ML11286A071

Submittal of Attachment 9 to Final Status Survey Report Supporting Eventual Termination of Licenses for Plum Brook Reactor Facility

ML11286A071
Person / Time
Site:	Plum Brook
Issue date:	10/07/2011
From:	Kolb P US National Aeronautics & Space Admin (NASA), John H. Glenn Research Ctr at Lewis Field
To:	Document Control Desk, NRC/FSME
References
Download: ML11286A071 (92)

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National Aeronautics and Space Administration John H. Glenn Research Center Lewis Field Plum Brook Station Sandusky, OH 44870 October 7, 2011 Reply to Attn of: QD U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555

Subject:

Final Status Survey Report, Attachment 9, Embedded Piping, 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 Attachment 9 to the Final Status Survey Report supporting eventual termination of the licenses for the Plum Brook Reactor Facility.

The complete Final Status Survey Report will consist of a series of Attachments, each addressing 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 which will consolidate and summarize the details presented in the Attachments.

This Attachment addresses the Final Status Survey of the Embedded Piping. It supports our conclusion that radiological remediation of the building has been completed and the area meets the criteria for unrestricted release specified in 10 CFR 20.1402.

Should you have any questions or need additional information, please contact me at NASA Plum Brook Station, 6100 Columbus Avenue, Sandusky, Ohio 44870, or by telephone at (419) 621-3242.

Peter C)'Kolb, R.E.M.

Actýihn NASA Decommissioning Program Manager

i -- - 41, Enclosure

1. Plum Brook Reactor Facility Final Status Survey Report, Attachment 9, Embedded Piping, revision 0, dated October 6, 2011.

cc:

USNRC/C. J. Glenn (FSME)

USNRC/J. Webb (FSME)

USNRC/J. Tapp RIJI/DNMS/DB ODH/M. J. Rubadue

Plum Brook Reactor Facility Final Status Survey Report Attachment 9 Revision 0 Embedded Piping iv

FINAL STATUS SURVEY REPORT ROUTING AND APPROVAL SHEET Document

Title:

Final Status Survey Report, Attachment 9 Embedded Piping Revision Number: 0 ROUTING SIGNATUWr) DATE Prepared By GL Wood/ .)A I C -KU- I.I Prepared By N/A REVIEW & CONCUR!% O Independent Technical Reviewer R. Case /0 /6 !

Other Reviewer, QA Manager J. Thomas \.

Other Reviewer N/A FSS/Characterization Manager W. Stoner 60/* 24_ _

NASA Project Radiation Safety Officer 1W. Stoner1o 71 ii

NASA PBRF DECOMMISSIONING PROJECT CHANGE/CANCELLATION RECORD DOCUMENT TITLE: Final Status DOCUMENT NO: N/A REVISION NO: 0 Survey Report, Attachment 9, Embedded Piping Revision 0: Initial issue of Report For AD-0 1/3 Rev 1 iii

Plum Brook Reactor Facility FSSR Attachment 9, Rev. 0 LIST OF EFFECTIVE PAGES DOCUMENT NO: N/A 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 0 List of Acronyms & 0 Symbols, 2 pages Text, pages 1 through 0 31 Appendix A 0 12 pages Appendix B 20 pages Appendix C 0 12 pages Appendix D 0 7 pages AD-01/5 IForm iv Rev 2

Plum Brook Reactor Facility FSSR Attachment 9, Rev. 0 TABLE OF CONTENTS 1.0 Introduction ............................................................................................................. 1 2.0 Embedded Piping Description ................................................................................. 2 2.1 Embedded Piping Systems ....................................................................................... 2 3.0 History of Operations with Radioactive Materials ................................................ 3 3.1 Piping Group 1, Primary Cooling Water (PCW) ...................................................... 3 3.2 Piping Group 2, Quadrant and Canal Piping .......................................................... 3 3.3 Piping Group 3, Hot Drains ..................................................................................... 4 3.4 Piping Group 4, Cold Drains .................................................................................... 4 3.5 Labeling of Embedded Piping .................................................................................. 4 3.6 Cleaning Process to Remediate Radioactive Materials in EP .................................. 4 3.7 Survey Process to Assess Final Status of Radioactive Materials in EP ................... 5 4.0 Embedded Piping FSS Design Approach ............................................................... 6 4.1 Embedded Piping DCGLs & Radionuclide Distributions ........................................ 6 4.2 Embedded Piping Conceptual Dose Model for Final Status Survey ........................ 8 4.3 Dose Calculations for 9-Pipe Cluster for Final Status Survey ................................ 9 4.4 Embedded Piping DCGL Values for 9-Pipe Cluster for Final Status Survey ........ 11 4.5 Embedded Piping Reporting Units in Piping Release Records .............................. 12 5.0 Embedded Piping Survey Results ........................................................................... 12 5.1 Detector Efficiencies and MDCs ........................................................................... 13 5.2 Survey Results ....................................................................................................... 18 5.3 Q uality C ontrol ....................................................................................................... 27 5.4 ALARA Evaluation ................................................................................................ 27 5.5 EPA Trigger Values .............................................................................................. 28 5.6 C onclusions ............................................................................................................ 29 6.0 R eferences ..................................................................................................................... 30 7.0 A p pend ices .................................................................................................................... 31 Appendix A - E xhibits ..............................................................................................................

Appendix B - Embedded Piping Penetration Location Maps ..................................................

Appendix C -Structural Survey Unit/Embedded Piping Dose Tables .....................................

Appendix D -Primary Cooling Piping, EP 1.11 & EP 1.12 ....................................................

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Plum Brook Reactor Facility FSSR Attachment 9, Rev. 0 LIST OF TABLES Table la, DCGL Values for Embedded Piping .......................................................................... 7 Table 1b, Radionuclide Activity Profiles for all Piping Groups ............................................... 8 Table 2, Description of Pipe Cluster in Canal F - Pump Walkway ........................................... 9 Table 3, Dose Calculation Model Dimensions ........................................................................ 10 Table 4, Calculated Doses from Principal Gamma Emitting Radionuclides ................................ 11 Table 5, Individual Radionuclide DCGL Values for Embedded Piping .................................. 12 Table 6, Embedded Piping MDC and Efficiency Ranges for Cobalt-60 and Cesium-137 using Various Detectors ......... .............................................. 15 Table 7, Embedded Piping Survey Results for Co-60 Surrogate Piping ................................... 19 Table 8, Embedded Piping Survey Results for Cs-137 Surrogate Piping ............................... 26 vi

Plum Brook Reactor Facility FSSR Attachment 9, Rev. 0 LIST OF ACRONYMS & SYMBOLS Ag-108m Silver- 108 metastable ALARA As Low As Reasonably Achievable Am-241 Americium 241 beta; denotes beta radiation C-14 Carbon 14 Co-60 Cobalt 60 CFR Code of Federal Regulations Cm-243/244 Curium 243/244 cm centimeters cpm counts per minute CsI Cesium Iodide Cs-137 Cesium 137 CV Containment Vessel DCGL Derived Concentration Guideline Level DCGLw DCGL for average concentrations over a survey unit, used with statistical tests.

(the "W" suffix denotes "Wilcoxon)"

dpm disintegrations per minute D and D Decommissioning and Decontamination EP Embedded Piping EPA US Environmental Protection Agency Eu-152 Europium 152 Eu-154 Europium 154 FSS Final Status Survey FSSP Final Status Survey Plan FSSR Final Status Survey Report ft feet 7 gamma, denotes gamma radiation g gram g/cc grams per cubic centimeter H-3 Tritium HDS Hot Dry Storage HTD Hard to Detect nuclides HRA Hot Retention Area 1-129 Iodine 129 in. inch m2 square meters MARSSIM Multi-Agency Radiation Survey and Site Investigation Manual MDC Minimum Detectable Concentration MDCR Minimum Detectable Count Rate N measurements mrem millirem mrem/hr millirem per hour mrem/yr millirem per year mSv/hr milliSeivert per hour vii

Plum Brook Reactor Facility FSSR Attachment 9, Rev. 0 LIST OF ACRONYMS & SYMBOLS. Continued NASA National Aeronautics and Space Administration Nb-94 Niobium 94 N/A Not Applicable Nal Sodium Iodide Ni-63 Nickel 63 NRC US Nuclear Regulatory Commission PBRF Plum Brook Reactor Facility Pu-238 Plutonium 238 Pu-241 Plutonium 241

% percent PCW Primary Cooling Water QC Quality Control Quad Quadrant Rm room ROLB Reactor Office and Laboratory Building s seconds SEB Service Equipment Building Sn-126 Tin 126 SR Survey Request Sr-90 Strontium 90 TBD Technical Basis Document p Mean activity concentration VSP Vitrified Storm Pipe WHB Waste Handling Building viii

Plum Brook Reactor Facility FSSR Attachment 9, Rev. 0 1.0 Introduction This report presents the results of the final status radiological surveys of the Plum Brook Reactor Facility (PBRF) Embedded Piping (EP). It is Attachment 9 of the PBRF Final Status Survey Report (FSSR). 1This attachment describes the EP, its operational history and final condition for the final status survey (FSS). It describes the methods used in decontaminating and surveying the EP and presents the results.

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 requirements of US NRC 10CFR20 Subpart E. The principal requirement is that the dose to future site occupants will be less than 25 mrem/yr. Subpart E also requires that residual contamination be reduced to levels as low as reasonably achievable (ALARA). Derived Concentration Guideline Levels (DCGL) have been established for residual contamination in the EP. As presented in the FSSP, Section 3.3, the EP dose goal is < lmrem/yr. Considering the radionuclides established in the FSSP for EP, gross beta DCGLs range from 2.408E+05 to 3.785E+06 dpm/100-cm 2 as presented in Table la.

The survey measurement results and supporting information are presented to demonstrate that residual contamination levels in each embedded pipe of the PBRF are below the respective DCGLs. It is also shown that residual contamination has been reduced to levels that are consistent with the ALARA requirement. Therefore, the EP contribution to the total dose assessment of any given structural survey unit meets the criteria for unrestricted release as described in the FSSP.

Section 2.0 of the report provides a description of EP. The specific definition of EP and examples of EP as situated in PBRF buildings are provided.

In Section 3.0, a description of the operational history with radioactive materials is presented for the various groups of EP. Post shutdown decommissioning remediation and survey activities are described.

An introduction to the sampling efforts in support of radiological characterization is included.

Section 4.0 presents the FSS design process for the EP. This section includes applicable characterization efforts in support of FSS, DCGL and nuclide distribution development. FSS Plan specifics concerning DCGLs and EP Dose Modeling are presented.

Survey results are presented in Section 5.0. The survey design approach, instrumentation and measurement sensitivities are presented. This section includes a summary of the survey measurements performed in the EP, comparison to DCGLs, tests performed and an evaluation of residual contamination levels relative to the ALARA criterion, and a conclusion with regard to the FSS of EP at PBRF.

Section 6.0 provides the references that were used to support the development of this Attachment.

1 The PBRF Final Status Survey Report comprises the report main body and several attachments. This attachments presents survey results for individual runs of embedded piping and their contribution to applicable structural survey units.

The entire final report will provide the basis for requesting termination of Nuclear Regulatory Commission (NRC) Licenses TR-3 and R-93 in accordance with 10CFR50.82 (b) (6).

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Plum Brook Reactor Facility FSSR Attachment 9, Rev. 0 Section 7 provides supporting information as contained in Appendices. Appendix A contains photos to supplement the text. Appendix B provides EP penetration location maps. Appendix C provides table(s) identifying the structural survey units which coincide with EP and the total dose combination of the EP and the structural survey units. Appendix D details the survey and data evaluation process unique to pipes EP 1.11 and EP 1.12.

2.0 Embedded Piping Description Embedded piping (EP) is any pipe situated below the minus three foot elevation (628 foot mean sea level2) that is totally encased in concrete or piping directly beneath building floors that may not be totally encased in concrete, but contained within the structural foundation of the building. Additionally, EP is grouted at the time of license termination to demonstrate compliance with the release criterion as developed in the FSSP. Examples include Containment Vessel Quadrant and Canal drain piping and remaining sections of the Primary Cooling Loop. All references to EP in this attachment fulfills all the criteria described above.

2.1 Embedded Piping Systems The EP at PBRF is divided into categories based on similar histories and operational system liquids for characterization of residual contamination and development of radionuclide profiles (Technical Basis Document (TBD), PBRF-06-004 [PBRF 2006b], Activity Ratios of Radionuclides in Embedded and BuriedPiping). The objective is to provide a basis for assignment of radionuclide profiles. Breakdown of the PBRF piping systems into similar groups considers facility design, operating history, results from recent inspections, radiological surveys and sample results. The EP comprises interconnected piping systems that can be described by a simplified conceptual model. The model consists of four main elements or compartments:

• Source compartments,

• Processing compartments,

• Mixing compartments and

• Connecting piping The principal source compartments are the:

• Primary Cooling Water System

• Fuel Storage (and Mock-up Reactor)

• Irradiated test materials (ROLB Laboratories, Hot Cells and transfer system piping)

• Waste Cleanup System This model assumes that each of these sources has a characteristic radionuclide profile. The radionuclides present in the piping were deposited over the period of facility operation and during the post-shutdown period. During PBRF operation, processing of liquid waste streams occurred in the Reactor Building, Primary Pump House, Fan House and Waste Handling 2 The reference grade level at the Reactor building is 631 feet above mean sea level as described in the NACA Reactor Plot Plan andSoil Boring Data,December 1956.

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Plum Brook Reactor Facility FSSR Attachment 9, Rev. 0 Building. During the post-shutdown period, the radionuclide composition and activity ratios of the piping deposits have changed over time due to radioactive decay and movement (and mixing) of contaminated waste water. Water movement has occurred from intermittent pumping, entry into floor drains from in-leakage and flooding, and losses from leakage and discharge to the effluent pathway.

Compartments where mixing occurred includes:

• Main Quads and Canals

• Hot Retention Area

• Cold Retention Basins

• Miscellaneous sumps and tanks 3.0 History of Operations with Radioactive Materials The internals of the EP systems reported in this attachment were utilized to contain and transport various system waters in support of reactor operation and reactor facility support. The system models introduced in Section 2.0 were developed into piping groups with similar radioactive characteristics.

Four of these piping groups are EP groups. Histories of the radioactive material transported by these systems during operations and removal of those radioactive materials during decommissioning are described below.

3.1 Piping Group 1, Primary Cooling Water (PCW)

The remnants of this piping system include about 700 to 800 feet of piping, comprising about 15 separate runs, most of which is embedded in concrete. The most significant portion is the 24-inch primary cooling water piping - 280 feet in length. The PCW piping also includes the embedded remnants of the By-pass Cleanup, Instrument Cooling and Shutdown loops, and drain lines. The PCW piping is stainless steel and it is the only EP system that operated significantly above ambient temperature and pressure and under controlled chemistry conditions. Most of this piping is presently in good physical condition and contains relatively uniform radioactive corrosion layer deposits. The uniform corrosion deposits are characteristic of those that occur in controlled chemistry, pressure and temperature environments as found in water cooled power reactor primary circuits. These deposits are overlaid by some non-uniform deposits from formerly suspended corrosion and fission products. The radionuclide composition of residual contamination deposits in PCW piping is relatively uniform throughout. In addition to the primary cooling water piping itself, piping from nearby drains and other drain piping whose main source of waste water is from the PCW system have been included in Group 1.

