Cold Test Area (east) and Vault Fl 49 1 RO-3-5 Sump Room, Sumps, Elevator Sump Fl 50 1 RO-3-6 Sump Room, Men's Room, Janitor Lw 51 1 RO-3-7 Area Way and Vault Lw 52 1 RO-3-8 Cold Test Area and Vestibule Lw 53 1 RO-3-9 Sump Room Ceiling 54 1 RO-3-10 Sump Room Uw and Vestibule, Men's Room, Janitor Ceiling 55 1

Plum Brook Reactor Facility FSSR, Attachment 1 Appendix B Rev. 0, Page 3 of 72, Index of ROLB Survey Unit Maps and Tables of Coordinates Description Survey Unit (Rm=Room; FI=Floor;Lw=Lower wall; Uw=Upper wall; WI=Window Page Number ledges) Number of Pages RO-3-11 Men's Room, Janitor, and Vault Uw and Vault Ceiling 56 1 RO-3-12 Vestibule Uw and Area Way Ceiling 57 1 RO-3-13 Area Way Uw 58 1 RO-3-14 Cold Test Area and Columns Uw 59 1 RO-3-15 Cold Test Area (North) Ceiling 60 1 RO-3-16 Cold Test Area (North Central) Ceiling 61 1 RO-3-17 Cold Test Area (South Central) Ceiling 62 1 RO-3-18 Cold Test Area (South) Ceiling 63 1 RO-3-19 Not Used NA 0 RO-3-20 Not Used NA 0 RO-3-21 Not Used NA 0 RO-3-22 Not Used NA 0 RO-3-23 Not Used NA 0 RO-3-24 Not Used NA 0 RO-3-25 Rooms. 1, 3, 11, 12, 13, 13A, 14 -16, Fl, elevator shaft Fl, Walls & Ceiling 64 1 RO-3-26 Rooms. 1, 3, 11, 12, 13, 13A, 14 -16, Lw&Uw 65 1 RO-3-27 Rooms. 1, 3, 11, 12, 13, 13A, 14-16, Ceiling 66 3 RO-3-28A Crawl Space 69 1 RO-3-28B Crawl Space Soil 70 1 RO-4-1 Roof 71 1 RO-4-2 Exterior Walls 72 1

Plum Brook Reactor Facility FSSR, Attachment I Appendix B Rev. 0, Page 4 of 72, Survey Unit RO-1-1 ROLB 1st Floor, Rooms 117 & 118 (Floor)

• t +R *W *9 +W

• 99 *gm *ý

• W *R +W Survey Unit RO-1-1: ROLB Rooms 117 & 118 Floor X Coord Y Coord Label Value Type Notes 0.6 0.6 SM-1 575 Systematic NA 3.3 0.6 SM-2 535 Systematic NA 6.0 0.6 SM-3 827 Systematic NA 1.9 3.0 SM-4 685 Systematic NA 4.7 3.0 SM-5 567 Systematic NA 7.4 3.0 SM-6 496 Systematic NA 0.6 5.4 SM-7 543 Systematic NA 3.3 5.4 SM-8 535 Systematic NA 6.0 5.4 SM-9 630 Systematic NA 8.8 5.4 SM-10 512 Systematic NA 11.5 5.4 SM-11 913 Systematic NA Table Notes:

1. Measurement locations are established on a triangular grid with randomly selected starting coordinates.

2. Measurement values are in units of dpm/l00-cm 2.

Plum Brook Reactor Facility FSSR, Attachment I Appendix B Rev. 0, Page 5 of 72, Survey Unit RO-1-2 ROLB 1st Floor, Rooms 117 &118 (Lower Walls)

North Wall IEast Wall ISouth Wall IEast Wall I South Wall West Wall Survey Unit RO-I-2: ROLB Rooms 117 & 118, Lower Walls X Coord Y Coord Label Value Type Notes 2.9 0.9 SM-1 -94 Systematic NA 6.6 0.9 SM-2 55 Systematic NA 10.4 0.9 SM-3 71 Systematic NA 14.1 0.9 SM-4 354 Systematic NA 17.8 0.9 SM-5 16 Systematic NA 21.5 0.9 SM-6 260 Systematic NA 25.2 0.9 SM-7 134 Systematic NA 28.9 0.9 SM-8 -31 Systematic NA 32.6 0.9 SM-9 -323 Systematic NA 36.3 0.9 SM-0 189 Systematic NA 40.0 0.9 SM-11 79 Systematic NA

,-rA I able rNotes:

1. Measurement locations are established on a triangular grid with randomly selected starting coordinates.

2. Measurement values are in units of dpm/1 00-cm2.

Plum Brook Reactor Facility FSSR, Attachment 1 Appendix B Rev. 0, Page 6 of 72, Survey Unit RO- 1-3 ROLB 1st Floor, Rooms 119 & 120 (Floor)

N Survey Unit RO-1-3: ROLB 1 Floor, Rooms 119 & 120 (Floor)

X Coord Y Coord Label Value Type Notes 0.3 0.9 SM-1 638 Systematic NA 2.8 0.9 SM-2 795 Systematic NA 5.3 0.9 SM-3 890 Systematic NA 7.7 0.9 SM-4 669 Systematic NA 1.5 3.1 SM-5 693 Systematic NA 4.0 3.1 SM-6 646 Systematic NA 6.5 3.1 SM-7 787 Systematic NA 0.3 5.3 SM-8 717 Systematic NA 2.8 5.3 SM-9 591 Systematic NA 5.3 5.3 SM-10 638 Systematic NA 7.7 5.3 SM-11 -94 Systematic NA Table Notes:

1. Measurement locations are established on a triangular grid with randomly selected starting coordinates.

2. Measurement values are in units of dpm/100-cm 2.

Plum Brook Reactor Facility FSSR, Attachment I Appendix B Rev. 0, Page 7 of 72, Survey Unit RO- 1-4 ROLB 1st Floor, Rooms 119 & 120 Lower Walls & Window Ledges North Wall East Wall South Wall West Wall I II II II II I ImM= II I1* II 1111 I Survey Unit RO-1-4: ROLB Rooms 119 & 120 (lower walls and window ledges), Class 2 X Co-ord (m) Y Co-ord (m) Label Type Value Notes 1.54 0.53 SM-1 Systematic 157 NA 4.26 0.53 SM-2 Systematic 528 NA 6.98 0.53 SM-3 Systematic 409 NA 1.17 0.53 SM-4 Systematic 260 NA 3.88 0.53 SM-5 Systematic 118 NA 6.60 0.53 SM-6 Systematic 0 NA 1.24 0.53 SM-7 Systematic 0 NA 0.10 0.53 SM-8 Systematic 0 NA 2.82 0.53 SM-9 Systematic 31 NA 5.54 0.53 SM-10 Systematic 94 NA

-0.32 0.21 SM-1I Systematic 0 On west side of east window Table Notes:

1. Measurement locations are established on a triangular grid with randomly selected starting coordinates.

2. Measurement values are in units of dpm/1 00-cm2.

3. With the exception of SM-11, all of the other sample measurements are located by taking the lowest left-hand comer, of the surface on which they rest, as the origin. For example, the location of SM-1 is measured from the lower left hand comer of the north wall. SM-I I uses the glass and the lower ledge as the origin so one measures from the glass 0.32 meters out and then up 0.21 meters.

Plum Brook Reactor Facility FSSR, Attachment I Appendix B Rev. 0, Page 8 of 72, Survey Unit RO- 1-5 ROLB 1st Floor Class 2, Survey Unit, Rooms 109-120 M-1 SM- SM-3 SM EiII7i't 0111 111718

~Rms.

El Rms. 119& 120 117 & 118 Q Q 0 Rm 112 Rm. 113 Rm. 114 Rm. 115 Rm. 115 Storage Rms. 109- 111 measure from this point Survey Unit RO-1-5: ROLB 1st Floor, Rooms 109-120 X Co-ord (m) Y Co-ord (m) Label Value Type Notes 3.92 2.34 SM- I 173 Systematic N/A 3.98 2.34 SM-2 94 Systematic N/A 1.80 2.34 SM-3 220 Systematic N/A 3.85 2.34 SM-4 -87 Systematic N/A 3.25 0.84 SM-5 693 Systematic N/A 2.33 2.76 SM-6 39 Systematic N/A 2.16 -0.02 SM-7 -71 Systematic Window sill 0.05 1.30 SM-8 102 Systematic N/A 2.54 3.83 SM-9 543 Systematic N/A 0.28 2.75 SM-10 94 Systematic N/A 0.68 5.57 SM-11 677 Systematic N/A Table Notes:

I. Measurement locations are established on a triangular grid with randomly selected starting coordinates.

2. Measurement values are in units of dpm/100-cm2.

3. Other than SM-7, all of the other sample measurements are located by taking the lowest left-hand comer of the surface on which they rest as the origin. For example, the location of SM- I is measured from the lower left comer of the wall with windows. SM-7 (window sill), on the other hand, is measured from the inside left comer closest to the glass.

Plum Brook Reactor Facility FSSR, Attachment I Appendix B Rev. 0, Page 9 of 72, Survey Unit RO-1-6 ROLB 1st Floor Class 2 Survey Unit, Rooms 121-126 Um=% =

0 fiTf N.Closet Rm. 121 Rm. 122 a S.C loset WRm. 123 Janitor Closet Phone

~ Men's Rm. & Pipe Space C=

E Rm. 125 Lavatory 0

Closet SM -3 I m

-2 Rm. 126 Women's Rm.

Survey Unit RO-1-6: ROLB Is Floor, Rooms 121-126 X Co-ord (m) Y Co-ord (m) Label Value Type Notes 1.96 0.42 SM-1 2000 Systematic N/A 0.98 0.42 SM-2 1830 Systematic N/A 1.35 0.42 SM-3 2170 Systematic N/A 0.66 0.30 SM-4 2500 Systematic N/A 3.58 0.49 SM-5 315 Systematic N/A 1.94 0.49 SM-6 55 Systematic N/A 3.59 3.68 SM-7 811 Systematic N/A 0.32 0.14 SM-8 268 Systematic N/A 1.22 0.02 SM-9 559 Systematic N/A 3.76 1.05 SM-10 835 Systematic N/A

-1.03 -2.84 SM-11 417 Systematic Measured from NE comer of room Table Notes:

1. Measurement locations are established on a triangular grid with randomly selected starting coordinates.

2. Measurement values are in units of dpm/100-cm 2 .

3. Other than SM-11, all of the other sample measurements are located by taking the lowest left-hand comer, of the surface on which they rest, as the origin. For example, the location of SM-I is measured from the lower left hand comer of the wall. SM-I 1, on the other hand, is measured from the northeast comer of the room.

Plum Brook Reactor Facility FSSR, Attachment 1 Appendix B Rev. 0, Page 10 of 72, Survey Unit RO-1-7 ROLB 1st Floor Class., Survey MMi E & S Sta ells South Stairwell I I

-El' Penthouse Walls and Ceiling North Stairwell A

First Floor to Second Floor Second Floor to Penth Basement to First Floor Survey Unit RO-1-7: ROLB North and South Stairwells X Co-ord (m) Y Co-ord (m) Label Value Type Notes 0.85 1.55 SM- 1 -30 Systematic Under stairs 1.75 1.10 SM-2 79 Systematic North wall 1.65 1.09 SM-3 122 Systematic South wall 3.78 .60 SM-4 720 Systematic 2 floor landing nd 1.52 1.86 SM-5 -37 Systematic West wall 0.54 0.67 SM-6 262 Systematic Under stairs 0.44 1.88 SM-7 55 Systematic West wall 0.70 0.11 SM-8 Systematic Vertical surface between 6 ' step and 140 landing 0.31 2.27 SM-9 37 Systematic East wall

-0.21 2.10 SM-10 262 Systematic West wall 0.71 0.11 SM-11 1159 Systematic 3" step Table Notes:

1. Measurement locations are established on a triangular grid with randomly selected starting coordinates.

2. Measurement values are in units of dpm/100-cm 2.

3. Other than SM-10, all of the other sample measurements are located by taking the lowest left-hand comer, of the surface on which they rest, as the origin. For example, the location of SM-5 is measured from the lower left hand comer of the west wall. SM-10 is measured from the lower east comer where the top of the bottom stair step meets the west wall.

