ML20206F424

Rev 2 to General Atomics Triga Reactor Facility Decommissioning Plan

ML20206F424
Person / Time
Site:	General Atomics
Issue date:	04/27/1999
From:	Bramblett G, Greenwood J, Nicolayeff V GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER
To:
Shared Package
ML20206F419	List: ML20206F414 ML20206F424
References
CON-9009 PC-000482, PC-000482-R02, PC-482, PC-482-R2, TAC-L05435, TAC-L5435, NUDOCS 9905060121
Download: ML20206F424 (172)

Text

{{#Wiki_filter:- -- PC-000482/2 4 GENERAL ATOMICS TRIGA* REACTOR FACILITY DECOMMISSIONING PLAN / APRIL 1999 p;sogog pg, & cansnas.aromacs P PDR 2 -__________a

hEENERALAT0nNCE mm e m_ PROJECT CONTROL ISSUE

SUMMARY

DOC. CODE PROJECT DOCUMENT NO. REV. RGN 9009 PC-000482 2 TITLE: General Atomics TRIGA* Reactor Facility Decommissioning Plan APPROVAL (S) REVISION CM APPROVAL / PREPARED RESOURCE / DESCRIPTION / DATE REV BY SUPPORT PROJECT W.O.NO. A i/ ISSUE 0 2 > 0 A. J. Welch V. Nicolayeff C bhtt Initial Issue ) W. O. 9009.303.055 APR 171997 g, K. E. Asmussen 4/e7/97 bN9 ' ISSIDI 2 > 1 a.oreenwood v.Nicolay'er c , 4 5/.pg.. ceneral Revisions to ~ .C.B mblet t address NRC comments JAN 2 91999 09009.303.05500 e/29 smusser Y ISSUED 2 > 2 a.oreenwood v.uicolayerf y/uI[ Revised pages 2-23, / G.C. ramb1d / 3-5, 3-11, A-pqt g ] APR 2 71999 F A-8 to addresdrNRC,. j Q',.. smussero comments 4/wff 09009.303.05500-CONTINUE ON GA FORM 2175-1 o See Lisi Of Effective Pages O GA PROPRIETARY INFORMATION THIS DOCUMENT IS THE PROPERTY OF GENERAL ATOMICS. ANY TRANSMITTAL OF THIS DOCUMENT OUTSIDE GA WILL BE IN CONFIDENCE. EXCEPT WITH THE WRITTEN CONSENT OF GA. (1) THIS DOCUMENT MAY NOT BE COPIED IN WHOLE OR IN PART AND WILL BE RETURNED UPON REQUEST OR WHEN NO LONGER NEEDED BY RECIPIENT AND (2) INFORMATION CONTAINED HEREIN MAY NOT BE COMMUNICATED TO OTHERS AND MAY BE USED BY RECIPIENT ONLY FOR THE PURPOSE FOR WHICH lT WAS TRANSMITTED, @ NO GA PROPRIETARY INFORMATION lPAGE jj OF )

PC-000482/2 ' LIST OF EFFECTIVE PAGES ' Page Number Page Count Revision . i through ix' 9 2 ' l-1 through 1-13 13 2 2-1 through 2-23 23 2 3-1 through 3-19 19 2 4-1 through 4-4 4 2 5-1 1-2 6-1 1-2 7-1 1 2 8-1 1 2 9-1 1 2 10-1 through 10-2 2 2 A-1 through A 68-2 B-1 through B-28 28 2 Total 171 i ~ i iii -)

PC-000482/2 TABLE OF CONTENTS PR OJ E CT CO NTR O L I S S U E S U M M A R Y............................................................. 11 LI ST O F E F F E CTI V E P A G E S.......................................................................... 111 TA B L E O F C O N T E N T S................................................................................... l v LI ST O F FI G U R E S......................................................................................... v i LISTOFTABLES..........................................................................................vi LI ST O F AC R O N Y M S/A B B R E VI ATIO N S.............................................................vil

1. S U M M A R Y O F P L A N................................................................................ 1 - 1 1.1 introduction....................................

...............................................................1-1 1.1.1 Overview.......... ...............................................................1-1 1.1.2 Decommissioning Pian Provisions.................................................................1 -1 1.2 Background................................................................................................................1-8 12.1 Reactor Decommissioning Overview.................................................................1 10

1. 2.2 E st i ma te d C o st..............................................................................

......1-11 1.2.3 Avallability of Funds............................................. .........1-11 1.2.4 Program Quality Assurance................ ........................111

2. D E C O M M I S S I O N I N G A CTIVITI E S............................................................... 2 - 1 2.1 Decommissioning Alte rnatives............................................................................ 2-1 2.2 Facility Radiological Status........................................................................................ 2 1 2.2.1 Facility Ope t ating Histo ry.......................................................................................... 2 - 1 2.2.2 Current Radiological Status of the Facility...................................................