3.2 Piping Group 2, Quadrant and Canal Piping This piping totals over 2000 ft. and comprises about 45 runs of stainless and carbon steel piping ranging from 2 to 10 inches in diameter. This piping, mostly drain piping, received water from or supplied water to the Quads and Canals (mostly low temperature water). Much of this piping was exposed to the atmosphere for various periods of time and is significantly degraded. Piping deposits range from loose scale and sediment-debris, loosely adhered corrosion scale, "bathtub 3

Plum Brook Reactor Facility FSSR Attachment 9, Rev. 0 line deposits" and possibly some more tightly adhered corrosion layer deposits (prior to cleaning and inspection). This piping includes the pipe runs that were modeled in the dose calculations to obtain the EP DCGL published in the FSSP. The water in this piping is not "well mixed", as some lines were only sporadically filled or drained.

3.3 Piping Group 3, Hot Drains This is a large and diverse group of piping, with 50 or more runs totaling over 5,000 feet in length. Much of this piping has been removed during the D and D process. These drain lines received water from the Reactor Building, Primary Pump House, Reactor Office and Laboratory Building (ROLB) Lab Drains, process buildings (Waste Handling Building and Fan House) and the Hot Laboratory. In addition to drains from the aforementioned buildings, it includes Hot Pipe Tunnel piping and drains. The piping is comprised of stainless and carbon steel and the condition of these piping runs is similar to Group 2 piping. As with Quad and Canal piping, the hot drains have variable radionuclide composition, activity levels and activity ratios throughout. Also, as with the Quad and Canal piping, the Hot Drains received water from diverse sources. The water in this piping was not considered to be "well mixed".

3.4 Piping Group 4, Cold Drains This is a group of long-run piping with approximately 25 pipe runs totaling about 5,000 feet in length. It includes a portion of Cold Pipe Tunnel piping and floor drains and the ROLB and Service Equipment Building (SEB) basement drains. This piping is comprised mostly of carbon steel and believed to be in similar condition to Quad and Canal piping, except there are no residual radioactivity levels.

3.5 Labeling of Embedded Piping Labeling for EP was begun by project personnel in 2004 and began with system identifications numbers as presented on plant system drawings. Subsequent consultations between retired personnel and decommissioning project engineers resulted in a comprehensive listing of piping meeting the definition for EP as described in Section 2.0 of this attachment and the FSSP. This listing of EP is identified in the plant buildings with markings on the walls and floors of the facility structures which use the numerical designator for the EP from the final inventory for EP which has been grouted in accordance with Section 3.3 of the FSSP. Each individual EP opening on the walls and floors is transcribed to maps which include building elevations, easily identified physical representations of the building surfaces, appropriately sized and positioned pipe openings, and the pipe number (label) from the EP inventory. These maps are reproduced in Appendix B to this attachment.

3.6 Cleaning Process to Remediate Radioactive Materials in EP Decontamination was performed on 100% of the interior surfaces of radiologically contaminated EP. Decontamination involves the use of vacuuming, mechanical cleaning, grit blasting, and high-pressure water (Appendix A, Exhibits 1 & 4). Remediation activities commence with the simplest remediation processes and graduate to more aggressive remediation processes based on representative survey results. This graduated approach minimizes radioactive waste generation and handling, allows use of those remediation efforts 4

Plum Brook Reactor Facility FSSR Attachment 9, Rev. 0 with the lowest safety hazards to be utilized first, and provides the best flexibility when coordinating workspace availability with other decommissioning efforts.

The simplest remediation technique is vacuuming with vacuum heads to remove debris deposits from the piping. This method does not appreciably remove corrosion or scale deposits and is rarely the only remediation process required (Appendix A, Exhibit 2).

Corrosion and scale removal requires mechanical agitation of interior piping surfaces; these methods employ rotating snakes and abrasive or pulverizing heads to mechanically separate radioactivity bearing scale and corrosion deposits from the interior piping surfaces(Appendix A, Exhibits 5 & 8). These mechanical processes utilize a vacuum head in close proximity to the piping surfaces being remediated to remove scale and corrosion fragments as they are generated.

When mechanical agitation is insufficient to achieve the remediation goal, aggressive remediation escalates to grit blasting. Interior piping surfaces are grit blasted to remove tightly adhered corrosion layers from the piping. Industrial grit blast media are applied using standard and proprietary techniques with the continuous removal of waste materials using vacuum heads as described earlier.

The most aggressive technique employed is high pressure water hydro-lasing. No vacuum heads are used in conjunction for those pipes which are hydro-lased, runoff water is collected in drums and processed by PBRF operations personnel (Appendix A, Exhibits 3 & 6).

Prior to initial radiological survey activities and at any opportune phase of remediation, the piping is inspected using remote camera systems to assure the physical condition of the piping is acceptable for moving radiological detectors through the piping. Before performing any radiological survey activities using in-situ survey equipment, the piping to be surveyed is assessed for loose surface contamination using full piping length swabs by radiological controls personnel. This minimizes the potential of loose surface contamination being transported through the piping by the in-situ survey equipment, contaminating the in-situ survey equipment, or biasing the piping survey results.

3.7 Survey Method to Assess Final Status of Radioactive Materials in EP Piping interior surfaces are surveyed using detectors mounted in engineered sleds. These sleds protect the detectors as they transit through the piping and assure reproducible in-situ geometries. These geometries are required to be consistent with the geometries and parameters established during the in-situ calibration of the detector. The sleds allow the connection of fish tapes, cables or fiber rods which are manipulated by technicians to move the detector and sled through the piping to be surveyed (Appendix A, Exhibits 7 & 9).

Sleds are not feasible to be used in some smaller diameter piping. For these scenarios the in-situ calibration does not utilize a sled, the detector is directly bound to the fishtape or cable used for movement through the piping, and movement through the piping is performed cautiously to minimize any chance of damage to the detector.

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Plum Brook Reactor Facility FSSR Attachment 9, Rev. 0 Detectors used to perform piping surveys are Nal or CsI gamma scintillating detectors of sizes appropriate to the piping size and the physical challenges of the piping runs. These detectors are optimized (windowed) to measure the gamma energies specific to either Co-60 or Cs-137.

A static radiological survey measurement is taken for every foot of pipe traveled.

2 Field measurements in cpm are converted to equivalent beta measurements in dpm/100cm through application of surrogate calculations and piping correction factors. These calculated activity densities are assessed against the applicable DCGL from the FSSP for compliance with the EP dose goal. As these post-remediation surveys demonstrate the EP dose goal has been achieved, the surveyed piping is placed in to isolation and control, and the survey results are documented into a release record.

The 24" primary cooling lines are surveyed using a different method from that described above due to circumstances as described in Appendix D to this attachment. These surveys utilize scintillating beta-gamma detectors mounted on an in-situ, variable geometry, pipe sled. This sled allows the detectors to traverse elbows and risers while assuring a consistent geometry for each survey measurement. 100% assay by scan survey of all accessible surfaces and static radiological measurements at specified increments are assessed to demonstrate compliance with the EP dose goal. These surveys are detailed in Appendix D of this attachment.

4.0 Embedded Piping FSS Design Approach 3

The approach for EP FSS is as follows:

• Determine if piping meets the definition of EP.

" Determine the piping group of the piping.

• Perform remediation and radiological surveys of the piping.

• Remediate and survey the piping until the EP dose goal is achieved.

• Establish controls on the piping to ensure the piping system is not impacted by site operations that could change the condition of the piping.

4.1 Embedded Piping DCGLs & Radionuclide Distributions The PBRF contains a number of pipe runs that are embedded in concrete. As stated above, EP is any pipe situated below the minus three (-3) foot elevation that is totally encased in concrete or piping directly beneath building floors that are not totally encased in concrete, but contained within the structural foundation of the building. Examples include the Containment Vessel Quadrant and Canal drain piping and remaining sections of the Primary Cooling Loop. The EP DCGL values are listed in Table 1a. These values represent surface activity concentrations that correspond to an annual dose of 1 mrem/yr to a future building occupant. In order to utilize the EP DCGL values, piping must be grouted prior to license termination.

The PBRF dose goal for EP was 1 mrem/yr. However, in accordance with Section 3.3 of the PBRF FSSP, different dose goals can be applied in different areas as long as the residual contamination on the structure surface in the survey unit containing the given EP is sufficiently The EP DCGLs are determined in accordance with Attachment C of the FSSP.

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Plum Brook Reactor Facility FSSR Attachment 9, Rev. 0 low to allow for the selected dose goal. For example, if the FSS results indicate that the residual contamination level in Hot Dry Storage is 0.5 times the DCGL, the dose from EP in this survey unit could be as high as 12.5 mrem/yr.

Table la, DCGL Values for Embedded Piping DCGL Radionuclide 2CG (dpm/100 cm2 per mrem/yr)

Co-60 2.408E+05 Eu-154 5.325E+05 Eu-152 7.352E+05 Nb-94 9.082E+05 Ag-108m 1.312E+06 Cs-137 3.785E+06 Radionuclide distributions and activity ratios were developed in TBD-06-004 [PBRF 2006b].

Recognizing that radionuclide composition in the piping varies considerably across the PBRF, the piping has been divided into groups with similar characteristics for development of radionuclide profiles. The EP has been divided into four main groups for this purpose. The January 2006 study evaluated information from laboratory analysis results of 55 samples of piping deposits. The Cs-137 to Co-60 activity ratio is an important parameter for evaluation of survey measurements in PBRF EP. When piping surveys are conducted using surface activity measurements, this ratio "controls" the gross beta DCGL. This is because these two radionuclides are found in all piping group residual contamination and they, in effect "bracket" the DCGLs, as seen in Table la. The Co-60 dose contribution is about 16 times the Cs-137 contribution per unit activity and Co-60 yields the most restrictive individual nuclide DCGL.

Correspondingly, the Cs-137 DCGL is about 16 times the Co-60 DCGL and is the least restrictive DCGL of the gamma emitters that are consistently observed in PBRF piping deposit samples. Other gamma emitters such as Eu-152 and Eu-154 found in some PBRF EP samples have unit dose factors intermediate between Co-60 and Cs-137. However, these are not usually seen in the absence of Co-60 and do not greatly influence the gross beta DCGL. A summary table of the radionuclide distributions utilized to surrogate field measurements and develop activity profiles for the EP is shown below as Table lb. Detailed explanation for the development of Table lb can be reviewed in TBD-06-004.

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Plum Brook Reactor Facility FSSR Attachment 9, Rev. 0 Table 1b, Radionuclide Activity Profiles for All Piping Groups 1 Radionuclide Primary Activity Fraction (%)

(1) Emission Group Group Group Group Group Group Group (2) 1 2 3.1 (3) 3.2(4) 3.3(5) 4.1(6) 4.2(61 Am-241 4 0.2 0.01 1.17 1.19 C-14 3 1.36 1.38 0.029 0.04 Cs-137 1 0.91 10.63 65.90 39.89 79.9 44.3 84.1 Co-60 1 22.96 20.50 4.04 4.37 3.94 55.7 15.9 Cm-243/244 4 0.82 Eu-152 1 21.78 0.17 Eu-154 1 5.79 0.12 0.27 0.28 1-129 1 3.37 Ni-63 3 12.93 57.90 10.60 16.37 7.87 Nb-94 1 0.67 0.01 Ag-108m 1 0.16 0.59 Pu-238 4 0.63 Pu-241 4 0.72 Sr-90 2 2.21 0.92 17.85 37.84 8.13 Sn-126 1 0.71 1 1 H-3 3 23.42 7.55 0.03 0.03 0.03 Table lb notes:

1. Radionuclides are included in the table if their activity fraction is 0.5% or greater in any of the piping group results (some activity fractions may be reported, even though <0.5% because the radionuclide is > 0.5% in at least one piping group).

2. Primary emission codes are: 1 = gamma (beta-gamma), 2 = beta-only, 3 = HTD and 4 = alpha.

3. Group 3.1 (Miscellaneous Hot Drains) activity fractions for individual radionuclides are assigned the average values from all the group 3 samples (no samples from group 3.1 were sent for comprehensive analysis).

4. Group 3.2 (Hot Lab Hot Work Areas) activity fractions are obtained from the results of comprehensive analysis of sample No EP-l1 (Hot Lab Room 16 Floor Drain).

5. Group 3.3 (activity fractions are obtained from the results of comprehensive analysis of sample Nos. CS050823-012 (HRA Pit drain pipe scale) and EP-4 (WHB Evaporator Room floor drain). The activity fractions are the averages of the activity fraction values from the two samples.

6. No comprehensive analysis results are available for piping group 4. Activity fractions are available for gamma emitters only - from gamma spectroscopy results.

4.2 Embedded Piping Conceptual Dose Model for Final Status Survey Various piping configurations were evaluated to determine which EP scenario delivered the highest dose to a building occupant [PBRF 2006]. The EP configuration that delivers the highest dose to a future building occupant is the 9-pipe cluster in the Canal F - Pump Walkway. The individual is assumed to occupy the walkway between Canal F and the Pump Room at the Reactor Building -25 ft. elevation and is exposed to a group of pipes (a pipe cluster) embedded in the concrete beneath the walkway. Plant drawings were reviewed and inspections performed to confirm that the pipe cluster located beneath the Canal F - Pump Room Walkway represents the most conservative case. That is, this pipe cluster is the highest concentration of embedded pipes to which a future building occupant could be exposed while 8

Plum Brook Reactor Facility FSSR Attachment 9, Rev. 0 occupying a single location in the facility. Table 2 describes the piping layout used in the dose model.

Table 2, Description of Pipe Cluster in Canal F - Pump Walkway Piping DID Lenh Horizontal Offset Pipe CLV') Pipe Top Surf gDescription D From Dose Point Depth Depth Below Run ID (in.) (ft) CL(3 ) (ft) (in.) floor (in.)

1.21 Canal H Drain 6 81 1.5 16 13.25 1.23 Canal G Drain 6 42 1.5 16 13.25 1.24 Canal G Purge 3 39 3 16 14.75 1.25 Canal F Drain 6 20 4.5 16 13.25 1.26 Canal F Purge 3 19.5 6 16 14.75 1.641 Canal F&G OF Header(1 ) 8 25 3 38 34.25 1.81 Canal K Floor Drain 6 25 6 25 22.25 1.82 Canal J & HDS Riser (2) 3 25 4.5 25 23.75 1.83 HDS Floor Drain 4 25 7 38 36.25 Average Dimensions => 5.0 33.5 22.9 20.6 Table 2 Notes:

1. Overflow Header

2. Hot Drain System Riser

3. CL denotes centerline 4.3 Dose Calculations for 9-Pipe Cluster for Final Status Survey All dose calculations were performed using MicroShield Version 5.04. [PBRF 2006] For the primary DCGL dose calculations, MicroShield geometry option 10 was used for the 9-pipe cluster Canal F - Pump Room Walkway model. 4 This is a cylindrical surface source with external dose point. The following assumptions were used to establish the MicroShield case runs and for determination of DCGL values:

The dose receptor (dose point) is located one meter above the walkway floor surface on the longitudinal centerline of the pipe cluster and at a distance midway between the pipe ends.