Plum Brook Reactor Facility FSSR, Attachment I Appendix B Rev. 0, Page 11 of 72, Survey Unit RO-1-8 ROLB 1st Floor Class 2 Survey Unit, EW Hallway Ceiling IU 120A PC 119 PC 117 PC 115A PC 114 PC I Nit h North Wall EE East Wall South Wall PI 115 PC 11 120B PC 120 PC 118PC 115B PC Survey Unit RO-1-8: ROLB East/West Hallway X Co-ord (m) Y Co-ord (m) Label Value Type Notes 0.56 0.41 SM-1 710 Systematic N/A 0.12 0.25 SM-2 1000 Systematic N/A 0.45 0.30 SM-3 637 Systematic N/A 0.21 2.53 SM-4 532 Systematic Rear wall of pipe chase 0.74 2.53 SM-5 435 Systematic Inside of front wall 0.48 2.53 SM-6 476 Systematic Far left wall 1.77 0.59 SM-7 -129 Systematic N/A

-0.31 0.59 SM-8 234 Systematic N/A 1.01 0.58 SM-9 -24 Systematic N/A 0.36 0.87 SM-10 347 Systematic Back wall left of column

-0.08 0.87 SM-11 403 Systematic Inside front wall Table Notes:

1. Measurement locations are established on a triangular grid with randomly selected starting coordinates.

2. Measurement values are in units of dpm/1 00-cm2.

3. Other than SM-8 and SM-11, all of the other sample measurements are located by taking the lowest left-hand comer, of the surface on which they rest, as the origin. For example, the location of SM-7 is measured from the lower left hand comer of the north wall. Both SM-8 and SM-1I are measured from the lower right comer where the walls meet the floor.

Plum Brook Reactor Facility FSSR, Attachment I Appendix B Rev. 0, Page 12 of 72, Survey Unit RO-1-9 ROLB 1st Floor Class 2 Survey Unit, Rooms 112-120 & EW Hallway Ceilings Ceilings of Rooms North of the East/.A... .

~ a~ a 4 n ~ fl ii Ceiling above the SM-7 SM-8 Ceiling of Rooms South of the East/West I-alway im ~i III S-3 fCeiling SM-I SM-2 behind North Stairwell Ceilings from Rest Rtonx6 ' C*lklt~1or Shaft North/South Concrete Beam at West End of East/West Hallway Survey Unit RO-1-9: ROLB Is' Floor, Class 2 Ceilings X Co-ord (m) Y Co-ord (m) Label Value Type Notes 1.91 7.51 SM-1 1031 Systematic Overhead of Men's Room 0.29 0.58 SM-2 268 Systematic North of south column 1.83 15.2 SM-3 685 Systematic Overhead of Men's Room 0.57 1.43 SM-4 630 Systematic Overhead of Rm. 117 3.51 1.97 SM-5 622 Systematic 12.34 1.97 SM-6 724 Systematic Overhead of east/west hallway 21.17 1.97 SM-7 339 Systematic 29.99 1.97 SM-8 480 Systematic 7.93 1.48 SM-9 567 Systematic Overhead of Rm. 119/120 16.76 1.48 SM-10 528 Systematic Overhead of Rm. 117/118 25.58 1.48 SM-11 457 Systematic Overhead of Rm. 117/118 Table Notes:

1.Measurement locations are established on a triangular grid with randomly selected starting coordinates.

2. Measurement values are in units of dpm/1 00-cm 2.

3. Other than SM-2, all of the other sample measurements are located by taking the lowest left-hand comer, of the surface on which they rest, as the origin. For example, the location of SM-4 is measured from the lower left hand comer (southwest comer) of the ceiling. SM-2, on the other hand, is measured from inside the south ceiling support column.

Plum Brook Reactor Facility FSSR, Attachment I Appendix B Rev. 0, Page 13 of 72, Survey Unit RO- I- 10 ROLB 1st Floor Class 3 Survey Unit, N-S Hallway Floor South Wall TT _JM==

West Wall 111mmIUn1ý'l West Wall North Wall p

East Wall U

Ui Cubby Hole Rm. 108A Survey Unit RO-1-10: ROLB 18 Floor, N-S Hallway, Class 3 X Co-ord (m) Y Co-ord (in) Label Value Type Notes 22.17 0.04 SM-1 1960 Random N/A 11.85 1.56 SM-2 730 Random N/A 1.22 1.45 SM-3 241 Random N/A 12.95 1.51 SM-4 220 Random N/A 7.98 0.02 SM-5 433 Random N/A 0.58 0.69 SM-6 57 Random N/A 39.88 0.61 SM-7 411 Random N/A 15.68 2.14 SM-8 57 Random N/A 7.58 0.24 SM-9 135 Random N/A 1.86 0.01 SM-10 220 Random N/A 7.05 1.23 SM- 1 206 Random N/A Table Notes:

1. Measurement locations are selected on a random basis - Class 3 survey unit.

2. Measurement values are in units of dpm/100-cm 2.

3. All sample measurements are located by taking the lowest left-hand comer, of the surface on which they rest, as the origin. For example, the location of SM- I is measured from the lower left hand comer (southeast comer) of the north/south hallway.

Plum Brook Reactor Facility FSSR, Attachment I Appendix B Rev. 0, Page 14 of 72, Survey Unit RO-1-1 I ROLB 1st Floor Class 3 Survey Unit, Lobby, Rooms 100-108, 109-111, 121-126 (pag Iof 2) a UT LRm. 121 Rm. 122 a Closets E* Rm. 123

_ LIIH 1 11 II D

P72 I II=I E Rm. 124 Rms. 109-111 D Rm. 125 Rm. 108

[I] Rm. 126

Plum Brook Reactor Facility FSSR, Attachment I Appendix B Rev. 0, Page 15 of 72, Survey Unit RO-1-1 I ROLB 1st Floor Class 3 Survey Unit, Lobby, Rooms 100-108, 109-111, 121-126 (Page 2 of 2)

M1 Lobby Rm. 107 C=

C=

Rm. 100

__Lnmý_s I Rm. 106 0- Rm. 101 ARm. 105 E Rm. 102 SM-11L R.104 measure from this corner ERm. 103 Survey Unit RO-1-11: ROLB 1V Floor, Class 3 X Co-ord (m) Y Co-ord (m) Label Value Type Notes 0.75 0.56 SM-I 231 Random N/A 1.47 0.95 SM-2 340 Random N/A 4.25 1.41 SM-3 -324 Random N/A 0.27 0.30 SM-4 528 Random See map for point of origin 3.68 2.87 SM-5 1306 Random N/A 1.74 2.54 SM-6 463 Random N/A 2.50 0.70 SM-7 204 Random N/A 0.52 0.74 SM-8 287 Random N/A 1.91 2.84 SM-9 -9 Random N/A 0.62 0.35 SM-10 583 Random N/A 1.65 0.64 SM-I1 231 Random N/A Table Notes:

1. Measurement locations are selected on a random basis - Class 3 survey unit.

2. Measurement values are in units of dpm/100-cm 2.

3. With the exception of SM-4 all other sample measurements are located by taking the lowest left-hand comer, of the surface on which they rest, as the origin. For example, the location of SM- 11is measured from the lower left hand comer of the west wall of Room 104 (the extreme southwest comer of the room). SM-4 is measured from a point just inside the entrance door (see map for location).

Plum Brook Reactor Facility FSSR, Attachment 1 Appendix B Rev. 0, Page 16 of 72, Survey Unit RO-l-12 (Page 1 of 2)

ROLB 1st Floor Class 3 Survey Unit, Rooms 110-111, 121-126 & N-S Hallway v Beam Bem Hallwa A

ast Room Beams SI WM-

-7 SMF-41C IIi SN West Rooms Ceiling East Roon ns Ceiling West Room Beams North/South Hallway Ceiling

Plum Brook Reactor Facility FSSR, Attachment I Appendix B Rev. 0, Page 17 of 72, Survey Unit RO-l-12 (Page 2 of 2)

Survey Unit RO-1-12: ROLB 1s" Floor Class 3 X Co- Y Co- Label Value Type Notes ord (m) ord (m) 1.25 N/A SM-1 282 Random Lowest horizontal surface of the 74th beam 1.62 N/A SM-2 514 Random North slanted surface of the 11 h beam 0.41 N/A SM-3 437 Random Lowest horizontal surface of the 2 2 nd beam 0.35 N/A SM-4 479 Random Between 7th and 8th beam 0.74 N/A SM-5 289 Random Between 6 3rd and 64th beam 0.90 N/A SM-6 528 Random South vertical surface of the 67th beam 0.46 N/A SM-7 465 Random Between 39th and 40th beam 0.45 N/A SM-8 1000 Random South vertical surface of the 8th beam 0.21 -0.16 SM-9 739 Random Measured from the northwest comer 0.12 N/A SM-10 585 Random Between 17th and 1 8 th beam 0.47 N/A SM-11 359 Random Lowest horizontal surface of the 71st beam Table Notes:

1. Measurement locations are selected on a random basis - Class 3 survey unit.

2. Measurement values are in units of dpm/100-cm 2.

3. With the exception of SM-9, all other all other sample measurements are determined by taking the x-coordinate as the distance from the west wall. The notes column (above) denotes what beam the sample measurement point is located. SM-9 is measured from the extreme northwestern corner of the ceiling beam where it mates with the north wall above the double door opening.

Plum Brook Reactor Facility FSSR, Attachment I Appendix B Rev. 0, Page 18 of 72, Survey Unit RO-2-1 ROLB 2nd Floor Class 1 Survey Unit L

or§E East/West Hallway Between Columns B4/B5 and C4/C5 4ý OtiKý Owii Room 207 Room 207A Survey Unit RO-2-1: ROLB 2"n Floor, Class I X Co-ord (m) Y Co-ord (im) Label Value Type Notes 2.05 0.63 SM-1 640 Systematic N/A 4.63 0.63 SM-2 784 Systematic N/A 7.21 0.63 SM-3 480 Systematic N/A 0.75 2.86 SM-4 536 Systematic N/A 3.34 2.86 SM-5 568 Systematic N/A 5.92 2.86 SM-6 368 Systematic N/A 2.05 5.10 SM-7 -8 Systematic N/A 4.63 5.10 SM-8 216 Systematic N/A 0.75 7.34 SM-9 480 Systematic N/A 3.34 7.34 SM-10 160 Systematic N/A 2.05 9.57 SM-1 1 296 Systematic N/A Table Notes:

I Measurement locations are established on a triangular grid with randomly selected starting coordinates.

2

2. Measurement values are in units of dpm/100-cm .

3. All of the sample measurements are located by taking the lowest left-hand comer, of the surface on which they rest, as the origin. For example, the location of SM-I is measured from the lower left hand comer of the survey unit (southwest comer of Room 207).

Plum Brook Reactor Facility FSSR, Attachment I Appendix B Rev. 0, Page 19 of 72, Survey Unit RO-2-2 ROLB 2nd Floor Class 1 Survey Unit N

Room 210 Room 209 Survey Unit RO-2-2: ROLB 2n' Floor, Rooms 209-210 (floor), Class I X Co-ord (m) Y Co-ord (mi) Label Value Type Notes 0.53 1.30 SM- 1 887 Systematic N/A 2.99 1.30 SM-2 742 Systematic N/A 5.45 1.30 SM-3 421 Systematic N/A 7.91 1.30 SM-4 767 Systematic N/A 1.76 3.43 SM-5 779 Systematic N/A 4.22 3.43 SM-6 761 Systematic N/A 6.68 3.43 SM-7 1100 Systematic N/A 0.53 5.56 SM-8 830 Systematic N/A 2.99 5.56 SM-9 836 Systematic N/A 5.45 5.56 SM-l0 823 Systematic N/A 7.91 5.56 SM-lI 723 Systematic N/A Table Notes:

1. Measurement locations are established on a triangular grid with randomly selected starting coordinates.

2. Measurement values are in units of dpm/100-cm 2 .

3. All of the sample measurements are located by taking the lowest left-hand comer, of the surface on which they rest, as the origin. For example, the location of SM-1 is measured from the lower left hand comer of the survey unit (at column E4).