...........2-3 2.3 Deco mmis sioning Tas ks............................................................................. ..................2-5 2.3.1 Activiti es a nd Tasks.............................................................................................. 2 - 5 2.32Schedute............................................................................................................2-13 2.4 Decommissioning Organization and Responsibilities........................... .........................2-14 2.4.1 Decommissioning Project Manager........................................................................ 2-14 2.4.2 TR F Physicist-in-C ha rge..................................................................................... 2-18 2.4.3 Manager, Health Physics.................................... ......................................218 2.4.4 Manager, Quality Assuranee.............. .........................218 2.5 Training Prog ram................................................................................................... 2 18 2.5.1 General Employee Radiological T:aining (GERT 4 Hour)......................... ..............219 2.5.2 Radiological Worker Training (RWT 16 Hour)............................................................ 2 19 2.5.3 Health Physics Technician Training............................................................................ 2 19 2.5.4 Equipment Operator Training........................................................................... 2 19 2.5.5 Safety / Accident Prevention Training......................................................................... 2-19 2.5.6 Hazard Communication Training............................................................................. 2 19 2.5.7 Contamination Control Training.................................................................... 2 19 2.5. 8 Re sp i rato r Tra in i n g............................................................................................... 2 -2 0 2.5.9 Confined Space Entry Training............................................................................. 2-20 2.5.10 Emerge ncy Response Training....................................................................... 2 2 0 2.5.1 1 Haza rdous Mate rials Training.................................................... .........................2-20 2.5.12 H AZWO PE R Trainin g Cou rse.................................................................................. 2-2 0 2.5.13 Hazardous Materials Packaging........................................................................ 2-20 2.5.14 Waste Acceptance Criteria.......................................................................... ....... 2-20 2.5.15 Dangerous Waste Regulations....................................................................... 2-20 2.5.16 Emergency Response Training................................................................................ 2 20 2.5.17 RCRA Facility Standards Overview Training................................................................ 2-21

2. 6 Contractor Assistance...................................................................................................

2.6.1 Cont ra ct o rs................................................................................................ 2.6.2 Tasks...........................................................................................................221 2.6.3 Pote ntial Contracters.......................................................................................... l iv A

PC-000482/2 1 l 2.6.4 S u bco nt ract o rs.................................................................................................... 2 21 2.7 Decontamination and Decommissioning Documents and Guides........................................ 2-22 1 2.8 Facility Release C riteria................................................................................................... 2-2 2 I

3. PROTECTION OF THE HEALTH AND SAFETY OF RADIATION WORKERS ANDTHEPUBLIC...................................................................................3-1 3.1 Ra diation Protectio n..................................................................

.......................31 3.1.1 Ensuring As Low As is Reasonably Achievable Radiation Exposures............................... 3-1 3.1.2 Health Physics P rog ram.................................................................................. 3-3 I 3.1.3 Radioactive Material Controls................................................................... 3-10 3.1.4 Dose Estimates.......... .....................3-11 3.2 Radioactive Waste Management................................. ....................................3-14 3.2.1 Fue l Re mova l. ....................................................................................... 3 1 4 3.2.2 Radioactive Waste Processing.................. ...............314 3.2.3 Radioactive Waste Disposal............... ................................................................3-14 3.2.4 General Industrial Safety Program.,............ ....................................................316 3.3 Radiological Accident Analyses............................................................................... 3-17

4. PRO POSE D FIN AL R ADI ATION SU RVEY PL AN............................................. 4 1 4.1 Description of Final Radiation Survey Plan................................................................... 4 1 4.1.1 Means for Ensuring that all Equipment. Systems, Structures, and Site are included in the Su rvey Plan......................................................................

.........4-1 4.1.2 Means for Ensuring that Sufficient Data is included to Achieve Statistical Goals............. 4-1 4.2 Backg rou nd S u rvey R es ults..................................................................................... 4 1 4.3 Final Release Criteria-Residual Radiation and Contamination Levels............... ................42 4.4 Measurements for Demonstrating Compliance with Release Criteria..................................... 4 2 4.4.1 Instrumentation-Type, Specifications, and Operating Conditions................................. 4-2 4.4.2 Measurement Methodology for Conduct of Surveys................................................ 4-3 4.4.3 Fixed Contamination Sutvey Protocol..................................................................... 4-3 4.4.4 Removable Contamination Survey Protocol............................................................ 4-4 4.5 Methods to be Employed for Reviewing, Analyzing, and Auditing Data..................................... 4-4 4.5.1 Laboratory / Radiological Measurements Quality Assurance........................................... 4-4 4.5.2 Supervisory and Management Review of Results......................................................... 4-4