The 9 pipes lie in parallel runs (parallel to each other and to the floor surface) at the same elevation. The actual pipe centerline depths range from 16 to 38 inches and the average depth is 22.9 inches.

4 The MicroShield code has several standard options for combinations of source and shield configurations. These are called "geometries". The geometry used for the default case, Geometry 10 is suitable for dose-receptor points external to the piping and located at positions that lie between the pipe ends (within the two planes perpendicular to the pipe longitudinal axis).

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Plum Brook Reactor Facility FSSR Attachment 9, Rev. 0

• The concrete in which the piping is embedded is modeled as a concrete slab shield (density 2.4 g/cc), 12 in. thick, placed between the top pipe surface and the floor elevation.

• All the pipes are cleaned by vacuuming and pressure blasting or mechanical means to remove loose scale and loosely adherent surface contamination. The pipes are filled with grout (concrete) with density 1.8 g/cc.

• The pipes are all assumed to be 25 ft. in length. Note that the pipe lengths vary from 19.5 to 81 ft. with average length of 33.5 ft. It is found that the calculated dose is not sensitive to pipe length as the length is increased beyond 20 ft.

• The pipe wall is modeled as a 1/4 in. thick (0.65 cm) cylindrical shield. This corresponds to Schedule 40 piping wall thickness for 5 in. piping, the average ID of the 9-pipe cluster. Note that the actual piping is all Schedule 80 (0.95 cm.

wall thickness) and the "buildup" medium for the MicroShield dose calculations is selected as the grout-filled pipe core.

The model includes a piping corrosion layer surrounding the cylindrical surface source, modeled as "cladding" of 0.025 cm thickness.

The only exposure pathway that is operative for EP is direct dose from gamma-emitting radionuclides. All the radionuclides that were present in piping residual contamination are fixed in place by the grout and are not available for transport to ground water or to ingestion or inhalation pathways to a future building occupant.

• This DCGL calculation uses MicroShield case run output dose rates in units of mSv/h (Deep Dose Equivalent Rate). The output dose rates are then converted to mrem/hr (100 mrem/h per mSv/h).

The MicroShield source, dose point coordinates and shield dimensions are summarized in Table 3 below.

Table 3, Dose Calculation Model Dimensions Source Dimensions (cm) Dose Point Coordinates (cm) Shields (cm)

Pipe Radius (1) X (2) y (3) Z (4) Wall Pipe Concrete Length Clad Wall 762 Pipe- Pipe- 381 Pipe- 0.025 0.65 30.48 (25 ft.) specific specific (12.5 ft.) specific (1 ft)

Table 3 Notes:

1. This is the radius in cm. corresponding to each pipe ID.

2. The x coordinate is the total distance from the center axis of each pipe to the dose point. This includes the pipe radius, wall clad, pipe wall-shield thickness, the 12 in. concrete slab-shield thickness and the 1-meter distance from floor surface to the dose point (receptor center-height above the floor).

10

Plum Brook Reactor Facility FSSR Attachment 9, Rev. 0

3. The y coordinate places the dose point at the center of the pipe lengths.

4. The z coordinate is the offset distance from the centerline of each pipe to the pipe cluster centerline (the dose point is located directly above the pipe cluster centerline).

The dose to the receptor from each radionuclide is obtained as the sum of the contributions from each piping run in the 9-pipe cluster. The results are shown in Table 4. It is noted that DCGL values for radionuclides that emit only beta particles are not calculated for EP, even though several have been measured in piping deposits. They do not contribute to the dose to future building occupants because the piping that remains in place is filled with grout.

Table 4, Calculated Doses from Principal Gamma Emitting Radionuclides Canal F - Pump Room Walkway 9-Dipe Cluster 2 Piping mrem/hr per dpm/1 00-cm Line No. Co-60 Cs-137 Eu-152 Eu-154 Ag-108m Nb-94 1.21 5.54E-10 3.90E-11 1.82E-10 2.50E-10 1.11E-10 1.58E-10 1.23 5.54E-10 3.90E-11 1.82E-10 2.50E-10 1.11E-10 1.58E-10 1.24 1.79E-10 1.08E-11 5.84E-11 8.08E-11 3.13E-11 4.60E-11 1.25 8.64E-11 3.60E-12 2.79E-11 3.95E-11 1.1OE-11 1.74E-11 1.26 1.76E-11 5.33E-13 5.68E-12 8.19E-12 1.71E-12 2.87E-12 1.641 2.90E-10 1.64E-11 9.42E-11 1.31E-10 4.79E-11 7.11E-11 1.81 2.43E-11 7.02E-13 7.87E-12 1.14E-11 2.27E-12 3.83E-12 1.82 6.12E-11 2.70E-12 1.97E-11 2.79E-11 8.16E-12 1.28E-11 1.83 8.29E-12 1.87E-13 2.71E-12 3.97E-12 6.32E-13 1.11E-12 Total 1.77E-09 1.13E-10 5.81E-10 8.03E-10 3.25E-10 4.71E-10 Table 4 Notes:

The dose rates from 1-129 (9.89E-35 mrem/hr), Sn-126 (1.45E-17 mrem/hr) and Eu-155 (4.1OE-16 mrem/hr) were calculated, but are found to be at least 5 orders of magnitude below the dose rates from the other gamma emitting radionuclides. They are of no consequence and are eliminated from further consideration.

4.4 Embedded Piping DCGL Values for 9-Pipe Cluster for Final Status Survey To obtain individual radionuclide DCGL values, the dose rate for each radionuclide is converted to annual dose by multiplying by 2340 h/yr, the exposure-hours for the occupant in the building occupancy scenario. The DCGL values are then obtained as the reciprocal of the 11

Plum Brook Reactor Facility FSSR Attachment 9, Rev. 0 annual dose. The results of these calculations are provided in Table 5. The individual radionuclide DCGL values range from 2.408E05 dpm!100-cm 2 for Co-60 to 3.785E06 dpm/100-cm 2 for Cs-137. The calculated doses and DCGL values are strongly dependent on the thickness of concrete shielding that surrounds the EP. The concrete typically provides a minimum of 12 to 14 inches of shielding for the piping.

Table 5, Individual Radionuclide DCGL Values for Embedded Piping Radionuclide Dose from all Pipes Annual Dose to Building DCGL (mrem/hr) Occupant (mrem/yr) 2 (dpm/100-cm per mrem/yr)

Co-60 1.77E-09 4.17E-06 2.408E+05 Eu- 154 8.03E- 10 1.89E-06 5.325E+05 Eu-152 5.81E-10 1.37E-06 7.352E+05 Nb-94 4.71E-10 1.11E-06 9.082E+05 Ag-108m 3.25E-10 7.60E-07 1.312E+06 Cs-137 1.13E-10 2.64E-07 3.785E+06 The gross activity DCGL for the EP is calculated using equations in the FSSP for gross activity and surrogate DCGLs, based on the radionuclide mixture in residual contamination. Activity fractions for the EP are shown in Table lb, individual DCGL values for EP are shown in Table 5.

4.5 Embedded Piping Reporting Units in Piping Release Records Embedded piping release records collate EP radiological surveys and assess compliance with the EP dose goal in units of unity where 1.0 is 1 mrem/yr. These unity values are determined in accordance with the FSSP, and reference the DCGL values (from the FSSP) as presented in Table 5 above.

The unity calculation is as follows:

Ci + C2 C___

+ <1 DCGLI DCGL2 DCGL ,

Where: Cn = concentration of radionuclide n and DCGLn = DCGL of radionuclide n.

Scenario's where EP unity is > 1.0 are discussed in section 5.0 below.

5.0 Embedded Piping Survey Results The surveys to establish the final status of EP systems are conducted after cleaning and remediation surveys are performed in accordance with the applicable Work Execution Package 12

Plum Brook Reactor Facility FSSR Attachment 9, Rev. 0 (WEP). As stated earlier these survey results are collated and assessed against the EP dose goal in units of unity where 1.0 is 1 mrem/yr. For survey conclusions which result in a unity of greater than one, there are two follow-on actions:

• Further remediation and radiological surveys with assessment against the EP dose goal.

• Select an appropriate EP dose goal as described in the FSSP and Section 4.1 above.

Further remediation and surveys are performed when it is ALARA and physically safe to do so.

Selection of a dose goal greater than one is performed when the safety constraints of additional remediation do not justify the reduction in contamination levels. This decision also considers ALARA concerns and the residual contamination on the structure surface in the structure survey units affected by the embedded pipe run(s). If selection of an EP dose goal greater than one cannot result in a dose of 25 mrem/yr or less for the affected structure survey units then the application of area factors as described in Section 3.7 of the FSSP may be used to demonstrate compliance with the release criterion. Selection of a dose goal greater than one is more conservative than applying area factors. Area factors were not required to demonstrate compliance with the release criterion for any embedded pipes.

5.1 Detector Efficiencies and MDCs The detectors utilized for EP surveys were gamma scintillating detectors constructed of Nal or CsI crystals with photo-multiplier tubes in a single housing purchased from various vendors.

These detectors were optimized during calibration to measure gamma energies representative of Co-60 or Cs-137 gamma energies with the use of discriminator settings (windowing) 5 After calibration and the establishment of the detector operating parameters, the detectors is assigned specific efficiencies for each unique combination of detector, sled, nuclide of concern, co-axial cable length and pipe diameter. An example of how these unique efficiencies are determined follows;

• A detector (e.g. detector #1003) requires an efficiency determination for Cs-137 in a 4 inch pipe.

• A sled suitable for the physical layout of the 4 inch pipe(s) to be surveyed is selected to be used with detector #1003 (e.g. sled #104)

" A four inch section of clean piping will be loaded with a large, flexible conformal single nuclide source which has a vendor certified, traceable to the National Institute of Standards and Technology, homogenous activity deposition of Cs-137 activity across its surface area. The source is loaded inside the 4 inch clean pipe section, in continuous contact with the pipes inside diameter. The pipe section is significantly longer then the sources maximum dimension, and the source is verified to be completely within the pipe section.

• The detector is fitted into the sled and inserted into the 4 inch pipe containing the conformal Cs-137 source. The detectors centerline is centered on the middle of the 5 Two pipe runs (EP 1.11 and EP 1.12) were surveyed using a different methodology from the other embedded pipes. The details for these two unique runs are described in Appendix D of this attachment.

13

Plum Brook Reactor Facility FSSR Attachment 9, Rev. 0 Cs-137 source (Photographs of a detector-sled-pipe and cable setup are located in Appendix A, Exhibit 10 of this attachment).

• The detector parameters are verified prior to acquiring activity measurements for the efficiency determination, and the cable length being used for the efficiency determination is documented.

• A series of counts are collected as prescribed by approved procedures for efficiency determination.

• The resultant efficiency determination is a unique efficiency defined by the detector number, sled number, pipe size, co-axial cable length, and nuclide of concern.

As mentioned previously, sleds are not feasible for some small diameter piping surveys. For these instances, the same procedure for efficiency determination is followed with the sled listed as "No Sled" in the detector efficiency determination and history file. Enhanced caution is applied when acquiring field measurements as the added protection of the sled is not available. Survey data quality is not adversely affected due to the scenario of having no sled with the detector. Detector sleds perform two purposes, the primary purpose is to facilitate ease of movement through piping and protect the detector from physical damage, the secondary purpose is to maintain the in-situ geometry consistent between field measurements and the efficiency determination. Detectors used with no sled have efficiency determinations which recreate the least optimal field geometry, and movement through the piping is performed cautiously to minimize any chance of damage to the detector during field surveys.

After any efficiency determination is completed the unique efficiency is used to calculate MDCs and MDCRs for that efficiency. All calibrations, efficiencies and MDC/MDCR calculations are entered into the detector history files and referenced for converting field measurements in counts per minute to activity measurements in disintegrations per minute per 100 centimeters squared. Detector sensitivity is verified to be compliant for use in Class 1 areas as defined in the FSSP (all embedded pipes are classified as Class 1). An additional measure of conservatism is that embedded pipes have static survey measurements performed over 100% of their surface area. This greatly enhances retrospective power curves when necessary to demonstrate compliance with the EP dose goal.

Table 6 lists efficiencies and MDCs for the numerous detector-sled-pipe and nuclide of concern combinations utilized during surveys of the EP presented in this attachment. Cable lengths have not been included in this table.