Plum Brook Reactor Facility FSSR, Attachment I Appendix B Rev. 0, Page 20 of 72, Survey Unit RO 2-3 ROLB 2nd Floor Class 1 Survey Unit Room 212 Room 211 Survey Unit RO-2-3: ROLB 2"" Floor, Rooms 211-212 (floor) Class I X Co-ord (m) Y Co-ord (m) Label Value Type Notes 2.15 0.46 SM-1 832 Systematic N/A 4.75 0.46 SM-2 700 Systematic N/A 7.34 0.46 SM-3 627 Systematic N/A 0.85 2.71 SM-4 788 Systematic N/A 3.45 2.71 SM-5 459 Systematic N/A 6.04 2.71 SM-6 1021 Systematic N/A 2.15 4.96 SM-7 890 Systematic N/A 4.75 4.96 SM-8 766 Systematic N/A 7.34 4.96 SM-9 810 Systematic N/A 0.85 7.21 SM-10 744 Systematic N/A 3.45 7.21 SM-I 1 919 Systematic N/A Table Notes:

1. Measurement locations are established on a triangular grid with randomly selected starting coordinates.

2. Measurement values are in units of dpm/100-cm2.

3. All of the sample measurements are located by taking the lowest left-hand comer, of the surface on which they rest, as the origin. For example, the location of SM-1 is measured from the lower left hand comer of the survey unit (at column E4).

Plum Brook Reactor Facility FSSR, Attachment I Appendix B Rev. 0, Page 21 of 72, Survey Unit RO-2-4 ROLB 2nd Floor Class I Survey Unit Okij 1ika N

1~i~

Room 213A Room 213 Survey Unit RO-2-4: ROLB 2 n Floor, Rooms 213-213A (floor) Class I X Co-ord (mi) Y Co-ord (mi) Label Value Type Notes 0.16 2.12 SM-I 120 Systematic N/A 2.84 2.12 SM-2 352 Systematic N/A 5.52 2.12 SM-3 520 Systematic N/A 8.20 2.12 SM-4 -504 Systematic N/A 1.50 4.44 SM-5 -48 Systematic N/A 4.18 4.44 SM-6 496 Systematic N/A 6.86 4.44 SM-7 368 Systematic N/A 0.16 6.76 SM-8 416 Systematic N/A 2.84 6.76 SM-9 728 Systematic N/A 5.52 6.76 SM-10 256 Systematic N/A 8.20 6.76 SM-I 1 544 Systematic N/A Table Notes:

1. Measurement locations are established on a triangular grid with randomly selected starting coordinates.

2. Measurement values are in units of dpm/100-cm 2.

3. All of the sample measurements are located by taking the lowest left-hand corner, of the surface on which they rest, as the origin.

Plum Brook Reactor Facility FSSR, Attachment 1 Appendix B Rev. 0, Page 22 of 72, Survey Unit RO-2-5 ROLB 2nd Floor Class I Survey Unit Room 214 Room 215 North/South -tllw yý Survey Unit RO-2-5: ROLB 2nd Floor, Rooms 214-215, N-S Hallway (floors), Class 1 X Co-ord (m) Y Co-ord (m) Label Value Type Notes 1.41 0.71 SM-1 817 Systematic Note 3 2.34 0.94 SM-2 693 Systematic N/A 5.01 0.94 SM-3 700 Systematic N/A 1.00 3.25 SM-4 109 Systematic N/A 3.67 3.25 SM-5 -7.3 Systematic N/A 6.34 3.25 SM-6 693 Systematic N/A 2.34 5.57 SM-7 824 Systematic N/A 5.01 5.57 SM-8 313 Systematic N/A 1.00 7.88 SM-9 810 Systematic N/A 3.67 7.88 SM-10 773 Systematic N/A 6.34 7.88 SM-11 518 Systematic N/A Table Notes:

1. Measurement locations are established on a triangular grid with randomly selected starting coordinates.

2. Measurement values are in units of dpm/100-cm 2.

3. With exception of SM-1, all of the sample measurements are located by taking the lowest left-hand comer, of the surface on which they rest, as the origin. For example, SM-2 is measured from the southwest comer of Room 215. SM-1 is measured from the southwest comer of the North/South Hallway.

Plum Brook Reactor Facility FSSR; Attachment 1 Appendix B Rev. 0, Page 23 of 72, Survey Unit RO-2-6 ROLB 2nd Floor Class I Survey Unit East'West Hallway Survey Unit RO-2-6: ROLB 2nd Floor, E-W Hallway, Sections C-H (floors), Class I X Co-ord (m) Y Co-ord (m) Label Value Type Notes 2.69 0.10 SM-I 812 Systematic Note 3 5.96 0.10 SM-2 315 Systematic N/A 9.24 0.10 SM-3 483 Systematic N/A 12.51 0.10 SM-4 752 Systematic N/A 15.78 0.10 SM-5 678 Systematic N/A 1.06 2.94 SM-6 756 Systematic N/A 4.33 2.94 SM-7 456 Systematic N/A 7.60 2.94 SM-8 101 Systematic N/A 10.87 2.94 SM-9 678 Systematic N/A 14.14 2.94 SM-10 812 Systematic N/A 17.42 2.94 SM- 1 792 Systematic N/A Table Notes:

1. Measurement locations are established on a triangular grid with randomly selected starting coordinates.

2. Measurement values are in units of dpm/100-cm2.

3. All of the sample measurements are located by taking the lowest left-hand comer, of the surface on which they rest, as the origin. For example, SM-1 is measured from the south comer from where the North/South Hallway and the East/West Hallway meet.

Plum Brook Reactor Facility FSSR, Attachment I Appendix B Rev. 0, Page 24 of 72, Survey Unit RO-2-7 ROLB 2nd Floor Class I Survey Unit NESW SM J6 J4 H4 F4 E4 D4 C4 E5 D5 Concrete Columns KEY: N is the north face of the column E is the east face of the column S is the south face of the column W is the west face of the column Survey Unit RO-2-7: ROLB 2nd Floor Columns, Class 1 X Co-ord (mi) Y Co-ord (m) Label Value Type Notes 0.17 1.10 SM- i 606 Systematic South column face 0.09 1.10 SM-2 701 Systematic North column face 0.03 1.10 SM-3 693 Systematic West column face 0.04 1.10 SM-4 323 Systematic South column face 0.11 1.10 SM-5 598 Systematic East column face 0.09 1.10 SM-6 843 Systematic North column face 0.14 2.76 SM-7 811 Systematic West column face 0.15 2.76 SM-8 378 Systematic South column face 0.25 2.76 SM-9 535 Systematic East column face 0.14 2.76 SM-10 890 Systematic West column face 0.03 2.76 SM- 11 858 Systematic West column face Table Notes:

I. Measurement locations are established on a triangular grid with randomly selected starting coordinates.

2. Measurement values are in units of dpm/1 00-cm 2.

3. All of the sample measurements are located by taking the lowest left-hand comer, of the surface on which they rest, as the origin. For example, SM-I is measured on the south face from the lower left comer (against the floor).

Plum Brook Reactor Facility FSSR, Attachment I Appendix B Rev. 0, Page 25 of 72, Survey Unit RO-2-8 ROLB 2nd Floor Class I Survey Unit East Wall South Wall I South Wall West Wall Room 207A I Room 207 1, I Column C5 Survey Unit RO-2-8: ROLB 2nd Floor, Rooms 207 & 208, Wall Section 1, Class I X Co-ord (m) Y Co-ord (m) Label Value Type Notes 0.36 0.92 SM-l -34 Systematic N/A 3.12 0.92 SM-2 402 Systematic N/A 2.17 0.92 SM-3 307 Systematic N/A

-3.49 0.92 SM-4 394 Systematic Measured from southwest comer of

-0.74 0.92 SM-5 402 Systematic Room 207 2.01 0.92 SM-6 94 Systematic N/A 4.76 0.92 SM-7 16 Systematic N/A 0.07 0.92 SM-8 551 Systematic West face of column C5 0.79 3.31 SM-9 71 Systematic N/A 3.54 3.31 SM-10 8 Systematic N/A

-2.12 3.31 SM-11 Systematic Measured from southwest comer of

_ _ -47 Room 207 Table Notes:

I. Measurement locations are established on a triangular grid with randomly selected starting coordinates.

2. Measurement values are in units of dpm/100-cm 2.

3. With the exception of SM-4, SM-5, and SM-1 l, all of the sample measurements are located by taking the lowest left-hand comer, of the surface on which they rest, as the origin. For example, SM-8 is measured, on the west face of column C5, from the lower left (north) corner. SM-4, SM5, and SM-Il are measured from the southwest comer of Room 207.

Plum Brook Reactor Facility FSSR, Attachment I Appendix B Rev. 0, Page 26 of 72, Survey Unit RO-2-9 ROLB 2nd Floor Class I Survey Unit is 11 1ý North Wall North Wall Room 210 Room 209 F~~1 LU IU4I 114ý East Wall LJ lJ IIII Room 207 East Wall-' Column North Wall No Wall East/West Hallway B5 Room 207 Room 207A Survey Unit RO-2-9: ROLB 2nd Floor, Wall Section 2, Class 1, X Co-ord (m) Y Co-ord (m) Label Value Type Notes 2.56 0.90 SM-1 -56 Systematic N/A 1.11 0.90 SM-2 -216 Systematic N/A 2.55 0.90 SM-3 62 Systematic N/A 1.97 0.90 SM-4 -309 Systematic N/A 1.19 3.27 SM-5 136 Systematic N/A 0.60 3.27 SM-6 111 Systematic N/A 0.41 2.34 SM-7 -99 Systematic Measured from the approximate 3.14 2.34 SM-8 -37 Systematic center of column E2 5.87 2.34 SM-9 1537 Systematic 0.20 0.13 SM-10 31 Systematic Upper sill 2.93 0.13 SM-11 354 Systematic Table Notes:

1. Measurement locations are established on a triangular grid with randomly selected starting coordinates.

2. Measurement values are in units of dpm/100-cm 2.

3. With the exception of SM- 10 and SM- 11, all of the sample measurements are located by taking the lowest left-hand comer, of the surface on which they rest, as the origin. For example, SM-1 is measured from the north comer of the East/West Hallway. SM-I 0 and SM-I 1 are measured from where the sill frame and the glass meet in Room 210.

Plum Brook Reactor Facility FSSR, Attachment I Appendix B Rev. 0, Page 27 of 72, Survey Unit RO-2-10 ROLB 2nd Floor Class I Survey Unit LII Ism-IlI uS- SM-I IL I SM-I SM- SM SM North Wall North Wall North Wall East Wa* North Wall Room 213A Room 213 Room 212 I Room 211 Survey Unit RO-2-10: ROLB 2nd Floor, Wall Section 3, Class I X Co-ord (im) Y Co-ord (m) Label Value Type Notes 0.28 0.13 SM-1 311 Systematic 4.10 0.13 SM-2 335 Systematic Measured from the northwest 7.93 0.13 SM-3 128 Systematic comer of Room 213A 11.75 0.13 SM-4 274 Systematic 1.62 0.13 SM-5 299 Systematic N/A 2.19 3.44 SM-6 -24 Systematic Measured from the northwest 6.01 3.44 SM-7 73 Systematic comer of Room 213A 9.84 3.44 SM-8 159 Systematic 1.32 3.44 SM-9 280 Systematic N/A 3.53 3.44 SM-b10 18 Systematic N/A 0.29 0.93 SM-11 -18 Systematic East side of window frame Table Notes:

I. Measurement locations are established on a triangular grid with randomly selected starting coordinates.

2. Measurement values are in units of dpm/l 00-cm2 .

3. SM-5, SM-9, and SM-10 are measured from the lower left comer of the surface on which the sample measurements are located. Since walls have been removed from this survey unit, SM-I through SM-4 and SM-6 through SM-8 are measured from the northwest comer of Room 213A. SM-Il is measured from where the sill frame and the glass meet in Room 213A.

Plum Brook Reactor Facility FSSR, Attachment I Appendix B Rev. 0, Page 28 of 72, Survey Unit RO-2-11 ROLB 2nd Floor Class I Survey Unit nI I

West Wall West Wall West Wall Room 215 Room 214 Room 213A Survey Unit RO-2-11: ROLB 2nd Floor, Wall Section 4, Class I X Co-ord (m) Y Co-ord (im) Label Value Type Notes 2.14 0.12 SM-1 55 Systematic 5.66 0.12 SM-2 30 Systematic 9.18 0.12 SM-3 -37 Systematic 12.71 0.12 SM-4 287 Systematic 16.23 0.12 SM-5 213 Systematic Measured from the southwest comer of 0.37 3.17 SM-6 -12 Systematic Room 215 3.90 3.17 SM-7 238 Systematic 7.42 3.17 SM-8 67 Systematic 10.94 3.17 SM-9 6 Systematic 14.47 3.17 SM-10 293 Systematic 0.18 1.04 SM- 1l 232 Systematic East side of window frame Table Notes:

I. Measurement locations are established on a triangular grid with randomly selected starting coordinates.

2. Measurement values are in units of dpm/100-cm 2.

3. Since walls have been removed from this survey unit, SM-I through SM-10 are measured from the southwest comer of Room 215. SM-Il is measured from where the sill frame and the glass meet in Room 213A.