5. TE C H N IC A L S P E C I FI C ATIO N S................................................................... 5 - 1

6. P H YS I C A L S E C U R ITY P L A N...................................................................... 6 - 1 7.-

E M E R G E N C Y P L A N................................................................................. 7 - 1 )

8. E N VI R O N M E NT A L R E P O R T...................................................................... 8 1

9. CH ANG ES TO TH E D ECOM MISSIONIN G PLAN.............................................. 9 - 1 10.

REFERENCES....................................................................................10-1 APPENDIX A-SUMM ARY OF CH ARACTERIZATION RESULTS............................ A-1 APPENDIX B-E N VI R O N M E NT A L R E P O R T...................................................... B - 1 i 1 e V w -

PC 000482/2 1 LIST OF FIGURES Figu re 1 Regional Location...................................................................................... 1 2 Figure 1 2-GA Site and Surrounding Uses.....................................................................1 -3 Figure 13-TRIGA Reactor Facility Site and Adjacent GA Structures..................................1-4 Figure 1-4-TRIGA Reactor Facility Areas Within Decommissioning Plan Scope.........................1 5 Figure 1-5-TRIGA Reactor Facility, Room Detail. Plan View........................................ 1-6 Figure 2 1-TRIG A Mark I Operating Chronology.................................................................. 2-2 Figure 2-2-TRIGA Mark F Operating Chronology.......................................................... 2-4 Figure 2-3-Reactor Decommissioning............................................................................. 2-9 Figure 2-4-TRIG A Mark I Reactor.................................................................. ...... 2 10 Figure 2-5-TR IGA Mark F Reactor......................................................................................2-11 Figure 2-6-Decommissioning Schedule.................................................. ..........2-15 { Figure 2 7-Decommissioning Organization................................................................. 2 17 ] LIST OF TABLES Table 1 1-Profile of TRIGA Reactors at General Atomics.......................................... ..1-7 Table 2-1-List of Expected Radionuclides......................................... ................................2-6 I Table 2-2-Components with Potential Surface Contamination-Group 1................................... 2-12 l Table 2-3-Components with Induced Radioactivity-Group 2............................. ...........212 Table 2-4-Reactor Tank Activated Components-Group 3.... ...........212 Table 2-5-Equipment Used in Decommissioning Operations--Group 4.................................. 2 12 Table 2-6-Acceptable Surface Contamination Levels...................................................... 2-23 Table 3-1-Specific Health Physics Equipment and instrumentation Uso and Capabilities................ 3-5 Table 3-2-Occupational Radiation Dose Estimates for TRIGA Reactors Decommissioning Tasks...... 3 12 i 4 I i 1 4 9 j i 1 i Vi a \\ M

PC 000482/2 LIST OF ACRONYACS/ ABBREVIATIONS ACPR Annular Core Pulsing Reactor ALARA As Low.As Reasonably Achievable - ALI. ' nnual Limit on Intake (see 10 CFR 20) - AMAD Activity Median Aerodynamic Diameter ANSI American National Standards Institute AP Activation Products - APPM ~ GA Accident Prevention Program Manual ARA- ~ Airborne Radioactivity Area (see 10 CFR 20) - ASME American Society of Mechanical Engineers j - ATPR _ Advanced TRIGA Prototype Reactor i CA< Conditional Authorization ~ CAL-DTSC State of Califomia Department of Toxic Substances Control CAL-DHS State of Califomia Department of Health Services CAL-EPA State of Califomia Environmental Protection Agency CAL-OSHA State of California Occupational Safety and Health Act CAL-RHB Radiological Health Branch of CAL-DHS CAM Continuous Air Monitor - CCR State of California Code of Regulations - CDE Committed Dose Equivalent (see 10 CFR 20) CE Conditional Exemption CFR Code of Federal Regulations - cm centimeter epm' counts per minute CPR Cardiopulmonary Resuscitation CTI Cryogeme Technology Inc. D&D Decontamination and Decommissioning DAC. Derived Air Concentration (see 10 CFR 20) DDE Deep Dose Eguivalent (see 10 CFR 20) ' DECON Decontamination - DNAA ' Delayed Neutron Activation Analysis dpm disintegrations per minute (measure of radioactivity) i EBOR Experimental Beryllium Oxide Reactor EDE-Eye Dose Equivalent (see 10 CFR 20) EH&S GA Environment, Health, and Safety Department - ENTOMB-Entombment ' EPA U.S. Environmental Protection Agency FFCRs Fuel-Follower Control Rod (s) FOR Fission Gas Release FLAIR Flashing Advanced Irradiation Reactor FLIP. Fuel Lifetime Improvement Program FP Fission Products g gram, a unit of mass GA__ ' General Atomics GCFR. Gas Cooled Fast-Breeder Reactor GERT' ' General Employee Radiological Training GISO GeneralIndustry Safety Orders GM Geiger-Mueller. j HCF Hot Cell Facility (GA Bldg. 23) HEPA High Efficiency Particulate Air (Filter) HEU High Enriched Uranium HP. GA Health Physics Department HPGe High Purity Germanium Detector vil L