14

Plum Brook Reactor Facility FSSR Attachment 9, Rev. 0 Table 6, Embedded Piping MDC and Efficiency Ranges for Cobalt-60 and Cesium-137 using Various Detectors Pipe Co-60 MDC Co-60 Cs-137 MDC Cs-137 Diameter Detector (dpm/100 cm 2 ) Efficiencies0') (dpm/100 cm 2) Efficiencies")

(Inches) Sled # # High Avg. Low High Avg. Low High Avg. Low High Avg. Low 70006-0.75 None 0047 9808 9808 9808 1 0.00069 0.00069 0.00069 1 10260 10260 10260 1 0.00075 0.00075 0.00075 212701 204402 1.0 None 70006- 6687 6687 6687 0.0006 0.0006 0.0006 1 21002 12247 7587 0.0007 0.00048 0.00019 0047 70006-0048 212701 204402 215957 238367 238369 1.5 None 247696 6897 4596 2935 0.0005 0.00046 0.00028 1 17490 5560 2330 0.004 0.00085 0.00019 247697 70006-0047 70006-0048 1.5 121 212701 9688 9688 9688 1 0.00028 0.00028 0.00028 212701 204402 215957 2.0 None 238367 1085 5842 2946 0.0008 0.0004 0.00017 238369 247696 247697 212701 2.0 121 204402 7836 5234 3268 0.0003 0.00024 0.00016 1 11221 10190 9158 1 0.0003 0.00026 0.00021 238369 2.5 121 212701 4099 4099 4099 0.0015 0.0015 0.0015 3.0 None 238367 1535 1535 1535 0.00086 15

Plum Brook Reactor Facility FSSR Attachment 9, Rev. 0 Table 6, Embedded Piping MDC and Efficiency Ranges for Cobalt-60 and Cesium-137 using Various Detectors Pipe Co-60 MDC Co-60 Cs-137 MDC Cs-137 Diameter Detector (dpm/100 cm 2 ) Efficiencies0') (dpm/100 cm 2 ) EfficienciesO')

(Inches) Sled # High Avg. Low High Avg. Low High Avg. Low High Avg. Low 212701 204402 3.0 101 3414 2710 2249 0.00066 0.00043 0.00014 LVSI 238369 212701 3.0 121 204402 12683 7396 2779 0.0003 0.00021 0.00013 238369 4.0 None 247696 2899 2899 2899 0.00043 0.00043 0.00043 2151 1874 1596 0.00069 0.00069 0.00069 LVS 1 238367 4.0 101 238369 10416 4973 1509 0.00064 0.00032 0.00013 9453 4280 1852 0.00083 0.00043 0.00019 247696 247697 4.0 107 238367 1398 1398 1398 0.00066 0.00066 0.00066 238367 6.0 101 238369 10856 6467 3143 0.0002 0.00013 0.00008 3393 2662 1394 0.00071 0.00040 0.0002 LVS1 238367 6.0 106 3406 3406 3406 0.00018 0.00018 0.00018 1206 1206 1206 0.00051 0.00051 0.00051 LVS1 6.0 107 LVS1 2066 1200 333 0.002 0.00119 0.00038 3306 2566 1286 0.00077 0.00047 0.0003 LVS1 4049 2358 695 0.0044 0.00171 0.0001 8.0 107 238369 B566A 8.0 108 B577A 16192 6135 1037 0.004 0.00333 0.003 1052 1026 999 0.006 0.006 0.006 A689X 10.0 107 LVS1 4320 4320 4320 0.0001 0.0001 0.0001 B566A B577A 10.0 108 11223 2832 378 0.0046 0.00382 0.003 994 874 712 0.0069 0.00597 0.005 A689X B566A B566A 10.0 13177 5294 631 0.0048 0.00372 0.003 1044 799 348 0.007 0.00645 0.006 B577A 20.0 118 B577A 12504 12504 12504 0.0001 0.0001 0.0001 16

Plum Brook Reactor Facility FSSR Attachment 9, Rev. 0 Table 6 Notes:

1. Efficiencies are determined in-situ with the detector-sled-pipe size and nuclide of concern as identified.

2. Range and average efficiencies were determined by adding similar detector efficiencies in the same configuration.

17

Plum Brook Reactor Facility FSSR Attachment 9, Rev. 0 5.2 Survey Results The EP remediation and survey campaign began in 2005 and continued through the decommissioning effort at PBRF. As a result of this remediation and survey campaign, 167 runs of EP were remediated, surveyed and grouted in compliance with the FSSP and its implementing procedures. Table 7 and Table 8 provide a summary of the EP survey results.

The tables are divided into piping where Co-60 is the nuclide of concern (Table 7) and piping where Cs-137 is the nuclide of concern (Table 8).

Tables 7 & 8 identify those pipes which utilized Co-60 or Cs-137 as the surrogate nuclide.

Each pipe run is identified with the label applied to the pipe run, a short description of the pipe run, the pipe run's length and the number of survey measurements acquired in the pipe run. For each pipe run the appropriate DCGL, maximum activity, mean activity and standard deviation of the survey measurements for that pipe run is listed. It should be noted that background is not subtracted from EP surface activity measurements; therefore, the results are conservative. Each pipe run's dose as represented by the pipe run's average activity is listed along with a statement that confirms the average dose and the survey measurements supporting that dose are less than DCGL.

Occasional piping runs (e.g. ROLB-102) contain multiple sections of piping within the run where Co-60 is the nuclide of concern. After assessing sample coupons and system history other sections of the same piping run have been determined to present Cs-137 as the nuclide of concern. In this scenario example (ROLB-102) drain drops from Cs-137 systems empty into the main system which was surveyed as a Co-60 nuclide of concern. These scenarios are described in individual release records for similar piping runs and the results of any individual sections are presented in Tables 7 & 8.

Embedded piping DCGLs correspond to a dose contribution of 1 mrem/yr to the structural survey units which coincide with the EP's location in or under the building footprint as described in the FSSP. Those structural survey units which must adjust their DCGL for EP are identified in each structure's attachment to the Final Status Survey Report. Appendix C of this attachment presents those structural survey unit's dose with any corresponding dose contribution from EP to demonstrate compliance with the release criterion.

18

Plum Brook Reactor Facility FSSR Attachment 9, Rev. 0 Table 7, Embedded Piping Survey Results for Co-60 Surrogate Piping Pipe # of DCGL ( Maximum Mean Activity Standard Average EP Dose EP ID # EP Description Length 2CL) Activity Deviation Activity (mrem/yr.)

N (dpm/100 cm) (dpmn/100 cm 2) (dpm/1OO cm 2 ) (dpmi/100 cm 2) <DCGL Pump Room 22 on -25 Foot Elevation of Reactor Building 1.31 Quad D Purge 141 141 3.57E+05 13,555 7,134 2,140 Yes 0.020 1.32 Quad D Drain 146 146 3.57E+05 82,248 17,135 13,708 Yes 0.048 1.33 Quad C Purge 90 90 3.57E+05 67,283 7,313 6,947 Yes 0.020 1.34 Quad C Drain 96 96 3.57E+05 38,725 8,226 4,113 Yes 0.023 1.35 Quad B Purge 78 78 3.57E+05 12,948 3,938 1,845 Yes 0.011 1.36 Canal E Drain 53 53 3.57E+05 53,573 10,358 7,857 Yes 0.029 1.37 Canal E Purge 36 36 3.57E+05 13,005 6,885 2,678 Yes 0.018 1.38 Quad B Drain 37 37 3.57E+05 7,695 5,497 1,099 Yes 0.015 1.39 Quad A Purge 38 38 3.57E+05 15,565 6,566 2,830 Yes 0.019 1.395 Quad A Drain 45 45 3.57E+05 9,488 4,744 1,459 Yes 0.013 1.21 Canal H Drain 80 80 3.57E+05 1,285 643 321 Yes 0.002 1.22 Canal H Purge 90 90 3.57E+05 8,336 3,574 1,516 Yes 0.009 1.23 Canal G Drain 42 42 3.57E+05 3,375 749 749 Yes 0.002 1.24 Canal G Purge 30 30 3.57E+05 11,065 6,278 1,785 Yes 0.019 1.25 Canal F Drain 20 20 3.57E+05 4,444 1,111 741 Yes 0.003 1.26 Canal F Purge 21 21 3.57E+05 12,059 8,039 1,827 Yes 0.022 1.71 Canal H Hot Drain 120 120 3.57E+05 54,313 4,502 4,934 Yes 0.013 1.72 Canal H Waste Air 100 100 3.57E+05 7,489 3,782 1,345 Yes 0.011 1.72A Trench to sump (pipe 14 14 3.57E+05 39,948 14,829 12,899 Yes 0.042 under removed valve) 1.641-8 Canal G&H Overflow 51 51 3.85E+05 24,217 6,594 3,278 Yes 0.018 1.641-4 Canal G&H Overflow 34 34 3.85E+05 12,361 7,466 1,969 Yes 0.019 1.81 Canal J&K Drains 20 20 3.57E+05 6,916 1,692 1,363 Yes 0.005 1.82 HDS Valve Box 16 16 3.57E+05 13,890 7290 2,066 Yes 0.019 Header Rx-151 QuadB Spare (closed) 21 21 3.57E+05 7,311 3,214 1,311 Yes 0.011 Rx-1 11 RT Drain to Sump 1 1 3.57E+05 20,022 20,022 20,022 Yes 0.056 19

Plum Brook Reactor Facility FSSR Attachment 9, Rev. 0 Table 7, Embedded Piping Survey Results for Co-60 Surrogate Piping Pipe # of DCGL (1) maximum Mean Activity Standard Average EP Dose EP ID # EP Description Length 2 Activity 2 Smreytan Activity 2 ActiveeD (Et) N 2

(dpmI/100 cm ) (dpm/100 cm 2) (dpm/100 cm ) (dpm/100 cm ) <DCGL (mremlyr.)

Rx-113 Water to Pump Rm 20 20 3.57E+05 6,191 3,967 312 Yes 0.012 Rx-148 2nd Cooling to tests 21 21 3.57E+05 4,739 3,912 611 Yes 0.009 Rx-150 Quad B utility air 21 21 3.57E+05 7,186 3,969 1,292 Yes 0.012 Rx-152 Quad B DI water 21 21 3.57E+05 5,911 3,169 983 Yes 0.011 Rx-113D Water to Pump Rm 17 17 3.57E+05 25,616 15,179 5,129 Yes 0.046 Drain Rx-148D 2nd Cooling Drain 16 16 3.57E+05 27,612 14,732 4,933 Yes 0.044 Rx-150D

___________Drain Quad B utility air 15 15 3.57E+05 18,962 14,179 4,317 Yes 0.038 Rx-151D Spare - drain line 15 15 3.57E+05 21,001 15,093 2,911 Yes 0.042 Rx-160 RT Drain to Sump 2 2 3.57E+05 5,551 5,551 5,551 Yes 0.016 Rx-155 Sump/trench vent 7 7 3.57E+05 5,069 4,111 649 Yes 0.012 Rx-152D Drain Line forDI 15 15 3.57E+05 35,166 17,311 7,494 Yes 0.051 water Rx-129 Sump Room Hot Drain 3 3 3.85E+05 40,419 31,011 8,914 Yes 0.079 Rx-161 Canal E drain into 3 3.57E+05 857 750 804 Yes 0.002 QUAD. B Rx-126 Quad B ( secondary 21 21 3.57E+05 10,713 7,649 1,931 Yes 0.022 cooling water return) I Rx-126D Quad B ( sec. cooling 15 15 3.57E+05 22,914 13,319 3,408 Yes 0.038 water return DRAIN) I_ _____

Drain Trench on Reactor Bldg -25 ft 1.41 Quad B Hot Drain 45 45 3.57E+05 31,492 6,910 4,007 Yes 0.019 1.42 Quad B Cooling Air 42 42 3.57E+05 12,144 5,009 2,001 Yes 0.015 1.43 Service Ring Return 47 47 3.57E+05 9,413 6,195 1,362 Yes 0.018 1.44 Sub-pile Suction 54 54 3.85E+05 156,116 81,009 25,881 Yes 0.211 1.45 CA-RT Vent line 112 112 3.85E+05 169,847 33,364 36,209 Yes 0.088 1.51 Annulus Floor Drain 3 3 3.85E+05 4,500 3,750 417 Yes 0.010 1.51D Annulus Floor Drain 7 7 3.85E+05 11,099 6,747 2,373 Yes 0.018 1.51 Annulus Floor Drain 72 72 3.85E+05 29,191 6,909 5,559 Yes 0.019 1.51 Annulus Floor Drain 46 46 3.85E+05 15,193 9,197 2,579 Yes 0.024 Elect. CND to JB at 1.51-A-4 point A 2 2 3.85E+05 3,151 3,151 0 Yes 0.008 RX12 RX-162 A Drain Cable Line Tray to 1.51 Quad D & 27 27 3.85E+05 9,949 4,211 2,073 Yes 0.012 1 20

Plum Brook Reactor Facility FSSR Attachment 9, Rev. 0 Table 7, Embedded Piping Survey Results for Co-60 Surrogate Piping Pipe ##oof Pie DCGL CL()( Maximum Activity Mean Activity Standard Deviation Average Activity EP Dose (rmy.

EP ID # EP Description Length N (dpm/100 cm 2) (dpAcivi cm2) (dpmI100 cm ) 2 (dpm0i0o cm2) <DCGL (mremyr.)

(ft) ______m___________

RX-163 Cable Tray Quad D& 26 2 3.85E+05 8,636 4,361 1,619 Yes 0.013 C= Drain Line to 1.51 RBDL-1 Rx-25 Hot Cold Drain 21 21 3.85E+05 36,177 6,626 7,003 Yes 0.018 (RX 127)

RBDL-2 Rx-25 Hot Cold Drain 44 44 3.85E+05 28,644 7,166 6,141 Yes 0.020 (RX 147)

Drain Line from RX 157 annulus at elevator pit ____ 5 5 3.85E+05

_________________ 11,694 11,161

______ 2,116 Yes 0.029 Canal 1.641 Overflow 34 ___ HDS Valve Box, HDS & Off Gas 1.641 Canal G&H Overflow 34 34 3.85E+05 12,919 7,761 1,878 Yes 0.019 1.64 Canal J K Overflow 60 60 3.57E+05 94,913 22,002 19,488 Yes 0.060 HL-111 Canal J Vent 3 3 3.57E+05 11,794 10,007 2,891 Yes 0.028 CV, Sub Pile & Corridor 1.13 Supply Loop Drain 39 39 3.85E+05 31,289 8,161 4,987 Yes 0.022 1.14 Return Loop Drain 35 35 3.85E+05 122,562 14,699 17,732 Yes 0.039 1.15 Sheath Drain 60 4 3.85E+05 15,429 8,085 3,048 Yes 0.021 Rx-139 Quad B to RT PCW 4 4 3.85E+05 65,522 47,618 12,571 Yes 0.125 Hot Drain from 1.52 annulus to sub pile 49 49 3.85E+05 49,041 10,965 7,707 Yes 0.029 room drain Rx-149 SPR Floor Drain 20 20 3.85E+05 7,244 4,108 1,459 Yes 0.011 Rx-135 Shield Drain 36 36 3.57E+05 95,139 56,869 21,011 Yes 0.163 Rx-137 PCW Valve Box Drain 9 9 3.85E+05 5,302 3,568 1,070 Yes 0.010 S1 Service conduit 16 16 3.85E+05 13,608 8,848 3,004 Yes 0.023 S2 Service conduit 16 16 3.85E+05 16,321 10,949 2,209 Yes 0.030 Quad A Rx-159 QuadAdrainntoDr 11 11 3.85E+05 25,664 16,741 5,239 Yes 0.043 annulus Rx-130 Spare to SPR 21 21 3.57E+05 72,797 12,061 16,085 Yes 0.036 Quad Conduit to Al Electrical Box D 49 I 3.57E+05 75,805 8,509 13,897 Yes 0.025 Quad Conduit to 35 35 3.57E+05 20,909 5,369 3,061 Yes 0.015 A2 Electrical Box A Quad Conduit to 33 33 3.57E+05 22,676 6,899 3,177 Yes 0.017 A3 Electrical Box A 21

Plum Brook Reactor Facility FSSR Attachment 9, Rev. 0 Table 7, Embedded Piping Survey Results for Co-60 Surrogate Piping Pipe Maximum Standard Average EP Dose EP ID # EP Description Length DCGL0u)Ma Acivt 2) ctivit Deiaio Actvit

_______ i f DG aiu enActivity Deviation 2 Activity (oeoy.

2 (dpm/00cm )

2 (dpm/100 cm ) <DCGL (mreinyr.)