Plum Brook Reactor Facility FSSR, Attachment I Appendix B Rev. 0, Page 29 of 72, Survey Unit RO-2-12 ROLB 2nd Floor Class I Survey Unit 4.

-11M ~j~j SM-Il

.4 .4 .4444.

South Wall SMULI]

East Wall I 159~

I South Wall I West Wall South Wall East/West Hallway North/South Hallway Room 215 Col mn mn IIo F5 J7 Survey Unit RO-2-12: ROLB 2nd Floor, Wall Section 5, Class 1 X Co-ord (im) Y Co-ord (m) Label Value Type Notes 1.04 0.63 SM-I 359 Systematic N/A 1.57 0.63 SM-2 268 Systematic N/A 0.42 0.63 SM-3 127 Systematic N/A 2.92 0.63 SM-4 120 Systematic N/A 0.54 0.63 SM-5 239 Systematic N/A 0.46 0.63 SM-6 -113 Systematic Measured from northwest comer of 2.95 0.63 SM-7 -106 Systematic column J7 0.11 2.79 SM-8 535 Systematic West face of column F5 1.79 2.79 SM-9 -106 Systematic N/A 1.70 2.79 SM-10 99 Systematic Measured from northwest comer of 4.26 2.79 SM-11 -56 Systematic column 17 Table Notes:

1. Measurement locations are established on a triangular grid with randomly selected starting coordinates.

2. Measurement values are in units of dpm/100-cm 2 .

3. With the exception of SM-6, SM-7, SM-10, and SM-I 1, all of the other sample measurements are located by taking the lowest left-hand comer, of the surface on which they rest, as the origin. For example, SM-5 is measured from the southwest comer of the north/south hallway at the double doors.

SM-6, SM-7, SM-IO, and SM-Il are measured from the northwest comer of column J7.

Plum Brook Reactor Facility FSSR, Attachment 1 Appendix B Rev. 0, Page 30 of 72, Survey Unit RO-2-13 ROLB 2nd Floor Class I Survey Unit East/West Hallway Room 207 Room 207 Room 207A

• ER3 Survey Unit RO-2-13: ROLB 2nd Floor, Rooms 207, 207A, E-W Hallway (ceilings), Class I X Co-ord (m) Y Co-ord (m) Label Value TvDe Notes 2.26 1.18 SM-I 416 Systematic Note 3 0.38 1.18 SM-2 453 Systematic Note 3 2.84 1.18 SM-3 562 Systematic Note 3 1.04 3.30 SM-4 547 Systematic Note 3 3.49 3.30 SM-5 292 Systematic Note 3 1.61 3.30 SM-6 504 Systematic Note 3 2.26 5.43 SM-7 482 Systematic Note 3 0.38 5.43 SM-8 584 Systematic Note 3 1.04 7.55 SM-9 642 Systematic Note 3 3.49 7.55 SM-10 482 Systematic Note 3 2.26 9.68 SM-11 416 Systematic Note 3 Table Notes:

1. Measurement locations are established on a triangular grid with randomly selected starting coordinates.

2. Measurement values are in units of dpm/100-cm 2.

3. SM-I, SM-4, SM-5, SM-7, SM-9, SM-10, and SM-I l are measured from the southwest comer of Room 207 at column C8. SM-2, SM-3, SM-6, and SM-8 are measured from the southwest comer of Room 207A at column B8.

Plum Brook Reactor Facility FSSR, Attachment I Appendix B Rev. 0, Page 31 of 72, Survey Unit RO-2-14 ROLB 2nd Floor Class I Survey Unit Room 210 Ceiling Room 209 Ceiling Survey Unit RO-2-14: ROLB 2nd Floor, Rooms 209 & 210 (ceilings), Class I X Co-ord (m) Y Co-ord (m) Label Value Type Notes 0.57 0.41 SM-1 920 Systematic Note 3 2.90 0.41 SM-2 1139 Systematic Note 3 1.73 2.42 SM-3 526 Systematic Note 3 0.57 4.44 SM-4 526 Systematic Note 3 2.90 4.44 SM-5 394 Systematic Note 3 1.73 6.45 SM-6 1489 Systematic Note 3 0.61 0.85 SM-7 861 Systematic Note 3 2.93 0.85 SM-8 423 Systematic Note 3 1.77 2.87 SM-9 423 Systematic Note 3 0.61 4.88 SM-10 664 Systematic Note 3 2.93 4.88 SM-I 1 387 Systematic Note 3 Table Notes:

1. Measurement locations are established on a triangular grid with randomly selected starting coordinates.

2. Measurement values are in units of dpm/1 00-cm 2.

3. SM-I through SM-6 are measured from the southwest comer of Room 210. SM-7 through SM-Il are measured from the southwest comer of Room 209.

Plum Brook Reactor Facility FSSR, Attachment I Appendix B Rev. 0, Page 32 of 72, Survey Unit RO-2-15 ROLB 2nd Floor Class 1 Survey Unit

• ffiý Room 212 Ceiling Room 211 Ceiling Survey Unit RO-2-15: ROLB 2nd Floor, Rooms 211 & 212 (ceilings), Class I X Co-ord (m) Y Co-ord (mi) Label Value Type Notes 1.70 1.04 SM-1 1599 Systematic Note 3 0.48 3.15 SM-2 467 Systematic Note 3 2.91 3.15 SM-3 1679 Systematic Note 3 1.70 5.25 SM-4 599 Systematic Note 3 0.48 7.36 SM-5 270 Systematic Note 3 2.91 7.36 SM-6 693 Systematic Note 3 1.08 1.19 SM-7 613 Systematic Note 3 3.52 1.19 SM-8 854 Systematic Note 3 2.30 3.30 SM-9 146 Systematic Note 3 1.08 5.41 SM-10 1321 Systematic Note 3 3.52 5.41 SM-11 1073 Systematic Note 3 Table Notes:

1. Measurement locations are established on a triangular grid with randomly selected starting coordinates.

2. Measurement values are in units of dpm/100-cm2.

3. SM-1 through SM-6 are measured from the southwest comer of Room 212. SM-7 through SM-Il are measured from the southwest comer of Room 211.

Plum Brook Reactor Facility FSSR, Attachment 1 Appendix B Rev. 0, Page 33 of 72, Survey Unit RO-2-16 ROLB 2nd Floor Class I Survey Unit Room 213A Ceiling Room 213 Ceiling Survey Unit RO-2-16: ROLB 2nd Floor, Rooms 213/213A (ceilings), Class 1 X Co-ord (m) Y Co-ord (m) Label Value Type Notes 0.76 2.03 SM-1 431 Systematic Note 3 3.29 2.03 SM-2 693 Systematic Note 3 2.03 4.22 SM-3 161 Systematic Note 3 0.76 6.41 SM-4 321 Systematic Note 3 3.29 6.41 SM-5 511 Systematic Note 3 0.80 0.47 SM-6 701 Systematic Note 3 3.33 0.47 SM-7 1051 Systematic Note 3 2.07 2.66 SM-8 438 Systematic Note 3 0.80 4.85 SM-9 1051 Systematic Note 3 3.33 4.85 SM-10 496 Systematic Note 3 2.07 7.04 SM-11 613 Systematic Note 3 Table Notes:

1. Measurement locations are established on a triangular grid with randomly selected starting coordinates.

2. Measurement values are in units of dpm/100-cm 2.

3. SM-1 through SM-5 are measured from the southwest comer of Room 213A. SM-6 through SM-1I are measured from the southwest comer of Room 213.

Plum Brook Reactor Facility FSSR, Attachment I Appendix B Rev. 0, Page 34 of 72, Survey Unit RO-2-17 ROLB 2nd Floor Class 1 Survey Unit ISM-3I N-S Hallway Ceiling Room 214/215 Ceiling SM-Survey Unit RO-2-17: ROLB 2nd Floor, Rooms 214, 125, N-S Hall (ceilings), Class I X Co-ord (m) Y Co-ord (m) Label Value Type Notes 1.09 4.58 SM-I 708 Systematic Between 4h"and 5t beam 1.09 9.34 SM-2 635 Systematic South slanted surface of the 10th beam 1.09 14.11 SM-3 380 Systematic South vertical surface of the 15t' beam 1.55 0.51 SM-4 380 Systematic N/A 4.30 0.51 SM-5 562 Systematic N/A 0.18 2.90 SM-6 526 Systematic N/A 2.93 2.90 SM-7 657 Systematic N/A 1.55 5.28 SM-8 657 Systematic N/A 4.30 5.28 SM-9 372 Systematic N/A 0.18 7.67 SM-10 394 Systematic N/A 2.93 7.67 SM-I 1 409 Systematic N/A Table Notes:

1. Measurement locations are on a triangular grid with randomly selected starting coordinates.

2. Measurement values are in units of dpm/1 00-cm 2.

3. SM-1 through SM-3 are measured from the southwest corner of the North/South Hallway. SM-4 through SM-1I are measured from the southwest comer of Room 215.

Plum Brook Reactor Facility FSSR, Attachment 1 Appendix B Rev. 0, Page 35 of 72, Survey Unit RO-2-18 ROLB 2nd Floor Class I Survey Unit

• 99 *LSM--G

-HSM-I Between Columns Between Columns Between Columns Between Columns Columns H4 & F4/F5 F4/F5 & E4/E5 E4/E5 & D4/D5 D4/D5 & C4/C5 East/West Hallway Survey Unit RO-2-18: ROLB 2nd Floor, E-W Hall, Section C-H (ceiling), Class 1 X Co-ord (m) Y Co-ord (m) Label Value Type Notes 2.41 0.20 SM-1 409 Systematic Measured from the SW comer of where 1.13 2.41 SM-2 971 Systematic the E/W hall meets the N/S hall 3.69 2.41 SM-3 766 Systematic 1.74 1.11 SM-4 555 Systematic F4/F5 roof beam at column F5 0.47 3.33 SM-5 555 Systematic 3.02 3.33 SM-6 504 Systematic 0.60 2.05 SM-7 715 Systematic E4/E5 roof beam at column E5 3.15 2.05 SM-8 460 Systematic 1.69 0.40 SM-9 321 Systematic D4/D5 roof beam at column D5 0.41 2.61 SM-10 693 Systematic 2.97 2.61 SM-I 1 577 Systematic Table Notes:

1. Measurement locations are established on a triangular grid with randomly selected starting coordinates.

2. Measurement values are in units of dpm/1 00-cm 2.

3. SM-4 through SM-i1 are measured from the east side of the roof beam even with the southeast comer of the respective column.

Plum Brook Reactor Facility FSSR, Attachment 1 Appendix B Rev. 0, Page 36 of 72, Survey Unit RO-2-19 (Page 1 of 3)

ROLB 2nd Floor Class 2 Survey Unit East Wall I South Wall South Wall South Wall I West Wall Room 206 Room 205 Room 204 Rms. 204/205/206 Floor Survey Unit RO-2-19: ROLB 2nd Floor, Class 2 Areas X Co-ord (m) Y Co-ord (m) Label Value Type Notes 1.96 0.12 SM-1 Systematic Measured from east side of frame against 44 the glass 1.43 0.63 SM-2 Systematic Measured from northeast comer of Rm. 206

-36 inside of column C5 3.53 0.63 SM-3 204 Systematic Measured from southeast comer of Rm. 206

-0.24 0.63 SM-4 Systematic Measured from southwest comer of Rm.

482 204 5.90 2.93 SM-5 650 Systematic N/A 0.45 2.26 SM-6 161 Systematic N/A 1.23 1.66 SM-7 -73 Systematic N/A 2.70 1.66 SM-8 234 Systematic N/A 2.29 0.83 SM-9 2204 Systematic See survey maps for location points to

-0.27 0.97 SM-10 73 Systematic mas froc

-0.02 1.74 SM-I l 1810 Systematic Table Notes:

1. Measurement locations are located on a triangular grid with randomly selected starting coordinates.

2. Measurement values are in units of dpm/1 00-cm2.

3. All of the sample measurements are located by taking the lowest left-hand comer, of the surface on which they rest, as the origin. For example, the location of SM-3 is measured from the lower left hand comer of the survey unit (southeast comer of Room 206).