PC-000482/2 HTGR High Temperature Gas-Cooled Reactor LLW ' Low-level Waste LSA Low Specific Activity (see 49 CFR) LSNC GA Licensing, Safety, and Nuclear Compliance Division MAP Mixed Activation Products MDCR Minimum Detectable Count Rate MFP Mixed Fission Products micro-R micro-Roentgen,10 Roentgen 4 MIWP-City of San Diego Metropolitan Industrial Waste Program MkF- - TRIGA Mark F Reactor Mkl

TRIGA Mark I Reactor MkIII TRIGA Mark III Reactor mR milli-Roentgen,10 Roentgen mrad milli-rad,10-3. rad mrem.

millirem,10~' rem - MSDS Material Safety Data Sheet MSHA U.S. Mine Safety and Health Administration mSv' milli-Sievert (unit of dose equivalence, see 10 CFR 20),10 Sievert NAA. Neutron Activation Analysis - NCRP-National Council on Radiation Protection and Measurements. NFPA National Fire Protection Association NIOSH. National Institute for Occupational Safety and Health NIST U.S. National Institute of Standards and Technology NPR. New Production Reactor NQA-NuclearQuality Assurance NTS Nevada Test Site ' NWPF GA Nuclear Waste Processing Facility OSHA Federal Occupational Safety and Health Acts -PB Peach Bottom (Nuclear Generating Station) pCi pico-curie, a unit of radioactivity (2.22 disintegrations per minute),10.i2 curie PCM Personnel Contamination Monitor POL . Possession Only License . PTS. Pneumatic Transfer System PVC Polyvinyl Chloride. QA .GA Quality Assurance Organization QAPD - Quality Assurance Program Document R Roentgen RA Restricted Area (see 10 CFR 20) rad l unit of absorbed radiation dose-RCRA Resource Conservation and Recovery Act rem Roentgen Equivalent Man (unit of dose equivalence, see 10 CFR 20) RESRAD USDOE Computer Code for Residual kadioactivity Calculations RM Radiation Monitor RO Reactor Operator RWP Radiological Work Permit - RWT-Radiological WorkerTraining ' SAFSTOR' Safe Storage - SD-DHS-HMMD County of San Diego Depanment of Health Services Hazardous Materials Management Division SDE-Shallow Dose Equivalent (see 10 CFR 20) SNF Spent Nuclear Fuel SNM . Special NuclearMaterial SS Stairies Steel Sv Sievert (unit of dose equivalence, see 10 CFR 20) viii

PC-000482/2 Sx(s) Sample (s) TEDE Tota. Effective Dose Equivalent (see 10 CFR 20) .TFFF . TRIGA Fuel Fabrication Facility (GA Bldg. 22) TKF TRIGA King Furnace TLD Thermoluminescent dosimeter TRDS TRIGA Reactor Decommissioning Scope (the part of Bldg. 21 and associated yard area covered in this Decommissioning Plan) .TRF TRIGA Reactor Facility (GA Bldg. 21) ~ TRIGA* Training, Research, Isotopes, General Atomics TTSL . TRIGA Thermal Stability Lab q TTSX TRIGAThermal Stability X-Ray Room I UC Uranium Dicarbide l USAEC U. S. Atomic Energy Commission USDOE U.S. Department of Energy USDOT U.S. Department of Transportation ] USEPA U.S. Environmental Protection Agency .I USNRC U. S. Nuclear Regulatory Commission -WA Work Authorization i l TRIGA is a Registered Trademark of General Atomics ix L-__--__-________.

g PC 000482/2 1.