(ft) N (dpm/100 cm ) (dpm/100 cm Quad B PCWS -

1.12-2.5 Instrumentation 6 6 3.85E+05 10,211 4,916 2,647 Yes 0.013 1.4 1-2.5 Hot Drain -

1NST iNTIsrmnain3 Instrumentation 3 3.57E+i05 16,505 7,336 8,069 Yes 0.020 1.42-2.5 14S. Waste Air -

InstenAio 7 7 3.85E+05 2,270 1,513 757 Yes 0.004 INST Instrumentation PCWR -

1.43-2 INST Instrumentation 1 1 3.85E+05 8,191 8,191 0 Yes 0.022 1.43-2.5 PCWR-14-. Ins Rm 5 5 3.85E+05 16,450 13,007 3,443 Yes 1NST Instrumentation 0.035 Rx-131 Spare to SPR 25 25 3.57E+05 37,877 11,197 8,847 Yes 0.029 Instrument line Rx-204 between access 10 10 3.57E+05 187,446 92,463 44,253 Yes 0.257 openings L&R Rx-205 Instrument line from 6 6 3.57E+05 56,544 38,897 9,724 Yes 0.108 access R to wall Instrument line from Rx____206H__ access L to wall 7 7 3.57E+05 53,740 26,245 24,370 Yes Instrument line from Rx 207 access Rto Access 3 3 3.57E+05 89,355 55,126 30,265 Yes 0.153 hatch Rx 208 Instrument line from 4 3.57E+05 20,081 15,061 6,096 Yes 0.042 Rx_____208____ access R to wall B Quad Conduit to 40 40 3.57E+05 6,919 4,044 1,255 Yes 0.012 B_1Electrical

_ Box D Quad Conduit to 39 39 3.57E+05 7,505 3,737 1,343 Yes 0.010 B2 Electrical Box D Quad Conduit to 29 29 3.57E+05 9,991 5,596 2,029 Yes 0.016 B3 Electrical Box A Quad Conduit to 28 28 3.57E+05 9,975 6,106 2,271 Yes 0.016 B4 Electrical Box A 2 22

Plum Brook Reactor Facility FSSR Attachment 9, Rev. 0 Table 7, Embedded Piping Survey Results for Co-60 Surrogate Piping Pipe # of DCGL (1) Maximum Mean Activity Standard Average EP Dose EPActivity 2 2 Deviation 2 Activity (rT EP Description Length N (dpm/100 cm ) (dpm/100 cm ) (dpm/100 cm ) <DCGL Quad C Rx-132 Spare to SPR 20 20 3.57E+05 5,587 3,173 1,865 Yes 0.014 1.12A-3 PCWS - Reactor Ring 48 48 3.85E+05 326,913 69,437 50,968 Yes 0.184 1.12B PCWS - Primary Loop 19 19 3.85E+05 343,193 59,691 73,191 Yes 0.151 to Reactor Ring 1.41A-4 Hot Drain - Reactor 48 48 3.85E+05 119,094 33,192 19,719 Yes 0.089 Ring I 1.41A-6 Hot Drain - Reactor 16 16 3.85E+05 133,411 32,787 28,206 Yes 0.086 Ring Waste Air - Reactor 1.42A-4 Ring 48 48 3.85E+05 36,966 16,122 8,968 Yes 0.037 Waste Air - Reactor 1.42A-6 Ring 15 15 3.85E+05 14,039 8,348 2,656 Yes 0.022 1.43A-4 PWCR Reactor Ring 48 48 3.85E+05 202,716 50,169 31,696 Yes 0.142 1.43A-6 PWCR Reactor Ring 16 16 3.85E+05 42,616 24,393 7,741 Yes 0.062 1.43A+B PWCR - Primary Loop 24 24 3.85E+05 317,641 99,799 72,011 Yes 0,261 to Reactor Ring C1 Quad Conduit to 0.014 Electrical Box D 32 32 3.57E+05 16,762 5,003 3,002 Yes C2 Quad Conduit to Electrical Box D 33 I 3.57E+05 13,069 6,279 2,916 Yes 0.015 Quad Conduit to C3 Electrical Box A 50 50 3.57E+05 25,517 5,764 3,777 Yes 0.016 Quad D Rx-116 SD Cooling Supply 3 3 3.57E+05 89,067 55,892 29,929 Yes 0.155 Rx-117 SD Cooling Return 8 8 3.57E+05 111,621 63,012 23,044 Yes 0.175 Rx-1.33 Spare to SPR 29 29 3.57E+05 7,675 4,397 1,397 Yes 0.012 Rx-138-1 Pump Seal Box Drain 22 8 3.85E+05 196,701 81,736 62,257 Yes 0.211 Rx-138-2 Pump Seal Box Drain 22 8 3.85E+05 44,823 32,564 7,662 Yes 0.086 Rx-138-3 Pump Seal Box Drain 22 7 3.85E+05 150,289 87,351 51,876 Yes 0.229 Rx-138-4 Pump Seal Box Drain 22 7 3.85E+05 18,456 14,660 3,074 Yes 0.038 D1 Quad Conduit to Electrical BoxD 34 34 3.57E+05 28,696 5,769 5,049 Yes 0.016 D2 Quad Conduit to Electrical BoxD 34 34 3.57E+05 13,627 5,067 2,917 Yes 0.014 23

Plum Brook Reactor Facility FSSR Attachment 9, Rev. 0 Table 7, Embedded Piping Survey Results for Co-60 Surrogate Piping Pipe # of DCGL () Maximum Mean Activity Standard Average EP Dose g N# m) Activity 2 Deviation 2 Activity t(ft) N (dpm/100 m2) (dpm/100 cm 2 ) (dpm/100 cm ) (dpm/100 cm ) <DCGL (mremlyr.)

Quad Conduit to 33 33 3.57E+05 8,179 3,895 1,993 Yes 0.011 D3 Electrical Box D Quad Conduit to D4 Electrical BoxA 45 45 3.57E+05 11,906 6,481 2,649 Yes 0.016 D5 D5Quad Electrical Box to Conduit A 44 44 3.57E+05 13,169 7,416 2,318 Yes 0.019 D6 D6Quad Electrical Box to Conduit A 44 44 3.57E+05 11,684 6,171 2,319 Yes 0.017 Reactor Building - Reactor Tank 201A PCWR from Quad A 7 7 3.57E+05 25,505 16,165 6,825 Yes 0.045 201B PCWR from Quad D 6 6 3.57E+05 14,576 7,652 4,373 Yes 0.021 202A PCWS from Quad A 5 5 3.57E+05 17,308 12,620 3,606 Yes 0.035 202B PCWS from Quad D 6 6 3.57E+05 46,968 25,505 5,900 Yes 0.073 Deion Water Sleeve 203A from Quad A 3.57E+05 18,834 6,519 8,330 Yes 0.018 Hot Drain Sleeve from 203B Quad B 7 3.57E+05 19,760 5,748 7,544 Yes 0.016 Rx 135A Pit Drain 6 6 3.57E+05 28,898 27,453 1,084 Yes 0.077 1.45A CA-RT Vent line to pit 7 7 3.85E+05 29,701 20,562 4,950 Yes 0.054 1.45B CA-RT Vent line to pit 4 4 3.85E+05 13,360 9,043 3,161 Yes 0.024 Reactor Building -15 ft elevation Rx-125 1st floor drains 127 127 3.57E+05 126,166 5,697 2,091 Yes 0.016 Rx-121 VSP sewer pipe with 66 66 3.85E+05 23,121 13,062 3,787 Yes 0.035 2" pipe inside Rx-15 Hot Cold Drain Rx-124 (RBCOl-) 215 215 3.85E+05 65,941 7,509 4,747 Yes 0.020 Rx-134 DR Drain Line 165 165 11,000 5,599 1,617 1,034 Yes 0.147 Reactor-Bowl CRT-1 Control Rod Tube 3 3 3.85E+05 30,262 12,861 15,888 Yes 0.034 CRT-2 Control Rod Tube 3 3 3.85E+05 51,054 20,574 26,289 Yes 0.055 CRT-3 Control Rod Tube 3 3 3.85E+05 69,208 24,089 39,001 Yes 0.063 CRT-4 Control Rod Tube 3 3 3.85E+05 46,497 17,532 25,154 Yes 0.046 CRT-5 Control Rod Tube 3 3 3.85E+05 31,767 12,248 17,223 Yes 0.032 CRT-6 Control Rod Tube 3 3 3.85E+05 32,904 12,243 17,982 Yes 0.032 CRT-7 Control Rod Tube 3 3 3.85E+05 62,322 23,323 34,029 Yes 0.061 24

Plum Brook Reactor Facility FSSR Attachment 9, Rev. 0 Table 7, Embedded Piping Survey Results for Co-60 Surrogate Piping Pipe # of DCGL ) Maximum Mean Activity Standard Average EP Dose EP ID # EP Description Length oCGL m2) Activity Deviation Activity (mremlyr.)

(ft) N (dpm/100 (dpm/100 cm 2) (dp 2 cm ) (dpm/100 cm 2) <DCGL CRT-8 Control Rod Tube 3 3 3.85E+05 30,029 11,699 15,989 Yes 0.030 CRT-9 Control Rod Tube 3 3 3.85E+05 21,695 14,512 11,599 Yes 0.040 CRT-10 Control Rod Tube 3 3 3.85E+05 30,633 13,019 16,082 Yes 0.034 IT-11 Instrument tube 3 3 3.85E+05 17,249 7,499 8,624 Yes 0.020 IT-12 Instrument tube 3 3 3.85E+05 7,800 6,240 1,560 Yes 0.016 IT-13 Instrument tube 3 3 3.85E+05 24,050 14,086 10,078 Yes 0.037 IT-14 Instrument tube 3 3 3.85E+05 50,050 22,159 24,452 Yes 0.058 VD-1 Vessel Drain 6 6 3.85E+05 99,003 61,711 22,615 Yes 0.162 Reactor Office And Laboratory Building ROLB-102 ROLB Floor Drains 343 343 1.13E+06 51,380 22,310 9,014 Yes 0.022 ROLB-111 Oil Storage Drain 27 27 1.13E+06 346,705 207,888 97,578 Yes 0.185 Table 7 Notes:

1. The DCGL is equivalent to the Embedded Pipe dose goal of 1 mrem/yr, as stated in Section 3.3 of the PBRF FSSP.

25

Plum Brook Reactor Facility FSSR Attachment 9, Rev. 0 Table 8, Embedded Piping Sur ey Results for Cs-137 Surrogate Piping Pipe of DCGL

• Maximum Mean A Standard Average EP Dose EP ID # EP Description Length # f cm) Activity Mn Deviation Activity ( Dom/s EPID_#EDescriptio Lngth(ft) N (dpm/100em (dpm/100 cm2 ) (dpm (dpm/100 cm2) <DCGL (mre yr.,

Pump Room 22 on -25 Foot Elevation of Reactor Building Rx-084 Trench drain to sump I 6 6 ] 1.94E+06 1 11,624 [ 9,687 1,937 Yes 0.005 HDS Valve Box, HDS & Off Gas 1.61 Canal K to valve pit 52 52 3.57E+05 155,402 55,156 27,882 Yes 0.155 Canal K vent to valve 1.62 pit 55 55 3.57E+05 144,585 16,588 21,147 Yes 0.047 1.63 Canal J to valve box 10 10 3.57E+05 279,596 99,749 6,977 Yes 0.277 1.83 HDS Floor drains 58 58 1.54E+06 27,951 6,604 3,686 Yes 0.004 1.84 Off Gas Hot Drain 23 23 1.54E+06 3,532 2,457 2,457 Yes 0.002 1.91 HDS to valve pit. 30 30 1.94E+06 60,834 10,849 10,461 Yes 0.006 1.92 Overflow from H)DS 8 8 1.54E+06 23,344 6,297 6,911 Yes 0.004 1.93 HDS Vent 24 24 1.54E+06 18,258 10,899 1,078 Yes 0.002 HL-1Il Canal J Vent 3 3 3.57E+05 8,538 7,244 2,069 Yes 0.028 Reactor Building -15 ft elevation CPT-16 CPT Trough drain 21 21 4.16E+05 11,006 7,568 1,896 Yes 0.019 SAN-12 North RB 16 16 1.54E+06 7,771 4,591 1,555 Yes 0.003 SAN-13 North RB 13 13 1.54E+06 6,101 4,477 1,535 Yes 0.003 Hot Pipe Tunnel HPT102 Pit Floor Drain 23 23 1.54E+06 5,682 2,671 1,103 Yes 0.002 HT Floor DrainsI HPT-104 (FD-1 thru FD-8) 273 273 1.94E+06 40,784 9,749 7,696 Yes 0.005 HPT-105 BL Off Gas Drains 25 25 1.94E+06 26,431 13,629 4,601 Yes 0.007 Reactor Office And Laboratory Building ROLB-109 Elevator Shaft Drain 3 3 1.13E+06 4,270 3,202 1,068 Yes 0.003 Fan House FH-102 Floor Drain 113 113 1.94E+06 356,886 41,949 52,694 Yes 0.022 FH-103 Drain to Resin Pit 15 15 1.94E+06 10,404 6,309 2,429 Yes 0.003 FH-111 Chase Drain 2 2 1.94E+06 57,282 52,236 3,945 Yes 0.027 Waste Handling Building WHB-111 1 Evap/LaundrySupply 180 180 2.16E+06 92,966 38,469 8,581 Yes 0.018 thru 6 and Drains I I Table 8 Notes:

1. The DCGL is equivalent to the Embedded Pipe dose goal of 1 mrem/yr, as stated in Section 3.3 of the PBRF FSSP.

26

Plum Brook Reactor Facility FSSR Attachment 9, Rev. 0 5.3 Quality Control The quality of piping radiological survey measurements was assured by the diligent application of numerous quality control protocols delineated in the implementing procedures and review criteria for EP field activities, detector quality control documents and survey assessment. All activities are directed by procedures, and all procedures used are PBRF approved procedures.

All instrument and detector calibrations are performed by qualified off-site vendor(s) calibrating with standards traceable to the National Institute of Standards and Technology, derived from accepted values natural physical constants or derived by the ratio-type of calibration techniques.

After calibration and prior to use, detector quality control charts are developed for each detector. These charts establish an expected detector response to a radioactive source standard and background radiation. The acceptable range for satisfactory performance is plus or minus 20% for the established source and background count rates. Satisfactory checks against these source and background radiation values are performed prior to and after any efficiency determinations or field survey measurements. These checks bound measurement data and assure its accuracy.

Efficiency determinations are performed using certified sources traceable to the National Institute of Standards and Technology. Drawings accompany all efficiency determinations which specify the in-situ geometry, detectors, radioactive sources and all other pertinent specifics allowing accurate reproduction of efficiency determinations at future dates.

The survey technician is required to verify the detector-sled-pipe size and nuclide of concern prior to acquiring survey data. All field survey documentation captures the date, time, access location, physical location within the facility, and identies the pipe run being surveyed.

5.4 ALARA Evaluation It is shown that residual contamination in the EP 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, those 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 is presumed that it had been reduced to levels that are ALARA. Therefore, the licensee does not need to conduct an 6

explicit analysis to meet the ALARA requirement."

6 This guidance was initially published in Draft Regulatory Guide DG-4006, but has been reissued in NUREG-1757 Volume 2, Appendix N [USNRC 2006].