Plum Brook Reactor Facility FSSR, Attachment I Appendix B Rev. 0, Page 37 of 72, Survey Unit RO-2-19 (Page 2 of 3)

East Wall South Wall West Wk Floor Stair Hall Ceiling North Wall East Wall IWest Wk South Wall West Wal

Plum Brook Reactor Facility FSSR, Attachment I Appendix B Rev. 0, Page 38 of 72, Survey Unit RO-2-19 (Page 3 of 3) measure from this point measure from this comer Men's Locker Room measure from this comer

Plum Brook Reactor Facility FSSR, Attachment 1 Appendix B Rev. 0, Page 39 of 72, Survey Unit RO-2-20 (Page 1 of 4)

ROLB 2nd Floor Class 3 Survey Unit IS-Room 216 Room 217 Survey Unit .2-20: ROLB 2"0 Floor, Class 3 Areas X Co-ord (i) Y Co-ord (W) Label Value Type Notes 1.28 0.21 SM-1 Random Measured from south side of window

-85 ledge against the glass 0.66 2.09 SM-2 -42 Random Measured from the NE comer 0.02 0.02 SM-3 676 Random Measured from NW comer of floor

-0.75 1.38 SM-4 42 Random Measured from the SE comer of the room 0.93 0.71 SM-5 56 Random 1.78 1.61 SM-6 648 Random Measured from the SW comer 1.87 3.29 SM-7 697 Random Measured from the SW comer 2.28 3.54 SM-8 535 Random Measured from the SW comer

-0.25 2.05 SM-9 -169 Random Measured from the SE comer of the room

-2.28 2.35 SM-10 387 Random Measured from the SE comer of the room

-0.80 3.25 SM-I 1 465 Random Table Notes:

1. Measurement locations are selected on a random basis - Class 3 survey unit.

2. Measurement values are in units of dpm/100-cm 2.

3. See the Table notes for locating measurement points in each room. The notes indicate that there are different reference points in each room which are used as the origin. For example, the location of SM-4 and SM-5 are on different walls, but are measured from the same point: the southeast comer of Room 217.

Plum Brook Reactor Facility FSSR, Attachment 1 Appendix B Rev. 0, Page 40 of 72, Survey Unit RO-2-20 (Page 2 of 4)

I I Janitor Closet Cubby Hole 200A Fire Extinguisher East Wall n

North/South Hallway

Plum Brook Reactor Facility FSSR, Attachment 1 Appendix B Rev. 0, Page 41 of 72, Survey Unit RO-2-20 (Page 3 of 4)

Room 220 I

Room 221

Plum Brook Reactor Facility FSSR, Attachment I Appendix B Rev. 0, Page 42 of 72, Survey Unit RO-2-20 (Page 4 of 4)

MM&Na Room 203 I

Room 202

Plum Brook Reactor Facility FSSR, Attachment I Appendix B Rev. 0, Page 43 of 72, Survey Unit RO-2-21 ROLB 2nd Floor Class 3 Survey Unit Ceiling Secti-'i--" N a - south side vertical b - south side slant c - horizontal between beaxr d - north side slant e - north side vertical i

I SM46 4--

Survey Unit RO-2-21: ROLB 2nd Floor, Class 3 Areas (ceilings)

X Co-ord (im) Y Co-ord (m) Label Value Type Notes 1.04 N/A SM-1 824 Random North side 41st beam vertical surface 1.91 N/A SM-2 908 Random South side 11th beam vertical surface 1.99 N/A SM-3 563 Random North side 23r' beam 3.91 N/A SM-4 401 Random South side 40 beam slant 1.01 N/A SM-5 880 Random Between 38th & 39th beam 0.02 0.13 SM-6 817 Random Measured from NE comer of column H16 0.43 N/A SM-7 690 Random North side 14th beam slant 2.39 N/A SM-8 211 Random South side 27th beam vertical surface 2.79 N/A SM-9 500 Random South side 9th beam vertical surface 1.97 N/A SM-10 810 Random South side 39'h beam slant 2.70 N/A SM-1 1 873 Random South side 26' beam vertical surface Table Notes:

I. Measurement locations are selected on a random basis - Class 3 survey unit.

2. Measurement values are in units of dpm/l00-cm 2.

3. With the exception of SM-6, all other X co-ordinates are taken from the west side of the ceiling. With the exception of SM-6, no Y co-ordinates are given as the surfaces are very small so that the probe may just fit onto them. The "slant" refers to the short transition between the vertical beam and the horizontal ceiling.

Plum Brook Reactor Facility FSSR, Attachment I Appendix B Rev. 0, Page 44 of 72, Survey Unit RO-2-22 ROLB 2nd Floor Class 1 Survey Unit N

I W

Beam KI /14 Beami~ 1/G4 Beam F2/F4 a1m. - SM 1SM .4m1 M Beam F4/L4 3 Beam F4/F5 Beam J4/J173 Beam H4/H8 Survey Unit RO-2-22: ROLB 2nd Floor Ceiling Beams, Class 1 X Co-ord (m) Y Co-ord (m) Label Value Type Notes

-2.83 0.31 SM-I 832 Systematic Measured from where beam F4/F5 meets beam F4/L4 0.50 0.20 SM-2 664 Systematic Measured from where beam F4/L4 meets column L4 3.20 0.20 SM-3 657 Systematic 1.59 0.20 SM-4 642 Systematic Measured from where beam K1/K4 meets beam F4/L4 2.68 0.20 SM-5 343 Systematic Measured from where beam G1/G4 meets beam F4/L4 3.31 0.01 SM-6 482 Systematic Measured from where beam K 1/K4 meets beam F4/L4 7.98 0.01 SM-7 438 Systematic 0.17 0.13 SM-8 292 Systematic Measured from where beam G l/G4 meets beam F4/L4 4.83 0.13 SM-9 394 Systematic 4.50 0.33 SM-10 839 Systematic Measured from where beam F2/F4 meets beam F4/L4

-0.22 0.10 SM-11 467 Systematic Measured from where beam H4/H8 meets beam F4/L4 Table Notes:

1. Measurement locations are established on a triangular grid with randomly selected starting coordinates.

2

2. Measurement values are in units of dpm/100-cm .

3. See the Notes above for how to locate where sample measurements were taken. For example, SM-1 is measured from the north end of Beam F4/F5 (where it intersects Beam F4/L4) south 2.83 meters and then up (toward the ceiling) 0.31 meters.

Plum Brook Reactor Facility FSSR, Attachment 1 Appendix B Rev. 0, Page 45 of 72, Survey Unit RO-2-23 ROLB 2nd Floor Class 1 Survey Unit is

• 104 W.$1 11 El Dir-Eýl Survey Unit RO-2-23: ROLB 2nd Floor Ceiling Beams, Class 1, X Co-ord (m) Y Co-ord (m) Label Value Type Notes

-9.31 0.32 SM-I 533 Systematic

-5.30 0.32 SM-1 511 Systematic Measured from where beam C2/C8 meets

-5.30 0.32 SM-2 511 Systematic the north wall

-1.28 0.32 SM-3 504 Systematic _________________

-8.66 0.28 SM-4 401 Systematic Measured from where beam D2/D5 meets

-4.64 0.28 SM-5 387 Systematic the north wall

-0.63 0.28 SM-6 438 Systematic

-10.04 0.24 SM-7 482 Systematic Measured from where beam E2/E5 meets

-6.03 0.24 SM-8 307 Systematic the north wall

-2.02 0.24 SM-9 584 Systematic 0.73 0.17 SM-10 285 Systematic Measured from where beam B2/B8 meets 4.74 0.17 SM-11 175 Systematic the south wall Table Notes:

1. Measurement locations are established on a triangular grid with randomly selected starting coordinates.

2. Measurement values are in units of dpm/100-cm2.

3. See the Notes above for how to locate where sample measurements were taken. For example, SM-9 is measured from the north end of Beam E2/E5 (where it intersects with the north wall) south 9.31 meters and then up (toward the ceiling) 0.32 meters.

Plum Brook Reactor Facility FSSR, Attachment 1 Appendix B Rev. 0, Page 46 of 72, Survey Unit RO-3-1 ROLB Basement Class 1 Survey Unit- Areaway Room 5 Floor I

Survey Unit RO-3-1: ROLB Basement, Areaway (floor), Class I X Co-ord (m) Y Co-ord (m) Label Value Type Notes 0.98 0.54 SM-I 841 Systematic Note 3 3.86 0.54 SM-2 1265 Systematic Note 3 6.74 0.54 SM-3 932 Systematic Note 3 9.62 0.54 SM-4 894 Systematic Note 3 2.42 3.03 SM-5 1015 Systematic Note 3 5.30 3.03 SM-6 818 Systematic Note 3 8.18 3.03 SM-7 1091 Systematic Note 3 0.98 5.53 SM-8 1030 Systematic Note 3 3.86 5.53 SM-9 1159 Systematic Note 3 6.74 5.53 SM-10 1114 Systematic Note 3 9.62 5.53 SM-I1 1008 Systematic Note 3 Table Notes:

I. Measurement locations are established on a triangular grid with randomly selected starting coordinates.

2. Measurement values are in units of dpm/100-cm2.

3. All of the sample measurements are located by taking the lowest left-hand comer, of the surface on which they rest, as the origin. For example, the location of SM-I is measured from the south west comer of the Area Way (Room 5).

Plum Brook Reactor Facility FSSR, Attachment 1 Appendix B Rev. 0, Page 47 of 72, Survey Unit RO-3-2 ROLB Basement Class 1 Survey Unit-Vestibule, Mens Room, Janitor and Cold Test Area W. Floors, Lower Columns Column E5 Column D5 Column C5 0] 0 ObRIB obiý I from here

,ii9 Cold Test Area (Room 4 West)

Vestibule (Room 8) Men's (Room 9) Janitor (Room 10)

Survey Unit RO-3-2: ROLB 2no Floor, Class I Areas (floors)

X Co-ord (m) Y Co-ord (m) Label Value Type Notes 0.14 1.49 SM-1 265 Systematic Measured from NW comer of column D5 0.23 1.13 SM-2 886 Systematic N/A 2.98 1.13 SM-3 841 Systematic N/A 0.34 1.37 SM-4 500 Systematic N/A 1.72 0.98 SM-5 811 Systematic N/A 2.46 -1.14 SM-6 -106 Systematic 1.09 1.24 SM-7 98 Systematic 3.84 1.24 SM-8 712 Systematic See drawing above for location of origin 2.46 3.62 SM-9 636 Systematic 1.09 6.00 SM-10 621 Systematic 3.84 6.00 SM-il 985 Systematic Table Notes:

1. Measurement locations are established on a triangular grid with randomly selected starting coordinates.

2. Measurement values are in units of dpm/100-cm 2.

3. All of the sample measurements are located by taking the lowest left-hand comer, of the surface on which they rest, as the origin. For example, the location of SM-I is measured from the south west comer of the Vestibule (Room 8).

Plum Brook Reactor Facility FSSR, Attachment I Appendix B Rev. 0, Page 48 of 72, Survey Unit RO-3-3 ROLB Basement Class 1 Survey Unit, Cold Test Area (center) Floor F *N" r-i Survey Unit RO-3-3: ROLB Basement, Cold Test Area, Center (floor), Class I X Co-ord (m) Y Co-ord (im) Label Value Type Notes 1.85 0.23 SM-1 1250 Systematic Note 3 4.63 0.23 SM-2 1121 Systematic Note 3 0.46 2.63 SM-3 727 Systematic Note 3 3.24 2.63 SM-4 803 Systematic Note 3 6.02 2.63 SM-5 871 Systematic Note 3 1.85 5.04 SM-6 735 Systematic Note 3 4.63 5.04 SM-7 962 Systematic Note 3 0.46 7.44 SM-8 735 Systematic Note 3 3.24 7.44 SM-9 894 Systematic Note 3 6.02 7.44 SM-10 924 Systematic Note 3 1.85 9.85 SM-11 1061 Systematic Note 3 4.63 9.85 SM-12 788 Systematic Note 3 Table Notes:

I. Measurement locations are established on a triangular grid with randomly selected starting coordinates.

2. Measurement values are in units of dpm/100-cm2.

3. All of the sample measurements are located by taking the lowest left-hand comer of the surface on which they rest as the origin. For example, SM-I is measured from the south west comer of the Cold Test Area (center).