27

Plum Brook Reactor Facility FSSR Attachment 9, Rev. 0 Comparison of EP survey results to NRC generic soil screening levels is not applicable.

However, the highest dose attributed to any of the EP identified in this report is 1.366 mRem/yr associated with EP 1.12, which is the 24 inch diameter Primary Coolant Supply line. The dose from all other EP dose is less than this value and most of the piping is significantly below this value. The PBRF dose goal for EP was 1 mrem/yr. However, in accordance with Section 3.3 of the PBRF FSSP, different dose goals could be applied in different areas as long as the residual contamination on the structure surface in the survey unit containing the given EP is sufficiently low to allow for the selected dose goal. The dose attributed to EP, as identified in Table 7 and Table 8 of this report, is added to the dose of any structural surface survey units which coincide with EP in Appendix C of this report. As presented in Appendix C, the combined dose of all EP and structure survey units is < 25 mrem/yr.7 The dose attributed to EP at PBRF from the EP surveys is ALARA since the EP survey results indicate the dose from 165 EP surveys is less than or equal to the dose goal of 1 mrem/yr as identified in the FSSP, except for EP 1.11 and EP 1.12. The dose attributed to these two piping runs is 1.009 mrem/yr for EP 1.11 and 1.366 mrem/yr for EP 1.12. However the modified dose goal (2 mrem/yr) when combined with the coinciding structural survey unit dose estimate is significantly less than 25 mrem/yr. The addition of EP dose did not result in any structure survey unit's total dose reaching the 22.5 mrem/yr threshold for additional review in accordance with section 3.5 of the FSSP.

The cost of removing the piping is high and far more costly than justified by the Nuclear Regulatory Commission (NRC) $2000/person-rem ALARA standard. The operational phase of removing the Primary Cooling Loop was estimated to consume fifty-nine (59) weeks of schedule duration at an estimated cost of eight million to ten million dollars ($8,000,000-

$10,000,000). The addition of removing the embedded Quadrant and Canal piping would have further increased that cost by approximately one million to one million, two hundred fifty thousand dollars (-$1,000,000-$1,250,000). In total, the estimated costs associated with removing the PBRF's EP systems would have ranged, more or less, from nine million dollars to eleven million, two hundred fifty thousand dollars ($9,000,000-$11,250,000).

Once the preliminary estimates of costs associated with the removal of the PBRF embedded systems were thoroughly evaluated, it was decided that the more prudent and logical course of action would be that of surveying the EP conduits, decontaminating the same as necessary to either meet the DCGL values or ALARA, and subsequently leave the EP in place.

5.5 EPA Trigger Values 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). Concentrations of individual radionuclides, identified as "trigger levels" for further review and consultation between the agencies, are published in the MOU. However, no soil 7 As stated in the PBRF 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/yr. 10CFR20 Subpart E also requires that residual contamination be reduced to levels as low as reasonably achievable (ALARA).

28

Plum Brook Reactor Facility FSSR Attachment 9, Rev. 0 survey units are included in the survey of the EP. It is also noted that groundwater is not within the scope of the EP survey effort. Therefore, comparison 8 with EPA Trigger Levels is not applicable to EP survey measurement results.

5.6 Conclusions The results presented above demonstrate that the EP satisfies all FSS Plan commitments and meets the release criteria in 10CFR20 Subpart E. The principal conclusions are:

• Radiation surveys were conducted on 167 runs of EP.

• The highest dose associated with any EP survey is 1.366 mrem/yr from EP 1.12, which is a 24 inch diameter Primary Loop Coolant line.

• The dose attributed to 165 out of 167 EP surveys, was < 1 mRem/yr. Most of the EP dose for each piping run is < 0.10 mRem/yr.

• The highest combined structure and EP dose is 6.84 mrem/yr, this dose is only 27%

of the allowed dose of 25 mrem/yr to be in compliance with the release criterion.

• The EP surveys identified in this report meet the ALARA principle identified by the NRC.

" Therefore, the PBRF piping defined as EP, and discussed in this Attachment, meets the criteria for unrestricted release 8 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. Since these trigger levels are only applicable to the PBRF for residual soil and water concentrations, they do not apply to the Embedded Piping results provided in this attachment.

29

Plum Brook Reactor Facility FSSR Attachment 9, Rev. 0 6.0 References 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 2006 Plum Brook Reactor Facility Technical Basis Document, Calculationof PBRF Embedded PipingDCGLs with Revised Conceptual Dose Model, PBRF-TBD-06-00 1, Revision 0, March 2006.

PBRF 2006a Plum Brook Reactor Facility Technical Basis Document, Evaluation of Radionuclide Profiles in Embedded and BuriedPipingat the Plum Brook Reactor Facility,PBRF-TBD-06-003, Revision 0, January 2006.

PBRF 2006b Plum Brook Reactor Facility Technical Basis Document, Activity Ratios of Radionuclidesin Embedded and Buried Piping,PBRF-TBD-06-004, Revision 0, October 2006.

PBRF 2005 PBRF-WEP-05-006, Decontamination& RadiologicalSurvey of Embedded and BuriedPipng Systems.

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

USNRC 2006 US Nuclear Regulatory Commission, ConsolidatedDecommissioningGuidance, NUREG-1757, Vol. 1, Rev.2, September 2006.

USEPA 2002 Memorandum of Understanding, US Environmental Protection Agency and US Nuclear Regulatory Commission, Consultation and Finalityon Decommissioningand Decontaminationof ContaminatedSites, October 9, 2002.

30

Plum Brook Reactor Facility FSSR Attachment 9, Rev. 0 7.0 Appendices Appendix A - Exhibits Appendix B - Embedded Piping Penetration Location Maps Appendix C - Structural Survey Unit/Embedded Piping Dose Tables Appendix D - Primary Cooling Piping, EP 1.11 & EP 1.12.

31

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix A Rev.0, Page 1 of 12 Plum Brook Reactor Facility Final Status Survey Report Attachment 9 Embedded Piping Revision 0 Appendix A Exhibits

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix A Rev.0, Page 2 of 12 List of Exhibits Exhibit 1, Video Inspection of Embedded Piping in Reactor Building ............................................ 3 Exhibit 2, HEPA Ventilation Unit ...................................................................................................... 4 Exhibit 3, Tanks to Capture Hydrolazer W ater .................................................................................. 5 Exhibit 4, Setting up for Cleaning of Embedded Piping .................................................................... 6 Exhibit 5, Cleaning the Embedded Piping ......................................................................................... 7 Exhibit 6, NLB Hydrolazer Unit ....................................................................................................... 8 Exhibit 7, Embedded Pipe Survey Sled ............................................................................................. 9 Exhibit 8, Embedded Pipe Cleaning ................................................................................................ 10 Exhibit 9, Embedded Piping Survey .................................................................................................... 11 Exhibit 10, Detector-Sled-Pipe and Cable Set-up ........................................................................... 12

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix A Rev.0, Page 3 of 12 Exhibit 1, Video Inspection of Embedded Piping in Reactor Building

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix A Rev.0, Page 4 of 12 Exhibit 2, HEPA Ventilation Unit I

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix A Rev.0, Page 5 of 12 Exhibit 3, Tanks to Capture Hydrolazer Water

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix A Rev.0, Page 6 of 12 Exhibit 4, Setting up for Cleaning of Embedded Piping

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix A Rev.0, Page 7 of 12 Exhibit 5, Cleaning the Embedded Piping

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix A Rev.0, Page 8 of 12 Exhibit 6, NLB Hydrolazer Unit

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix A Rev.0, Page 9 of 12 Exhibit 7, Embedded Pipe Survey Sled 25

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix A Rev.0, Page 10 of 12 Exhibit 8, Embedded Pipe Cleaning

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix A Rev.0, Page 11 of 12 Exhibit 9, Embedded Piping Survey

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix A Rev.0, Page 12 of 12 Exhibit 10, Detector-Sled-Pipe and Cable Set-up

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix B Rev.0, Page 1 of 20 Plum Brook Reactor Facility Final Status Survey Report Attachment 9 Embedded Piping Revision 0 Appendix B Embedded Piping Penetration Location Maps

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix B Rev.0, Page 2 of 20 Table of Contents M ap 1, Drain Trench on Reactor Building -25 Foot Elevation ..................................... 3 M ap 2, Pump Room on Reactor Building -25 Foot Elevation ........................................ 4 M ap 3, CV -25 Foot Elevation ....................................................................................... 5 M ap 4, ROLB -15 Foot Elevation ................................................................................... 6 M ap 5, CV, Sub Pile & Corridor .................................................................................... 7 M ap 6, Quad A ........................................................................................................... 8 M ap 7, Quad B ........................................................................................................... 9 M ap 8, Quad C .................................................................................................................. 10 M ap 9, Quad D .................................................................................................................. 11 M ap 10, Canal E ............................................................................................................... 12 M ap 11, Canals F, G, H, J & K ......................................................................................... 13 M ap 12, Reactor Tank ................................................................................................... 14 M ap 13, Reactor Vessel, -15 Foot Elevation and Vessel Bowl .................................... 15 M ap 14, Reactor Building -15 Foot Elevation ............................................................. 16 M ap 15, Fan House -15 Foot Elevation ......................................................................... 17 Map 16, Hot Pipe Tunnel .............................................................................................. 18 Map 17, HDS Valve Box .............................................................................................. 19 M ap 18, W aste Handling Building ............................................................................... 20

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix B Rev.0, Page 3 of 20 Map 1, Drain Trench on Reactor Building -25 Foot Elevation Rx-125 Rx-124 L44 1 Ej,

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix B Rev.0, Page 4 of 20 Map 2, Pump Room on Reactor Building -25 Foot Elevation

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix B Rev.0, Page 5 of 20 Map 3, CV -25 Foot Elevation

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix B Rev.0, Page 6 of 20 Map 4, ROLB -15 Foot Elevation

[]

03 03

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix B Rev.0, Page 7 of 20 Map 5, CV, Sub Pile & Corridor

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix B Rev.0, Page 8 of 20 Map 6, Quad A Quad A

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix B Rev.0, Page 9 of 20 Map 7, Quad B Quad B RX-152 1.38.1

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix B Rev.0, Page 10 of 20 Map 8, Quad C Quad C N 0

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix B Rev.0, Page 11 of 20 Map 9, Quad D Quad D (- N

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix B Rev.0, Page 12 of 20 Map 10, Canal E Canal E T N

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix B Rev.0, Page 13 of 20 Map 11, Canals F, G, H, J & K IN Canal K

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix B Rev.0, Page 14 of 20 Map 12, Reactor Building Reactor Tank

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix B Rev.0, Page 15 of 20 Map 13, Reactor Vessel, -15 Foot Elevation and Vessel Bowl Column 7 Thermal IKý1ý EID--i,

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix B Rev.0, Page 16 of 20 Map 14, Reactor Building -15 Foot Elevation

• x,*I*x,* l~~SA Rx124 12lxI24IRials** x

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix B Rev.0, Page 17 of 20 Map 15, Fan House -15 Foot Elevation

,0

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix B Rev.0, Page 18 of 20 Map 16, Hot Pipe Tunnel 0

N

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix B Rev.0, Page 19 of 20 Map 17, HDS Valve Box CANAL F CANAL G 722 CANAL E

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix B Rev.0, Page 20 of 20 Map 18, Waste Handling Building 0

NT

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix C Rev.0, Page 1 of 12 Plum Brook Reactor Facility Final Status Survey Report Attachment 9 Embedded Piping Revision 0 Appendix C Structural Survey Unit/Embedded Piping Dose Tables

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix C Rev.0, Page 2 of 12 Table of Contents T ab le 1. ............................................................................................................................ 3.

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix C Rev.0, Page 3 of 12 PBRF FSSR Attachment 9, Appendix C, Table 1 Structural Survey Units with EP Contributing Highest Location Highest Structural Highest EP Highest Possible Embedded Pipe Present mremlyr to Structural SU SU mremlyr Value mremlyr Value Combined mremlyr Value FSSR, Aft. 1, Rev. I RO-3-1 ROLB-111 Area Way 1.03 0.19 1.22 RO-3-2 ROLB-111 Vestibule, Men's Room, Cold Test Area 1.03 0.19 1.22 RO-3-3 ROLB-111 Cold Test Area 1.03 0.19 1.22 RO-3-4 ROLB-111 Cold Test Area and Vault 1.03 0.19 1.22 RO-3-5 ROLB-111 Sump Room, Sumps, Elevator Sump 1.03 0.19 1.22 FSSR, ACt. 2, Rev. 1 SE-3-1 CPT-16 Cold Pipe Tunnel - Floor Section 1 Fl 6.82 0.02 6.84 SE-3-2 CPT-16 Cold Pipe Tunnel - Floor Section 2 Fl 6.82 0.02 6.84 SE-3-3 CPT-16 Cold Pipe Tunnel - Floor Section 3 Fl 6.82 0.02 6.84 SE-3-4 CPT-16 Cold Pipe Tunnel - Floor Section 4 Fl 6.82 0.02 6.84 SE-3-5 CPT-16 Cold Pipe Tunnel - Floor Section 5 Fl 6.82 0.02 6.84 SE-3-6 CPT-16 Cold Pipe Tunnel - Floor Section 6 Fl 6.82 0.02 6.84 SE-3-7 CPT-16 Cold Pipe Tunnel - Floor Section 7 Fl 6.82 0.02 6.84 SE-3-8 CPT-16 Cold Pipe Tunnel - Floor Section 8 Fl 6.82 0.02 6.84 SE-3-9 CPT-16 Cold Pipe Tunnel - North Wall Section 1 Lw 6.82 0.02 6.84 SE-3-1 0 CPT-16 Cold Pipe Tunnel - North Wall Section 2 Lw 6.82 0.02 6.84 SE-3-11 CPT-16 Cold Pipe Tunnel - North Wall Section 3 Lw 6.82 0.02 6.84 SE-3-12 CPT-16 Cold Pipe Tunnel - North Wall Section 4 Lw 6.82 0.02 6.84 SE-3-13 CPT-16 Cold Pipe Tunnel - North Wall Section 5 Lw 6.82 0.02 6.84 SE-3-14 CPT-16 Cold Pipe Tunnel - South Wall Section 1 Lw 6.82 0.02 6.84 SE-3-15 CPT-16 Cold Pipe Tunnel - South Wall Section 2 Lw 6.82 0.02 6.84 SE-3-16 CPT-16 Cold Pipe Tunnel - South Wall Section 3 Lw 6.82 0.02 6.84 SE-3-17 CPT-16 Cold Pipe Tunnel - South Wall Section 4 Lw 6.82 0.02 6.84 PBRF FSSR Attachment 9, Appendix C, Table 1