Plum Brook Reactor Facility FSSR, Attachment I Appendix B Rev. 0, Page 49 of 72, Survey Unit RO-3-4 ROLB Basement Class 1 Survey Unit, Cold Test Area (East) and Vault Floors Survey Unit RO-3-4: ROLB Basement, Cold Test Area (East) & Vault (floors), Class I X Co-ord (m) Y Co-ord (m) Label Value Type Notes 0.43 0.95 SM-1 927 Systematic N/A 3.61 0.95 SM-2 536 Systematic N/A 2.02 3.71 SM-3 753 Systematic N/A

-3.52 0.55 SM-4 783 Systematic

-0.34 0.55 SM-5 370 Systematic

-5.12 3.31 SM-6 587 Systematic

-1.93 3.31 SM-7 399 Systematic Measured from southeast comer

-3.52 6.07 SM-8 565 Systematic of Cold Test Area (Room 4)

-0.34 6.07 SM-9 710 Systematic

-5.12 8.83 SM-10 725 Systematic

-1.93 8.83 SM- 11 746 Systematic Table Notes:

1. Measurement locations are established on a triangular grid with randomly selected starting coordinates.

2. Measurement values are in units of dpm/l 100-cm2.

3. Unless otherwise noted, all sample measurements are located by taking the lowest left-hand comer, of the surface on which they rest, as the origin. For example, the location of SM-1 is measured from the south west comer of the Vault (Room 17).

Plum Brook Reactor Facility FSSR, Attachment I Appendix B Rev. 0, Page 50 of 72, Survey Unit RO-3-5 ROLB Basement Class 1 Survey Unit, Sump Room Floor, sumps and Elevator Sump 0 0 0

LIIZ 0 [--1o 0 0*ý Elevator Sump Survey Unit RO-3-5: ROLB Basement, Sump Room, Sumps & Elevator Sump, Class I X Co-ord (mi) Y Co-ord (mi) Label Value Type Notes 0.44 1.00 SM-I 826 Systematic Note 3 3.18 1.00 SM-2 803 Systematic Note 3 1.82 -0.34 SM-3 323 Systematic Note 3 1.81 3.37 SM-4 765 Systematic Note 3 4.54 3.37 SM-5 902 Systematic Note 3 0.44 5.74 SM-6 674 Systematic Note 3 3.18 5.74 SM-7 1008 Systematic Note 3 1.81 8.10 SM-8 856 Systematic Note 3 4.54 8.10 SM-9 977 Systematic Note 3 0.44 10.47 SM-10 1045 Systematic Note 3 3.18 10.47 SM-11 568 Systematic Note 3 Table Notes:

1. Measurement locations are established on a triangular grid with randomly selected starting coordinates.

2. Measurement values are in units of dpm/100-cm 2.

3. Unless otherwise noted, all sample measurements are located by taking the lowest left-hand comer, of the surface on which they rest, as the origin. For example, the location of SM-I is measured from the south west comer of the Sump Room (Room 6). In the map shown above, the sump walls are "unfolded" and represented as rectangles. To locate SM-3, the upper left comer represents true north. From this point, measure clockwise 1.82 meters; then measure 0.34 meters from the floor elevation down the side of the sump.

Plum Brook Reactor Facility FSSR, Attachment 1 Appendix B Rev. 0, Page 51 of 72, Survey Unit RO-3-6 ROLB Basement Class 1 Survey Unit, Sump Room, Men's Room &Janitor Closet - Lower Walls Janitor (Room 10)

North Wall East South Wall West Men's Room (Room 9) ft-Sump Room (Room 6) 1131111-91 West Wall North Wall East Wall South Wall South Wall West Wall North Wall East Wall Survey Unit RO-3-6: ROLB Basement, Lower Walls, Class I X Co-ord (m) Y Co-ord (m) Label Value Type Notes 1.66 0.36 SM-I 129 Systematic South wall, Room 6 1.00 0.36 SM-2 540 Systematic West wall, Room 6 5.04 0.36 SM-3 395 Systematic West wall, Room 6 9.08 0.36 SM-4 290 Systematic West wall, Room 6 2.58 0.36 SM-5 194 Systematic North wall, Room 6 1.94 0.36 SM-6 355 Systematic East wall, Room 6 5.99 0.36 SM-7 339 Systematic East wall, Room 6 10.03 0.36 SM-8 121 Systematic East wall, Room 6 1.37 1.22 SM-9 1331 Systematic East wall, Room 9 2.37 1.22 SM-10 121 Systematic South wall, Room 9 0.90 1.85 SM-11 169 Systematic East wall, Room 10 Table Notes:

1. Measurement locations are established on a triangular grid with randomly selected starting coordinates.

2. Measurement values are in units of dpm/100-cm 2.

3. Unless otherwise noted, all sample measurements are located by taking the lowest left-hand comer, of the surface on which they rest, as the origin. For example, the location of SM-I is measured from the south east comer of the Sump Room (Room 6).

Plum Brook Reactor Facility FSSR, Attachment I Appendix B Rev. 0, Page 52 of 72, Survey Unit RO-3-7 ROLB Basement Class I Survey Unit, Area Way and Vault Lower Walls Vault (Room 17)

I North Wbi East WaIll South Wal fl n West Wall Door Frame Door Sides nri West Opening East Opening I North Wall East Wall I South Wall I West Wall I Room 5 Area Way Survey Unit RO-3-7: ROLB Basement Area Way & Vault (lower walls) Class I X Co-ord (im) Y Co-ord (mi) Label Value Type Notes 2.92 1.90 SM-1 599 Systematic Vault, North Wall 2.08 1.90 SM-2 967 Systematic Vault, East Wall 0.84 1.90 SM-3 703 Systematic Vault, South Wall 3.17 1.90 SM-4 1375 Systematic Vault, West Wall 0.62 1.51 SM-5 835 Systematic Area Way, East Wall 3.80 1.51 SM-6 282 Systematic Area Way, East Wall 0.97 1.51 SM-7 769 Systematic Area Way, South Wall 4.15 1.51 SM-8 1177 Systematic Area Way, South Wall 7.32 1.51 SM-9 1013 Systematic Area Way, South Wall 10.50 1.51 SM-10 368 Systematic Area Way, South Wall 3.07 1.51 SM-I 480 Systematic Area Way, West Wall Table Notes:

1. Measurement locations are established on a triangular grid with randomly selected starting coordinates.

2. Measurement values are in units of dpm/100-cm 2.

3. All static measurement sample points are located by taking the lowest left-hand comer, of the surface on which they rest, as the origin. For example, the location of SM-I is measured from the northwest comer of the Vault (Room 17).

Plum Brook Reactor Facility FSSR, Attachment 1 Appendix B Rev. 0, Page 53 of 72, Survey Unit RO-3-8 ROLB Basement Class 1Survey Unit Cold Test Area and Vestibule Lower Walls Vestikule

[West I North IEast I South I Cold Test Area West I North East South I West I Survey Unit RO-3-8: ROLB Basement Cold Test Area & Vestibule (lower walls),Class I X Co-ord (m) Y Co-ord (m) Label Value Type Notes 0.51 1.90 SM-1 120 Systematic West Wall - Room 4 3.69 1.90 SM-2 407 Systematic 5.43 1.90 SM-3 472 Systematic 8.61 1.90 SM-4 213 Systematic North Wall - Rom 4 11.79 1.90 SM-5 167 Systematic 1.15 1.90 SM-6 306 Systematic East Wall measured from 4.33 1.90 SM-7 19 Systematic south side of Column B5 0.68 1.90 SM-8 93 Systematic 3.86 1.90 SM-9 296 Systematic South Wall - Room 4 13.39 1.90 SM-10 694 Systematic 1.46 0.29 SM-11 432 Systematic South Wall - Room 8 Table Notes:

1. Measurement locations are established on a triangular grid with randomly selected starting coordinates.

2. Measurement values are in units of dpm/100-cm2.

3. Unless otherwise noted, all sample measurements are located by taking the lowest left-hand corner, of the surface on which they rest, as the origin. For example, the location of SM-6 is measured from the south side of Column B5 on the East Wall of the Cold Test Area (Room 4).

Plum Brook Reactor Facility FSSR, Attachment I Appendix B Rev. 0, Page 54 of 72, Survey Unit RO-3-9 ROLB Basement Class 1 Survey Unit, Sump Room Ceiling P.

S M------ C C

--- SM

• C C

C C

C C

C C

[

[

[

[

[

[

Survey Unit RO-3-9: ROLB Basement, Sump Room (ceiling), Class I X Co-ord (mi) Y Co-ord (m) Label Value Type Notes 0.50 See Note 3 SM-I 621 Systematic Between beams I and 2 on the 0.92 See Note 3 SM-2 636 Systematic horizontal surface 2.01 See Note 3 SM-3 523 Systematic Beam 4, horizontal surface 0.50 See Note 3 SM-4 371 Systematic Beam 6, north slanted surface 0.92 See Note 3 SM-5 273 Systematic 2.01 See Note 3 SM-6 508 Systematic Beam 9, south slanted surface 0.50 See Note 3 SM-7 394 Systematic Beam 11, north vertical surface 0.92 See Note 3 SM-8 356 Systematic 2.01 See Note 3 SM-9 Systematic Between beams 13 and 14 on the 659 horizontal surface 0.50 See Note 3 SM-10 295 Systematic Beam 16, north vertical surface 0.92 See Note 3 SM-11 538 Systematic Table Notes:

1. Measurement locations are established on a triangular grid with randomly selected starting coordinates.

2. Measurement values are in units of dpm/l00-cm2.

3. In lieu of y-coordinates, beam numbers are provided for SM-1 through SM-1 1. Lateral or transverse beams have been marked in the field to aid in their being located. Use the Ceiling Section (provided on the map) as a guide to locating the correct portion of the transverse beam to survey.

Plum Brook Reactor Facility FSSR, Attachment 1 Appendix B Rev. 0, Page 55 of 72, Survey Unit RO-3-10 ROLB Basement Class 1 Survey Unit SM-Il Vestibule, Men's Room, Janitor Ceil ff1T'

[

~E Sump Room Upper Walls South Wall I West Wall North Wall I East Wall Survey Unit RO-3-10: ROLB Basement (ceilings), Class 1 X Co-ord (mi) Y Co-ord (mi) Label Type Notes 0.22 2.67 SM-1 264 Systematic Sump Room, South Wall 3.42 2.67 SM-2 306 Systematic 1.92 2.67 SM-3 368 Systematic 5.12 2.67 SM-4 -56 Systematic Sump Room, West Wall 8.32 2.67 SM-5 313 Systematic 1.00 2.67 SM-6 257 Systematic Sump Room, North Wall 4.20 2.67 SM-7 160 Systematic 2.70 2.67 SM-8 222 Systematic Sump Room, East Wall 5.91 2.67 SM-9 222 Systematic 1.35 N/A SM-10 Systematic Between beams 21 and 22 on

_ _ 597 horizontal surface 1.35 N/A SM-I1 Systematic Between beams 26 and 27 on 1 457 horizontal surface Table Notes:

I. Measurement locations are established on a triangular grid with randomly selected starting coordinates.

2. Measurement values are in units of dpm/100-cm 2.

3. Unless otherwise noted, all sample measurements are located by taking the lowest left-hand comer, of the surface on which they rest, as the origin. For example, the location of SM-6 is measured from the north west comer in the Sump Room (Room 6). In lieu of y-coordinates, beam numbers are provided for both SM-10 and SM-I 1.

Lateral or transverse beams have been marked in the field to aid in their being located.

Plum Brook Reactor Facility FSSR, Attachment 1 Appendix B Rev. 0, Page 56 of 72, Survey Unit RO-3-11 ROLB Basement Class 1 Survey Unit, Men's Room, Janitor Closet and Vault Upper Walls &Vault Ceiling measure fromhere measuretmber Ceiling North I East South I West Men's Room Janitor I West I North I East I South North I I South I I East West Survey Unit RO-3-1 1: ROLB Basement (ceilings), Class I X Co-ord (mi) Y Co-ord (mi) Label Value Type Notes 0.57 2.22 SM-1 651 Systematic Men's Room West Wall 0.55 2.22 SM-2 230 Systematic Men's Room North Wall 0.75 2.22 SM-3 1559 Systematic Men's Room East Wall 0.78 2.22 SM-4 1341 Systematic Men's Room South Wall 1.55 2.22 SM-5 342 Systematic Janitor North Wall 0.35 2.22 SM-6 98 Systematic Janitor South Wall 0.60 2.22 SM-7 315 Systematic Janitor West Wall 2.86 1.84 SM-8 1059 Systematic Vault Ceilingl 1.25 0.40 0.27 0.57 SM-9 SM-1 782 703 Systematic Systematic Vault VaultUpper Wall Ceiling

-0.12 0.57 SM-11 381 Systematic Vault Ceiling Table Notes:

1. Measurement locations are established on a triangular grid with randomly selected starting coordinates.

2. Measurement values are in units of dpm/100-cm 2.

3. Unless otherwise noted, all sample measurements are located by taking the lowest left-hand comer, of the surface on which they rest, as the origin. For example, the location of SM-1 I is measured from the south side, against the east wall of the Vault Ceiling.

Plum Brook Reactor Facility FSSR, Attachment I Appendix B Rev. 0, Page 57 of 72, Survey Unit RO-3-12 ROLB Basement Class 1 Sur\ey Unit, Vestibule Upper Walls &Area Way Ceiling Vestibule ii I West I North East South Area Way Ceiling biR3 IED *NE9 *NY3 Survey Unit RO-3-12: ROLB Basement, Class 1 X Co-ord (m) Y Co-ord (m) Label Value Type Notes 0.06 1.00 SM-1 -43 Systematic 3.05 1.00 SM-2 268 Systematic 6.04 1.00 SM-3 239 Systematic 9.03 1.00 SM-4 -399 Systematic 1.56 3.59 SM-5 -167 Systematic Area Way Ceiling 4.55 3.59 SM-6 174 Systematic 7.54 3.59 SM-7 -174 Systematic 10.53 3.59 SM-8 72 Systematic 1.56 1.76 SM-9 232 Systematic Vestibule North Wall 0.23 1.76 SM- 10 420 Systematic Vestibule East Wall 1.06 1.76 SM-11 659 Systematic Vestibule South Wall Table Notes:

1. Measurement locations are established on a triangular grid with randomly selected starting coordinates.

2. Measurement values are in units of dpm/100-cm 2.

3. Unless otherwise noted, all sample measurements are located by taking the lowest left-hand comer, of the surface on which they rest, as the origin. For example, the location of SM-I is measured from the south west comer of the Area Way Ceiling.

Plum Brook Reactor Facility FSSR, Attachment I Appendix B Rev. 0, Page 58 of 72, Survey Unit RO-3-13 ROLB Basement Class 1 Surey Unit, Area Way Upper Walls West Openning East Openning North Wall East Wall South Wall West Wall Survey Unit RO-3-13: ROLB Basement, Area Way (upper walls), Class I X Co-ord (m) Y Co-ord (m) Label Value Type Notes 1.07 4.52 SM-1 629 Systematic 4.05 4.52 SM-2 766 Systematic 7.03 4.52 SM-3 887 Systematic North Wall 10.01 4.52 SM-4 427 Systematic 2.40 4.52 SM-5 500 Systematic 5.38 4.52 SM-6 774 Systematic 2.33 4.52 SM-7 605 Systematic 5.31 4.52 SM-8 806 Systematic South Wall 8.29 4.52 SM-9 508 Systematic 0.66 4.52 SM-10 476 Systematic West Wall 3.64 4.52 SM-11 266 Systematic Table Notes:

1. Measurement locations are established on a triangular grid with randomly selected starting coordinates.

2. Measurement values are in units of dpm/100-cm 2.

3. Unless otherwise noted, all sample measurements are located by taking the lowest left-hand comer, of the surface on which they rest, as the origin. For example, the location of SM-7 is measured from the south east corner of the Area Way.

Plum Brook Reactor Facility FSSR, Attachment 1 Appendix B Rev. 0, Page 59 of 72, Survey Unit RO-3-14 ROLB Basement Class 1 Surwey Unit, Cold Test Nea Upper Walls Column E5 Column D5 Column C5 SM-2and SM-3musure fromhere SM-8 and SM-9measurefromhere West Wall I North Wall EastW rail I South Wall Survey Unit RO-3-14: ROLB Basement, Cold Test Area & Columns (upper walls), Class 1 X Co-ord (m) Y Co-ord (mi) Label Value Type Notes 1.45 2.29 SM-1 121 Systematic 2.105 2.29 SM-2 -8 Systematic West Wall 6.78 2.29 SM-3 274 Systematic 3.60 2.29 SM-4 113 Systematic 8.23 2.29 SM-5 234 Systematic North Wall 12.85 2.29 SM-6 32 Systematic 1.81 2.29 SM-7 210 Systematic East Wall 1.96 2.29 SM-8 -105 Systematic East Wall - measured from 6.58 2.29 SM-9 153 Systematic south side of column B5 4.37 2.29 SM-10 -113 Systematic South Wall 13.61 2.29 SM- 11 435 Systematic S Table Notes:

1. Measurement locations are established on a triangular grid with randomly selected starting coordinates.

2. Measurement values are in units of dpm/100-cm 2.

3. Unless otherwise noted, all sample measurements are located by taking the lowest left-hand comer, of the surface on which they rest, as the origin. For example, the location of SM-I is measured from the southwest corner of the Cold Test Area (Room 4).

Plum Brook Reactor Facility FSSR, Attachment I Appendix B Rev. 0, Page 60 of 72, Survey Unit RO-3-15 ROLB Basement Class 1 Surwey Unit Cold Test Area North Ceiling Ceiling Section > E 1 2 3 4 5 6 7 8 la e b d c~

M M MZ7MM A MV MMC M7 iM 7WM it MAMM1 77A M7M MMIA a - east side vertical K east side slant c - horizontal between beams Above North Wall of Cold Test Area (Room 4) d - west side slant e - west side vertical

'SM-i 'SM-I 3M-41 ISM-I S3M- ISM-7 ISM-4 SM-" 'SM-i" 'SM-il' Frist Row of North/South Ceiling Beams Survey Unit RO-3-15: ROLB Basement Cold Test Area, North (ceiling), Class I X Co-ord (m) Y Co-ord (m) Label Value Type Notes

-0.12 -0.19 SM-l 690 Systematic See below N/A 0.15 SM-2 460 Systematic Beam 1, east vertical N/A 0.15 SM-3 526 Systematic Between beams 3 and 4, horizontal surface N/A 0.15 SM-4 460 Systematic Beam 6,horizontal surface N/A 0.15 SM-5 302 Systematic Between beams 8 and 9, horizontal surface N/A 0.15 SM-6 457 Systematic Beam 11, west vertical N/A 0.15 SM-7 513 Systematic Beam 13, east slant N/A 0.15 SM-8 394 Systematic Beam 16, west vertical N/A 0.15 SM-9 328 Systematic Beam 18, east vertical N/A 0.15 SM-10 657 Systematic Beam 21, west slant N/A 0.15 SM-11 144 Systematic Beam 23, horizontal surface Table Notes:

1. Measurement locations are established on a triangular grid with randomly selected starting coordinates.

2. Measurement values are in units of dpm/l00-cm 2.

3. The location of SM-I is measured 0.12m north off the 1st floor hallway, then down the floor opening 0.19 m. This measurement location is just above the highest point of the ceiling in the Cold Test Area (Room 4).

4. For the remainder of the static measurements, in lieu of x-coordinates, beam numbers are provided.

Beams have been marked in the field to aid in locating them. Use the Ceiling Section (provided on the map) as a guide to locating the correct portion of the beam to survey. All static measurements are taken from the south end of the beam.

Plum Brook Reactor Facility FSSR, Attachment I Appendix B Rev. 0, Page 61 of 72, Survey Unit RO-3-16 ROLB Basement Class 1 Survey Unit, Cold Test Area Ceiling (North Central)

Ceiling Section >E 9 10 11 12 13 14 15 a - east side vertical II = 1] = = = 0 b - east side slant c - horizontal between beams Column C5 Column B5 d - west side slant Column E5 Column D5 e - west side vertical S1 SM S HOMEEI i I -IV ---M I11§ 111

-... 1111111 111111 Survey Unit RO-3-16: ROLB Basement, Cold Test Area, North Central (ceiling), Class 1 X Co-ord (m) Y Co-ord (m) Label Type Value Notes

-0.19 -0.17 SM-1 Systematic 308 Note 3 N/A -1.00 SM-2 Systematic 476 Beam 1, east vertical N/A -1.00 SM-3 Systematic 347 Beam 4, west vertical N/A -1.00 SM-4 Systematic 613 Beam 6, east slant N/A -1.00 SM-5 Systematic 274 Beam 9, horizontal surface N/A -1.00 SM-6 Systematic 379 Between beams 1I and 12, horizontal surface N/A -1.00 SM-7 Systematic 508 Beam 14, east vertical N/A -1.00 SM-8 Systematic 460 Beam 17, west slant N/A -1.00 SM-9 Systematic 476 Beam 19, east vertical N/A -1.00 SM-10 Systematic 540 Beam 22, west vertical N/A -1.00 SM-11 Systematic 524 Between beams 24 and 25, horizontal surface Table Notes:

1. Measurement locations are established on a triangular grid with randomly selected starting coordinates.

2. Measurement values are in units of dpm/1 00-cm 2.

3. SM-I is measured 0.19 meters south off the It floor hallway, then down into the opening 0.17 meters.

For the remainder of the static measurements, beam numbers are provided in lieu of x-coordinates.

Beams have been marked in the field to aid in locating them. Use the Ceiling Section (provided on the map) as a guide to locating measurement points. All static measurements are taken 1.00 meters from the north end of the beam.

Plum Brook Reactor Facility FSSR, Attachment I Appendix B Rev. 0, Page 62 of 72, Survey Unit RO-3-17 ROLB Basement Class 1 Survey Unit, Cold Test Area (South Central) Ceiling Ceiling Section > E

~a eb d c a - east side vertical b - east side slant c - horizontal between beams d - west side slant e - west side vertical fIWl 1 WIWIH 11I1II IIIM 111IIII IIIA I1I;N111 1111 TW IIM Survey Unit RO-3-17: ROLB Basement Cold Test Area, South Central (ceiling), Class 1 X Co-ord (mi) Y Co-ord (m) Label Value Type Notes Note 3 0.90 SM-1 484 Systematic Beam 2, east slant Note 3 0.90 SM-2 565 Systematic Between beams 4 and 5, horizontal surface Note 3 0.90 SM-3 468 Systematic Beam 7, west vertical Note 3 0.90 SM-4 306 Systematic Beam 9, horizontal surface Note 3 0.90 SM-5 581 Systematic Beam 11, east vertical Note 3 0.90 SM-6 194 Systematic Between beams 13 and 14, horizontal surface Note 3 0.90 SM-7 508 Systematic Between beams 15 and 16, horizontal surface Note 3 0.90 SM-8 339 Systematic Beam 18, west vertical Note 3 0.90 SM-9 234 Systematic Beam 20, horizontal surface Note 3 0.90 SM-10 226 Systematic Beam 22, east vertical Note 3 0.90 SM-I 1 645 Systematic Between beams 24 and 25, horizontal surface Table Notes:

I. Measurement locations are established on a triangular grid with randomly selected starting coordinates

2. Measurement values are in units of dpm/1 00-cm.

3. Beam numbers are provided for SM-I through SM-Il In lieu of x-coordinates. Lateral or transverse beams have been marked in the field to aid in locating them. The Ceiling Section (on the map) is provided as an aid in locating the measurement points. All SM-1 through SM-1 I static points are 0.90 meters north from the south end of the smaller, north/south, lateral or transverse ceiling beams.

Plum Brook Reactor Facility FSSR, Attachment 1 Appendix B Rev. 0, Page 63 of 72, Survey Unit RO-3-18 ROLB Basement Class 1 Survey Unit, Cold Test Area Ceiling (South)

Ceiling Section - E

ýae 4be d~f c~

a - east side vertical b - east side slant c - horizontal between beams d - west side slant e - west side vertical S gil l 1 11 1 1 ll 1191 L 171171171171171 171171171 Survey Unit RO-3-18: ROLB Basement, Cold Test Area, South (ceiling), Class I X Co-ord (m) Y Co-ord (m) Label Value Type Notes See Note 3 0.67 SM-1 419 Systematic Between beams 1 and 2, horizontal surface See Note 3 0.67 SM-2 234 Systematic Beam 4, west vertical surface See Note 3 0.67 SM-3 452 Systematic Beam 6, east vertical surface See Note 3 0.67 SM-4 524 Systematic Between beams 8 and 9, horizontal surface See Note 3 0.67 SM-5 282 Systematic Beam 11, horizontal surface See Note 3 0.67 SM-6 Systematic Between beams 13 and 14, horizontal 452 surface See Note 3 0.67 SM-7 573 Systematic Beam 16, west vertical surface See Note 3 0.67 SM-8 234 Systematic Beam 18, east vertical surface See Note 3 0.67 SM-9 Systematic Between beams 20 and 21, horizontal 0 surface See Note 3 0.67 SM- 10 169 Systematic Beam 23 horizontal surface See Note 3 0.67 SM-11 Systematic Between beam 25 and the Elevator 444 1 Machinery west wall, horizontal surface Table Notes:

1. Measurement locations are established on a trian-gular grid with randomly selected starting coordinates.

2. Measurement values are in units of dpm/100-cm.

3. In lieu of x-coordinates, beam numbers are provided for SM-1 through SM-1 1. Lateral or transverse beams have been marked in the field to aid in locating them. A diagram of the Ceiling Section is shown on the map as a guide to locating measurement points. All SM-I through SM-I I static points are 0.67 meters north from the south end of the smaller, north/south, lateral or transverse ceiling beams.