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix C Rev.0, Page 4 of 12 Structural Survey Units with EP Contributing Highest Location Highest Structural Highest EP Highest Possible Embedded Pipe Present mrem/yr to Structural SU SU mrem/yr Value mrem/yr Value Combined mremlyr Value FSSR, Aft. 2, Rev. I SE-3-18 CPT-16 Cold Pipe Tunnel - South Wall Section 5 Lw 6.82 0.02 6.84 SE-3-19 CPT-16 CPT - Ceiling Section 1Ceiling 6.82 0.02 6.84 SE-3-20 CPT-16 CPT - Ceiling Section 2 Ceiling 6.82 0.02 6.84 SE-3-21 CPT-16 CPT - Ceiling Section 3 Ceiling 6.82 0.02 6.84 SE-3-22 CPT-16 CPT - Ceiling Section 4 Ceiling 6.82 0.02 6.84 SE-3-23 CPT-16 CPT - Ceiling Section 5 Ceiling 6.82 0.02 6.84 SE-3-24 CPT-16 CPT - Ceiling Section 6 Ceiling 6.82 0.02 6.84 SE-3-25 CPT-16 CPT - Ceiling Section 7 Ceiling 6.82 0.02 6.84 SE-3-26 CPT-16 CPT - Cooling Tower Basin Tunnel Floor 6.82 0.02 6.84 SE-3-27 CPT-16 CPT - CTB Tunnel S&W Walls Lw 6.82 0.02 6.84 SE-3-28 CPT-16 CPT - CTB Tunnel N&E Walls Lw 6.82 0.02 6.84 SE-3-29 CPT-16 CPT - CTB Tunnel Ceiling 6.82 0.02 6.84 SE-3-30 CPT-16 CPT - Connecting Tunnel Fl 6.82 0.02 6.84 SE-3-31 CPT-16 CPT - Connecting Tunnel Lw 6.82 0.02 6.84 SE-3-32 CPT-16 Basement Class 2 Areas Fl 1.20 0.02 1.22 FSSR, Aft. 3, Rev. 1 FH-2-1 FH-1 11 Basement - Floor - Section 1 2.54 0.03 2.57 FH-2-2 FH-1 11 Basement - Floor - Section 2 2.54 0.03 2.57 FH-2-3 FH-1 11 Basement - Floor - Section 3 2.54 0.03 2.57 FH-2-4 FH-1 11 Basement - Floor - Section 4 2.54 0.03 2.57 FH-2-5 FH-1 11 Basement - Floor - Section 5 2.54 0.03 2.57 FH-2-6 FH-1 11 Basement - Floor - Stairs &Valve Pit 2.54 0.03 2.57 PBRF FSSR Attachment 9, Appendix C, Table 1

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix C Rev.0, Page 5 of 12 Structural Survey Units with EP Contributing Highest Location Highest Structural Highest EP Highest Possible Embedded Pipe Present mrem/yr to Structural SU SU mrem/yr Value mrem/yr Value Combined mremlyr Value FSSR, Aft. 6, Rev. I WH-3-2 WHB-1 111 thru 6 WHB Basement Trench - Concrete Edges 0.36 0.02 0.38 WH-3-11 WHB-111 1 thru 6 WHB Basement Floor- Section 1 0.36 0.02 0.38 WH-3-12 WHB-111 1 thru 6 WHB Basement Floor- Section 2 0.36 0.02 0.38 WH-3-13 WHB-1 111 thru 6 WHB Basement Floor Section 3 &Sumps 0.36 0.02 0.38 FSSR, Aft. 8 HL-3-1 HPT-104 HPT - Floor- Section 1 &Sump 0.89 0.01 0.90 HL-3-2 HPT-104 HPT - Floor- Section 2 0.89 0.01 0.90 HL-3-3 HPT-104 HPT - Floor- Section 3 0.89 0.01 0.90 HL-3-4 HPT-104 HPT - Floor - Section 4 0.89 0.01 0.90 HL-3-5 HPT-104 HPT - Floor- Section 5 0.89 0.01 0.90 HL-3-6 HPT-104 HPT - Corrugated Pipe Tunnel - Section 1 0.89 0.01 0.90 HL-3-7 HPT-104 HPT - Corrugated Pipe Tunnel - Section 2 0.89 0.01 0.90 HL-3-8 HPT-104 HPT - Corrugated Pipe Tunnel - Section 3 0.89 0.01 0.90 HL-3-9 HPT-104 HPT - Walls - Section 1 0.89 0.01 0.90 HL-3-10 HPT-104 HPT - Walls - Section 2 0.89 0.01 0.90 HL-3-11 HPT-104 HPT - Walls - Section 3 0.89 0.01 0.90 HL-3-12 HPT-104 HPT - Walls - Section 4 0.89 0.01 0.90 HL-3-13 HPT-104 HPT - Walls - Section 5 0.89 0.01 0.90 HL-3-14 HPT-104 HPT - Walls - Section 6 0.89 0.01 0.90 HL-3-15 HPT-104 HPT - Ceiling - Section 1 0.89 0.01 0.90 HL-3-16 HPT-104 HPT - Ceiling - Section 2 0.89 0.01 0.90 HL-3-17 HPT-104 HPT - Ceiling - Section 3 0.89 0.01 0.90 HL-3-18 HPT-104 HPT - Ceiling - Section 4 0.89 0.01 0.90 PBRF FSSR Attachment 9, Appendix C, Table 1

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix C Rev.0, Page 6 of 12 Structural Survey Units with EP Contributing Highest Location Highest Structural Highest EP Highest Possible Embedded Pipe Present mremlyr to Structural SU SU mremlyr Value mremlyr Value Combined mrem/yr Value FSSR, Aft. 8 HL-3-19 HPT-104 HPT - Ceiling - Vents &Penetrations 0.89 0.01 0.90 HL-3-21 HPT-104 HPT - Floor - edges of removed section 0.89 0.01 0.90 HL-4-1 HPT-105 Off-Gas - Floor, 6'6" Walkway, North Wall 1.58 0.01 1.59 HL-4-2 HPT-105 Off-Gas - North &East Walls 1.58 0.01 1.59 HL-4-3 HPT-105 Off-Gas - South &West Walls 1.58 0.01 1.59 HL-4-4 HPT-105 HDS - Beam 0.74 0.01 0.75 HL-4-5 HPT-105 HDS - Floor - West section 1.58 0.01 1.59 HL-4-6 HPT-105 HDS - Floor - East section 1.58 0.01 1.59 HL-4-7 HPT-105 HDS - North Wall &Observation Window 0.74 0.01 0.75 HL-4-8 HPT-105 HDS - West Wall 0.74 0.01 0.75 HL-4-9 HPT-105 HDS - East Wall below beam 1.58 0.01 1.59 HL-4-10 HPT-105 HDS- South Wall &East Wall above beam 0.74 0.01 0.75 HL-4-11 HPT-105 Interim Storage - Floor and Pit 1.58 0.01 1.59 HL-4-12 HPT-105 Interim Storage - East &West Walls 0.74 0.01 0.75 HL-4-13 HPT-105 Interim Storage - North &South Walls and 0.74 0.01 0.75 HL-4-14 1.61 Canal K- Floor 0.53 0.16 0.69 HL-4-15 1.61 Canal K- North Wall 0.53 0.16 0.69 HL-4-16 1.61 Canal K- East Wall &South Wall 0.53 0.16 0.69 HL-4-17 1.61 Canal K- West Wall &South Wall 0.53 0.16 0.69 HL-4-18 1.63 Canal J - Floor 0.58 0.28 0.86 HL-4-18 1.63 Canal J - Floor 0.58 0.28 0.86 HL-4-19 1.63 Canal J - West Wall - North Section 0.58 0.28 0.86 HL-4-20 1.63 Canal J - East Wall - North Section 0.58 0.28 0.86

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix C Rev.0, Page 7 of 12 PBRF FSSR Attachment 9, Appendix C, Table 1 Structural Survey Units with EP Contributing Highest Location Highest Structural Highest EP Highest Possible Embedded Pipe Present mremlyr to Structural SU SU mrem/yr Value mremlyr Value Combined mremlyr Value FSSR, Att. 8 HL-4-21 1.63 Canal J - E &W Walls - South Section 0.58 0.28 0.86 FSSR, Aft. 11 CV-3-1 RX-135 Sub-Pile Room - Floor and Liner Floor 1.63 0.16 1.79 CV-3-2 RX-135 Sub-Pile Room - South Wall, Elevator walls 1.63 0.16 1.79 CV-3-3 RX-135 Sub-Pile Room - Ceiling, North Wall 1.63 0.16 1.79 CV-3-4 EP 1.12 Bio-Shield Lower 0.94 1.37 2.31 CV-3-5 EP 1.12 Bio-Shield Upper 0.94 1.37 2.31 CV-3-6 1.72A Canal E - West Floor Section and Doorway 0.62 0.04 0.66 CV-3-7 1.72A Canal E - East Floor Section 0.62 0.04 0.66 CV-3-8 1.72A Canal E - Wall Section #1 0.62 0.04 0.66 CV-3-9 1.72A Canal E - Wall Section #2 0.62 0.04 0.66 CV-3-10 1.72A Canal E - Wall Section #3 0.62 0.04 0.66 CV-3-11 1.72A Canal E - Wall Section #4 0.62 0.04 0.66 CV-3-12 1.72A Canal E - Wall Section #5 0.62 0.04 0.66 CV-3-13 1.72A Canal E - Wall Section #6 0.62 0.04 0.66 CV-3-14 1.72A Canal E - Ceiling 0.62 0.04 0.66 CV-3-15 RX-139 CV -25' Reactor Annulus -West Floor 0.55 0.13 0.68 CV-3-16 RX-139 CV -25' Reactor Annulus - North Floor 0.55 0.13 0.68 CV-3-17 RX-139 CV -25' Reactor Annulus - East Floor 0.55 0.13 0.68 CV-3-18 RX-139 CV -25' Reactor Annulus - Cave 0.55 0.13 0.68 CV-3-19 RX-139 CV-25' Reactor Annulus - East Platform 0.55 0.13 0.68 CV-3-20 RX-139 CV -25' Reactor Annulus - West Stairs 0.55 0.13 0.68 CV-3-21 RX-139 CV -25' Reactor Annulus - East Stairs 0.55 0.13 0.68

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix C Rev.0, Page 8 of 12 PBRF FSSR Attachment 9, Appendix C, Table 1 Structural Survey Units with EP Contributing Highest Highest Highest EP Highest Possible Embedded Pipe Present mremlyr to Structural SU Location Structural SU ghest Combined mrem/yr EmbededipePresnt remrtoStrc S mremr Value mrem/yr Value Value FSSR, Att. 11 CV-3-22 RX-139 CV -25' Reactor Annulus - West End Wall 0.55 0.13 0.68 CV-3-23 RX-139 CV-25' Reactor Annulus/Inner Wall Sect. #2 0.55 0.13 0.68 CV-3-24 RX-139 CV -25' Reactor Annulus/Inner Wall Sect. #3 0.55 0.13 0.68 CV-3-25 RX-139 CV -25' Reactor Annulus/Inner Wall Sect. #4 0.55 0.13 0.68 CV-3-26 RX-139 CV -25' Reactor Annulus/Outer Wall Sect. #1 0.55 0.13 0.68 CV-3-27 RX-139 CV -25' Reactor Annulus/Outer Wall Sect. #2 0.55 0.13 0.68 CV-3-28 RX-139 CV -25' Reactor Annulus/Outer Wall Sect. #3 0.55 0.13 0.68 CV-3-29 RX-139 CV -25' Reactor Annulus/Outer Wall Sect. #4 0.55 0.13 0.68 CV-3-30 RX-139 CV -25' Reactor Annulus/Outer Wall Sect. #5 0.55 0.13 0.68 CV-3-31 RX-139 CV -25' Reactor Annulus/West Ceiling 0.55 0.13 0.68 CV-3-32 RX-139 CV -25' Reactor Annulus/East Ceiling 0.55 0.13 0.68 CV-3-33 EP 1.12 Quads B &D 0.05 1.37 1.42 CV-3-34 EP 1.12 Quads B &D 0.05 1.37 1.42 CV-3-35 EP 1.12 Quads B &D 0.05 1.37 1.42 CV-3-36 EP 1.12 Quads B &D 0.05 1.37 1.42 CV-3-37 EP 1.12 Quads B &D 0.05 1.37 1.42 CV-3-38 EP 1.12 Quads B &D 0.05 1.37 1.42 CV-3-39 EP 1.12 Quads B &D 0.05 1.37 1.42 CV-3-40 EP 1.12 Quads B &D 0.05 1.37 1.42 CV-3-41 1.43 A+ B CV -25'- Quad A- Floor 1.87 0.26 2.13 CV-3-42 1.43 A + B CV -25' - Quad A- NWall, Reactor, &S Wall 1.87 0.26 2.13 CV-3-43 1.43 A + B CV -25'- Quad A - South Wall &Canal E Doorway 1.87 0.26 2.13 CV-3-44 1.43 A + B CV -25'- Quad A -West Wall 1.87 0.26 2.13

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix C Rev.0, Page 9 of 12 PBRF FSSR Attachment 9, Appendix C, Table 1 Structural Survey Units with EP Contributing Highest Location Highest Structural Highest EP Highest Possible Embedded Pipe Present mremlyr to Structural SU SU mrem/yr Value mrem/yr Value Combined mrem/yr Value FSSR, Aft. 11 CV-3-45 1.43 A + B CV -25'- Quad C - Floor 1.87 0.26 2.13 CV-3-46 1.43 A + B CV-25' - Quad C - NWall, Rx Wall, &S Wall 1.87 0.26 2.13 CV-3-47 1.43 A + B CV -25'- Quad C - East Wall 1.87 0.26 2.13 CV-3-48 1.43 A + B CV -25'- Quad C - S Wall &Canal E Door 1.87 0.26 2.13 FSSR, Aft. 12 RB-3-3 RX-134 RB -15' - Floor Section #1 0.94 0.15 1.09 RB-3-4 RX-134 RB -15' - Floor Section #2 0.94 0.15 1.09 RB-3-5 RX-134 RB -15' - Floor Section #3 0.94 0.15 1.09 RB-3-6 RX-134 RB -15'- Floor Section #4 0.94 0.15 1.09 RB-3-7 RX-134 RB -15' - Floor Section #5 0.94 0.15 1.09 RB-3-8 RX-134 RB -15' - Floor Section #6 0.94 0.15 1.09 RB-3-9 RX-134 RB -15'- Floor Section #7 0.94 0.15 1.09 RB-3-10 RX-134 RB -15'- Floor Section #8 0.94 0.15 1.09 RB-3-11 RX-134 RB -15'- Floor Section #9 0.94 0.15 1.09 RB-3-12 RX-134 RB -15'- Floor Section #10 0.94 0.15 1.09 RB-3-13 RX-134 RB -15' - East Stairway 0.94 0.15 1.09 RB-3-14 RX-134 RB -15'- West Stairway 0.94 0.15 1.09 RB-3-15 RX-134 RB -15'- Wall Section #1 0.94 0.15 1.09 RB-3-16 RX-134 RB -15'- Wall Section #2 0.94 0.15 1.09 RB-3-17 RX-134 RB -15' - Wall Section #3 0.94 0.15 1.09 RB-3-18 RX-134 RB -15'- Wall Section #4 0.94 0.15 1.09 RB-3-19 RX-134 RB -15' - Wall Section #5 0.94 0.15 1.09 RB-3-20 RX-134 RB -15' - Wall Section #6 0.94 0.15 1.09