Plum Brook Reactor Facility FSSR, Attachment I Appendix B Rev. 0, Page 64 of 72, Survey Unit RO-3-25 ROLB Basement Class 2 Survey Unit Designated Floors, Elevator Shaft Walls and Ceiling Room 13A Elevator Ceiling Elevator Shaft D Survey Unit RO-3-25: ROLB Basement, Designated Areas (floors, walls & ceilings), Class 2 X Co-ord (m) Y Co-ord (mi) Label Value Type Notes 6.06 4.50 SM- 1 768 Systematic N/A 1.43 0.68 SM-2 523 Systematic N/A 2.37 10.89 SM-3 442 Systematic N/A 7.15 0.56 SM-4 790 Systematic N/A 14.53 0.56 SM-5 536 Systematic N/A 0.10 1.27 SM-6 Systematic On the east wall, 0.1Om south of the 411 north wall, 1.72m above a line parallel to the bottom of the elevator door 6.05 2.26 SM-7 362 Systematic N/A 3.47 6.95 SM-8 819 Systematic N/A 10.84 6.95 SM-9 891 Systematic N/A 2.48 6.95 SM-10 862 Systematic N/A 2.29 -1.39 SM-11 652 Systematic Measured from the northwest comer of Calibration Rooml 3A Table Notes:

1. Measurement locations are established on a triangular grid with randomly selected starting coordinates.

2. Measurement values are in units of dpm/100-cm 2.

3. All of the sample measurements are located by taking the lowest left-hand corner, of the surface on which they rest, as the origin. For example, the location of SM-I is measured from the south west comer of the Building Service Area (Room 11).

Plum Brook Reactor Facility FSSR, Attachment I Appendix B Rev. 0, Page 65 of 72, Survey Unit RO-3-26 ROLB Basement Class 2 Survey Unit, Lower & Upper Walls of Designated Roooms Building Service Area (Room II) Columns II WestWall North Wall East Will South Wall I J4 H4 Counting Room (Room 12) Stair Hall (Room 1) Columns NorhoWall I ast I South Wall I We I I South Wout N oh I Fas I II J6 H6 Electronic Shop (Room 13) Elevatonr Column lachinery (Room 3)

IM Norh I

-E-at IS.h I Wuil Noth hast I E South WIat I

P7 Tool Crib / General Shop Area (Rooms 14/15)

Calibration (Room 13A)

I N~oh I East I South I West I Teleohone Exchange (Room 16)

Passage- l In I W-11 I SouthlI E-I NI I WoWall T1Nort Ih ,aut W.]I South Survey Unit RO-3-26: ROLB Basement, Designated Areas (lower & upper walls), Class 2 X Co-ord (m) Y Co-ord (m) Label Value Type Notes 6.31 0.21 SM-1 70 Systematic Room 16, west wall 4.78 0.21 SM-2 310 Systematic Room 16, east wall 1.27 0.12 SM-3 620 Systematic Rm. 14/15, west wall 5.38 0.12 SM-4 113 Systematic Rm. 14/15, north wall 2.22 0.12 SM-5 -77 Systematic Rm. 14/15, east wall 0.06 0.12 SM-6 85 Systematic West side of column D4 0.20 0.12 SM-7 352 Systematic West side of column F4 4.30 3.01 SM-8 859 Systematic Room 12, north wall 1.51 3.01 SM-9 500 Systematic Room 12, south wall 2.72 3.01 SM-10 908 Systematic Room 12, west wall 3.59 2.66 SM-11 831 Systematic Room 13, east wall Table Notes:

1. Measurement locations are established on a triangular grid with randomly selected starting coordinates.

2. Measurement values are in units of dpm/100-cm 2.

3. All of the sample measurements are located by taking the lowest left-hand corner, of the surface on which they rest, as the origin. For example, the location of SM-1 is measured from the southwest comer of the Telephone Exchange (Room 16).

Plum Brook Reactor Facility FSSR, Attachment 1 Appendix B Rev. 0, Page 66 of 72, Survey Unit RO-3-27 (Page 1 of 3)

ROLB Basement Class 2 Survey Unit, Rooms11-13A, Ceilings Room 13A Room 13 I

eiral t

,--I

Plum Brook Reactor Facility FSSR, Attachment I Appendix B Rev. 0, Page 67 of 72, Survey Unit RO-3-27 (Page 2 of 3)

ROLB Basement Class 2 Survey Unit, Rooms 15, 16 Ceilings Stair Hall Room 3 North 1 2 Be Central Si South an

Plum Brook Reactor Facility FSSR, Attachment 1 Appendix B Rev. 0, Page 68 of 72, Survey Unit RO-3-27 (Page 3 of 3)

Survey Unit RO-3-27: ROLB Basement, Room 15, 16 (ceilings), Class 2 X Co-ord (m) Y Co-ord (m) Label Value Type Notes 1.76 0.13 SM-1 915 Systematic Just above the south wall N/A N/A SM-2 Systematic Between beams 18 & 19, against the 437 east wall 1.76 N/A SM-3 310 Systematic Beam 32, south vertical N/A N/A SM-4 Systematic Beam 33, south slant, against the east 500 wall 0.15 -0.28 SM-5 359 Systematic Southeast of beam penetration 21 0.13 N/A SM-6 641 Systematic Beam 5, north vertical 3.87 0.08 SM-7 570 Systematic N/A 3.19 0.08 SM-8 965 Systematic N/A N/A -0.22 SM-9 394 Systematic Beam 1, west vertical 0.20 0.16 SM-10 1099 Systematic N/A N/A 1.19 SM-11 437 Systematic Beam 32, east vertical Table Notes:

1. Measurement locations are established on a triangular grid with randomly selected starting coordinates.

2. Measurement values are in units of dpm/100-cm2.

3. Unless otherwise noted, sample measurements are located by taking the lowest left-hand comer, of the surface on which they rest, as the origin. For example, the location of SM-7 is measured from the southwest comer of the Counting Room (Room 12).

4. In lieu of x-coordinates, beam numbers are provided for SM-2, SM-4, SM-9. and SM-11. Lateral or transverse beams have been marked in the field to aid in locating them. In lieu of y coordinates, beam numbers are provided for SM-2 through SM-4 and SM-6.The Ceiling Section (see the maps on page 66 and 67) is provided as a guide to locating the measurement points on the transverse ceiling beams.

Plum Brook Reactor Facility FSSR, Attachment 1 Appendix B Rev. 0, Page 69 of 72, Survey Unit RO-3-28A ROLB Basement Class 3 Survey Unit, Crawl Space Walls and Ceiling Ceiling (W

. . . . . . . . . .. . . . . . . . . . . . N

. NW..

Ceiling (West C Cohanns SM ~

Ceiling (Cent J10 J12 Ceiling (East J14 H14 IIN Ceiing(E, oS-M SM J16 H16 15,-M I West Wall North Wall SM- SM North East Wall South Wall J17 H17 East Wall Survey Unit RO-3-28A: ROLB Basement Crawl Space (walls & ceiling), Class 3 X Co-ord (m) Y Co-ord (m) Label Value Type Notes 1.51 0.28 SM-1 472 Random North from Column H16 0.52 0.77 SM-2 500 Random North from Column J15 3.15 0.47 SM-3 549 Random North from Column J15 16.89 -0.28 SM-4 908 Random 27.98 -1.30 SM-5 1140 Random West Wall 7.63 -0.21 SM-6 697 Random 8.75 -0.03 SM-7 852 Random East Wall 8.57 -0.77 SM-8 479 Random South Wall 19.65 -0.25 SM-9 331 Random East Wall 0.14 -0.68 SM-10 775 Random West Side of Colum J17 0.40 -0.54 SM-11 732 Random South Side of Column J10 Table Notes:

1. Measurement locations are selected on a random basis - Class 3 survey unit.

2. Measurement values are in units of dpm/100-cm 2.

3. The y-coordinates of SM-4 through SM-1I are measured from the top of the wall or column because the floor is not consistently level.

Plum Brook Reactor Facility FSSR, Attachment 1 Appendix B Rev. 0, Page 70 of 72, Survey Unit RO-3-28B ROLB Basement Class 3 Survey Unit, Crawl Space Soil Survey Unit RO-3-28B: ROLB Basement Crawl Space (soil), Class 3 X Co-ord (m) Y Co-ord (m) Label Value Type Notes 5.93 19.01 SM-1 <MDA Random N/A 3.01 30.60 SM-2 <MDA Random N/A 11.39 3.67 SM-3 <MDA Random N/A 5.57 8.05 SM-4 0.118 Random N/A 6.28 31.28 SM-5 <MDA Random N/A 5.11 21.63 SM-6 <MDA Random N/A 0.39 9.70 SM-7 <MDA Random N/A 9.15 0.68 SM-8 <MDA Random N/A 3.47 20.07 SM-9 <MDA Random N/A 8.74 3.30 SM-10 <MDA Random N/A 0.90 24.32 SM-1 I <MDA Random N/A Table Notes:

1. Measurement locations are selected on a random basis - Class 3 survey unit.

2. Measurement values are in units of pCi/g Cs-137.

3. All measurements are made from the extreme southwest comer of the crawl space.

Plum Brook Reactor Facility FSSR, Attachment 1 Appendix B Rev. 0, Page 71 of 72, Survey Unit RO-4-1 ROLB Exterior Class 2 Survey Unit, Building Roof Nj X Coord (ft) Y Coord (ft) Label Value Type Notes 5.9 5.6 SM-1 309 Systematic N/A 0.4 15.2 SM-2 138 Systematic N/A 11.4 15.2 SM-3 24 Systematic N/A 5.9 24.7 SM-4 -163 Systematic N/A 0.4 34.2 SM-5 146 Systematic N/A 11.4 34.2 SM-6 813 Systematic N/A 22.4 34.2 SM-7 577 Systematic N/A 33.4 34.2 SM-8 358 Systematic N/A 5.9 43.8 SM-9 919 Systematic N/A 16.9 43.8 SM-10 1420 Systematic N/A 27.9 43.8 SM-11 244 Systematic N/A Table Notes:

1. Measurement locations are established on a triangular grid with randomly selected starting coordinates.

2. Measurement values are in units of dpm/l00-cm2 .

3. All of the sample measurements are taken from the southwest corner of the roof.

Plum Brook Reactor Facility FSSR, Attachment I Appendix B Rev. 0, Page 72 of 72, Survey Unit RO-4-2 ROLB Exterior Class 3 Survey Unit, Building Exterior walls l IIIl X Coord (m) Y Coord (in) Label S

Survey Unit RO-4-2: ROLB Exterior Walls, Class 3 Value Type Notes

- 0.2 1.2 SM-1 2510 Systematic North Wall

- 0.6 - 0.3 SM-2 2440 Systematic North Wall 0.8 0.2 SM-3 411 Systematic North Wall 1.7 1.1 SM-4 1600 Systematic South Wall 3.4 - 0.1 SM-5 1860 Systematic South Wall 1.0 0.1 SM-6 192 Systematic East Wall

- 0.5 0.6 SM-7 2330 Systematic East Wall

- 0.8 -0.1 SM-8 -62 Systematic West Wall 1.0 -0.05 SM-9 1930 Systematic West Wall 0.6 0.7 SM-10 -48 Systematic West Wall

-0.05 1.7 SM-11 123 Systematic Entrance Table Notes:

1. Measurement locations are selected on a random basis - Class 3 survey unit.

2. Measurement values are in units of dpm/100-cm 2 .

3. All of the fixed measurement coordinates are referenced to the lower left comer of the masonry section in which they are located.