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix C Rev.0, Page 10 of 12 PBRF FSSR Attachment 9, Appendix C, Table 1 Structural Survey Units with EP Contributing Highest Location Highest Structural Highest EP Highest Possible Embedded Pipe Present mremlyr to Structural SU SU mremlyr Value mrem/yr Value Combined mremlyr Value FSSR, Aft. 12 RB-3-21 RX-134 RB -15'- Wall Section #7 0.94 0.15 1.09 RB-3-22 RX-134 RB -15' -Wall Section #8 0.94 0.15 1.09 RB-3-23 RX-134 RB -15'- ATS Tunnel Entrance 0.94 0.15 1.09 RB-3-24 RX-134 RB -15'- Ceiling Section #1 0.94 0.15 1.09 RB-3-39 RX-134 RB -15' -West Columns 0.94 0.15 1.09 RB-4-1 1.36 Canal F - Floor including F-J and F-H doorway 0.65 0.03 0.68 RB-4-2 1.36 Canal F -West &North Walls 0.65 0.03 0.68 R134-3 1.36 Canal F - East Wall &F-J doorway sides 0.65 0.03 0.68 RB-4-4 1.36 Canal F - Catwalk steel &undersides 0.65 0.03 0.68 RB-4-5 1.36 Canal G - Floor &G-H doorway 0.65 0.03 0.68 RB-4-6 1.36 Canal G - North Wall 0.65 0.03 0.68 RB-4-7 1.36 Canal G - E &WWalls, &S Wall lower 4m 0.65 0.03 0.68 R134-8 1.36 Canal G - S Wall >4m, G &Hwalkway 0.65 0.03 0.68 RB-4-9 1.36 Canal H - Floor 0.65 0.03 0.68 RB-4-10 1.36 Canal H- W &N Walls, G-H doorway sides 0.65 0.03 0.68 RB-4-11 1.36 Canal H - S &E Walls 0.65 0.03 0.68 RB-4-12 1.44 RB -25'- Trench bottom &Pit sides 4.92 0.21 5.13 RB-4-13 1.44 RB -25'- Trench sides 4.92 0.21 5.13 RB-4-14 1.44 RB -25'- Floor Section #1- East Floor 4.92 0.21 5.13 RB-4-15 1.44 RB -25'- Floor Section #2 - SE &South Floor 4.92 0.21 5.13 RB-4-16 1.44 RB -25'- Floor Section #3- Ctr Floor &Pad 4.92 0.21 5.13 RB-4-17 1.44 RB -25' - Floor Section #4 - N Floor &Strway 4.92 0.21 5.13 RB-4-18 1.44 RB -25'- PR Main Trench Fir &Pipe Chase 4.92 0.21 5.13

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix C Rev.0, Page 11 of 12 PBRF FSSR Attachment 9, Appendix C, Table 1 Structural Survey Units EP Contributing Highest Highest EP Highest Possible with Embedded Pipe Highest mremryr to Location Structural SU mrem/yr Combined mrem/yr Present Structural SU mrem/yr Value Value Value FSSR, Aft. 12 RB-4-19 1.44 RB -25'- Pump Room Main Trench Walls 4.92 0.21 5.13 RB-4-20 1.44 RB -25'- Pump Room Floor &Pump Services Trench 4.92 0.21 5.13 RB-4-21 1.44 RB -25'- Wall Section #1 4.92 0.21 5.13 RB-4-22 1.44 RB -25'- Wall Section #2 4.92 0.21 5.13 RB-4-23 1.44 RB -25'- Wall Section #3 4.92 0.21 5.13 RB-4-24 1.44 RB -25'- Wall Section #4 4.92 0.21 5.13 RB-4-25 1.44 RB -25'- Wall Section #5 4.92 0.21 5.13 RB-4-26 1.44 RB -25'- Wall Section #6 4.92 0.21 5.13 RB-4-27 1.44 RB -25'- Wall Section #7 4.92 0.21 5.13 RB-4-28 1.44 RB -25'- Wall Section #8 4.92 0.21 5.13 RB-4-29 1.44 RB-25'- Columns 4.92 0.21 5.13 RB-4-30 1.44 RB -25'- Pump Room - Mezzanine 4.92 0.21 5.13 RB-4-31 1.44 RB -25'- Pump Room - South &West Walls 4.92 0.21 5.13 RB-4-32 1.44 RB -25'- Pump Room - North, Northeast, &East Walls 4.92 0.21 5.13 RB-4-33 1.44 RB -25'- Pump Room - Ceiling 4.92 0.21 5.13 RB-4-34 1.44 RB -25'- Ceiling Section #1 4.92 0.21 5.13 RB-4-35 1.44 RB -25'- Ceiling Section #2 4.92 0.21 5.13 RB-4-36 1.44 RB -25'- Ceiling Section #3 4.92 0.21 5.13 RB-4-37 1.44 RB -25'- Ceiling Section #4 4.92 0.21 5.13 RB-4-38 1.44 RB -25'- Ceiling Section #5 4.92 0.21 5.13 RB-4-39 1.44 RB -25'- Ceiling Section #6 4.92 0.21 5.13 RB-4-40 1.44 RB -25'- Ceiling Section #7 4.92 0.21 5.13 RB-4-41 1.44 RB -25'- Ceiling Section #8 4.92 0.21 5.13

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix C Rev.0, Page 12 of 12 PBRF FSSR Attachment 9, Appendix C, Table 1 Structural Survey Units with EP Contributing Highest Location Highest Structural Highest EP Highest Possible Embedded Pipe Present mrem/yr to Structural SU SU mrem/yr Value mremlyr Value Combined mrem/yr Value FSSR, Att. 12 RB-4-42 1.44 RB -25'- Cold Sump 4.92 0.21 5.13 RB-4-43 1.44 RB-25'- PPP Room Sump 4.92 0.21 5.13

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix D Rev.0, Page 1 of 7 Plum Brook Reactor Facility Final Status Survey Report Attachment 9 Embedded Piping Revision 0 Appendix D Primary Cooling Piping, EP 1.11 & EP 1.12

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix D Rev.0, Page 2 of 7 Table of Contents Physical Description of EP 1.11 & EP 1.12 ................................................................... 3 Description of Embedded Pipe Surveys for EP 1.11 & EP 1.12 ................................... 3 Summary of Remediation & Embedded Pipe Surveys for EP 1.11 & EP 1.12 ............. 5 PBRF FSSR Attachment 9, Appendix D, Table 1 ......................................................... 6 EP 1.11 & EP 1.12 Draw ing ........................................................................................... 7

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix D Rev.0, Page 3 of 7 1.0 Physical Description of EP 1.11 & EP 1.12 The Primary Coolant Lines are identified in the EP surveys as EP 1.11 and EP 1.12. These lines exist after decommissioning as two 24 inch lines which run from the Primary Pump House Room #4 floor down to the RB -25 ending at the bottom of the reactor vessel tank. The two lines are remnants of the former reactor coolant return line (EP 1.11, hot leg), and the reactor cooling supply line (EP 1.12, cold leg).

The reactor coolant return line (EP 1.11) is the 24" hot leg for the Primary Coolant system. The function of this piping was to convey heated water away from the reactor core. As it exists today EP 1.11 consists of 24" diameter piping that is approximately 146 feet in length.

The reactor coolant supply line (EP 1.12) is the 24" cold leg for the Primary Coolant system. The function of this piping was to convey cool water into the reactor core. As it exists today EP 1.12 consists of 24" diameter piping that is approximately 146 feet in length.

The current physical configuration of these piping runs consists of the 24" pipes in a conformal steel support box at the PPH Room 4 which is surrounded by a concrete sarcophagus of at least two feet in thickness for the entire length of the piping until the piping enters the concrete foundations of the Containment Vessel.

The piping is completely encased in the Containment Vessel foundation and lies under the grouted section of the reactor vessel tank. There is no access into the sarcophagus from any adjacent survey units, and the steel support box is inaccessible to personnel as it is also concrete filled between the exterior of the 24" piping and the interior of the steel support box. The 24" piping is filled with grout between the PPH Room 4 minus 3 foot elevation to their lower ends at the reactor vessel tank.

2.0 Description of Embedded Pipe Surveys for EP 1.11 & EP 1.12 The 24" pipes were surveyed with beta-gamma scintillating detectors mounted on an in-situ, variable geometry, pipe sled. This sled allows the detectors to traverse elbows and risers while assuring a consistent geometry for each survey measurement. 100% assay by scan survey of all accessible surfaces and static radiological measurements at specified increments are assessed to demonstrate compliance with the EP dose goals. This detector and sled combination was utilized because the largest Nal scintillators in the project inventory were not able to provide sufficient MDA's for the 24" piping survey. Larger scintillating crystal detectors were not available to the project to allow surveys to be accomplished within the constraints of time and schedule.

The sled with detectors utilized for these surveys are illustrated below in both 24"mock-up piping and primary coolant 24" piping.

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix D Rev.0, Page 4 of 7 The detectors were calibrated under the PBRF calibration procedures and the efficiency determinations were performed with NIST traceable, conformable sources using the mock-ups pictured above. The sources were mounted in the mock-up allowing the detector-sled combination to reproduce the in-situ geometry of the 24" primary cooling pipes. Surveys in EP 1.11 and EP 1.12 were performed using detectors optimized to measure beta energies >85 keV. This energy is similar to the beta energy for Co-60 (96 keV), assuring the nuclide of concern for DCGL is assessed during data acquisition When performing piping surveys, the sleds were moved through the piping using flexible conduit rodding, extendable cameras and measuring tapes to control progress through the piping. Scan measurements require a 90 second scan time to survey each section of accessible 24"piping at < 1inch/second and within V2 inch of the piping surface. The gross cpm measurement for each scan is the highest, instantaneous, cpm count rate observed during the 90 second scan. The derived activity from these scan measurements is the most conservative quantity for that section of assessed piping. This conservatism is replicated when determining compliance with the DCGL release criterion. At each static measurement location a one minute static measurement was acquired at four clock positions for each location (12, 3, 6 and 9 o'clock).

Surveys of EP 1.11 & 1.12 were performed on the accessible piping in each piping run (106 feet of EP 1.11 and 87 feet of EP 1.12). 100% of the accessible piping was scanned. The inaccessible piping includes elbows (5 in EP 1.11 and 8 in EP 1.12), weld bead transitions (EP 1.12) and the three feet of piping between the 0' elevation and the -3' elevation in the PPH Room 4. The surveys performed

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix D Rev.0, Page 5 of 7 are representative of the entire pipe lengths and comply with the requirements of Section 7.5 of the FSSP.

The elbows and their approaches are inaccessible to the pipe sled. The upper 3 feet in PPH Room 4 was released to the structural DCGL for both pipe runs and is not grouted. This ungrouted piping was subsequently removed as part of ongoing decommissioning efforts.

Sixteen static survey locations were selected by a random number generator for each piping run (EP 1.11 and EP 1.12). At each accessible location four static measurements were acquired for a total of 44 static measurements in EP 1.11 and 40 static measurement locations in EP 1.12.

3.0 Summary of Remediation & Embedded Pipe Surveys for EP 1.11 & EP 1.12 The 24" primary cooling pipes were remediated using hydrolasing techniques as described in Section 3.6 of this attachment. The hydrolasing apparatus for remediating the piping enabled a consistent application of remediation effort throughout the entire piping run. Several remediation and post-remediation survey evolutions were performed on both EP 1.11 and EP 1.12. There was little to no change in the radiological contamination levels between hydrolasing evolutions remediation was secured and a dose goal of 2 mrem/yr was selected for EP 1.11 and EP 1.12. This selection was based after a review of the safety concerns inherent in hydrolasing operations, the diminished results of additional

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix D Rev.0, Page 6 of 7 hydrolasing, and the residual contamination levels achieved for the structure survey units which coincide with EP 1.11 and EP 1.12.

These piping runs are assessed for compliance with the embedded pipe dose goals attributing all activity derived dose as a 100% Co-60 nuclide distribution. This is the most conservative DCGL for the facility. Background was not subtracted from the survey measurements and the Elevated Measurement Comparison (EMC) was not employed for these survey units. As allowed in the FSSP, Section 3.3, a dose goal of 2 mrem/yr is designated for EP 1.11 and EP 1.12, the coinciding structural survey units were corrected for this dose goal.

The dose contribution for EP 1.11 is 1.009 mrem/yr, the dose contribution for EP 1.12 is 1.366 mrem/yr for the coinciding structural survey units as detailed below in Table 1. A summary of results is included as Table 2.

Appendix D, Table 1 - Structural Survey Unit/Embedded Piping Dose Table Structural Survey Units EP Contributing Highest Highest EP Highest Possible with Embedded Pipe Highest mrem/yr to Location Structural SU mremlyr Combined Present Structural SU mreml/r Value Value mrem/yr Value FSSR, Att. 11 CV-3-4 EP 1.12 Bio-Shield Lower 0.94 1.37 2.31 CV-3-5 EP 1.12 Bio-Shield Upper 0.94 1.37 2.31 CV-3-33 EP 1.12 Quads B &D 0.05 1.37 1.42 CV-3-34 EP 1.12 Quads B &D 0.05 1.37 1.42 CV-3-35 EP 1.12 Quads B &D 0.05 1.37 1.42 CV-3-36 EP 1.12 Quads B &D 0.05 1.37 1.42 CV-3-37 EP 1.12 Quads B &D 0.05 1.37 1.42 CV-3-38 EP 1.12 Quads B &D 0.05 1.37 1.42 CV-3-39 EP 1.12 Quads B &D 0.05 1.37 1.42 CV-3-40 EP 1.12 Quads B &D 0.05 1.37 1.42 Appendix D, Table 2 - Embedded Piping Survey Results for EP 1.11 & EP 1.12 Pipe # DCGL (1) Maximum Mean Standard EP Activity Activity Deviation Average EP Dose EPID# Length of (dpm/100 2

(dpm/100 (dpm/100 (dpm/100 Activ Description (ft) N cm ) 2 cm ) 2 cm )

2 cmr) <DCGL EP 1.11 24" Hot Leg 146 44 4.816E+05 336,638 243,208 35,638 Yes 1.009 EP 1.12 24" Cold Leg 146 40 4.816+05 466,670 328,933 45,270 Yes 1.366 Table 2 Notes:

Note 1 - DCGL value is based on dose goal of 2 mrem/yr. This value was increased from the initial 1 mrem/yr dose goal to 2 mrem/yr after extensive remediation and authorization from the NASA Project Radiation Safety Officer.

Plum Brook Reactor Facility FSSR, Attachment 9 Appendix D Rev.0, Page 7 of 7 EP 1.11 & EP 1.12 Drawing