SUMMARY

OF PLAN 1.1 - Introduction 1.1.1' Overview Although General Atomics (GA) continues to offer TRIGA* (Training, Research, Isotopes. General Atomics) reactors and related facilities, equipment, materials, and services. GA has ceased all TRIGA reactor operations at the GA main site located in San Diego, CA (USNRC . Licenses R-38 and R-67). Figure 1-1 shows the regional location of the General Atomics facility; Figuar 1-2 depicts the GA site and adjacent surrounding land uses; the TRIGA Reactor Facility (TRF) site and adjacent GA structures aie shown on Figure 1-3; the TRF areas to be decommissioned within the scope of this plan are depicted on Figure 1-4 and are defined as the TRIGA Reactor Decommissioning Scope (TRDS). Figure 1-5 presents a plan view of the rooms within the TRF. GA has decideu to shut down and decommission the - TRIGA Reactors due to reduced market demand for GA's reactor irradiation services. The ~ bjective of this Decommissioning Plan is to conduct decontamination (DECON) of the o TRDS and removal of radiologically-contaminated and/or radioactive materials, equipment, components, and soil, to obtain release to unrestricted use by the U.S. Nuclear Regulatory Commission (USNRC) and State of California of the TRDS mcluding part of the TRF and part of the associated adjacent Controlled Yard areas. The TRF has housed three TRIGA . reactors, which have been variously used since 1958 to provide controlled neutron and gamma irradiation for diverse research projects. The three reactors are referred to herein as the TRIGA Mark I. TRIGA Mark F, and TRIGA Mark III reactors. It should be noted that this Decommissioning Plan addresses only the TRIGA Mark I and TRIGA Mark F reactors; a profile of these two reactors is presented in Table 1-1. Inasmuch as USNRC Facility License R-100 was previously terminated, the decommissioning of the TRIGA Mark III Reactor, adjacent rooms, and yard areas will be implemented by GA in accordance with the GA Site Decommissioning Plan (Ref.10.14); these activities are not further addressed in this plan. This Decommissioning Plan has been prepared using the guidance and format of NUREG - %37 Rev. 0, Guidelinesfor Preparing and Reviewing Applications for the Licensing of Non- !'ower Reactors (Ref.10.1). 1.1.2 Decommissioning Plan Provisions This Decommissioning Plan provides the following: 1.1.2.1 : A description of the present radiological condition of the TRF and adjacent Controlled Yard areas. 1.1.2.2 A description of the planned approach to be employed to decommission the TRDS. . l.1.2.3 Descriptions of the' methods that will be utilized to ensure protection of the health and safety of the workers and to protect the environment and the public from radiological hazards associated with the sub.pect TRDS Decommissioning Project activities. 1,1.2.4 A description of TRDS physical security and material accountability controls that will be in place during the various phases of Decommissioning Project activities. 1.1.2.5 A description of the radioactive waste managernent and disposal.

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PC 000482/2 Table 1-1-Profile of TRIGA Reactors at General Atomics item Description l TRIGA Mk1 l TRIGA MkF ) GenetelReacter*

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P % nm< Classrhcabon: Research, WaterW Pool Type. Thermal, Pnvately-Owned Owner: General Atorrucs Locallort TRIGA Reactors Facility (Bldg. 21),3550 General Atomos Ct., San Diego, CA 92121 1194 Operator: Owner Owner uc x-: Owner Owner ArchitectEngineer Ralph M. Parsons Co. Ferver Dorland & A=w. Nue!aar Design: Owner Owner Research & Development: Owner Owner Core Manufacturer Owner Owner Construcbon Owner Owner Principal Uses: Training, NAA, DNAA, Transient Radiabon Studies Thermionic Power Development, n Radiography Reestor Operation and Authoriantion: %A ' < ' '< Mi M < ' W O 1 i Initial Cnticahty: 5G58 7/2MO Date Secured: 1&2997 322f95 USNRC Utilization Facility Lx:. #: R-38 R-67 USNRC Facility Docket #: 50-89 50 163 Remotor -- - . m: ' - e a >.- u w, 4 -A + MaximumPower, Steady State, MW(t): 025 15 Max.imumPower, Pulsing MW(t): 1000. 6400. 4 Steady State,(ny): 1.40E+13 3.30E+13 % Putsing, (nv): 5.40E+16 1.40E+17 ew Steady State. (ny): 4.50E+12 4.40E+13 ew Pulsing, (ny): 1.80E+16 1.90E+17 Specific Power (kW/kg "U): 80 420 Core Power Density, (kW/l): 3.5 20 Fuel Matenal: UZrH,, or UZrH,, UZrH,, Fuel Uranium Content, wt-% U: 8.5 8.5,30 Uranium Enrichment, % "U: 20% 20 % /0 % 93 % Fuel Element Geometry-Cylindrical rods, 1.42:(3.61 cm) dia. x 15" (38.1 cm) acbve length Element Cladding Matenal: 1100F Al or 304 SS l 304 SS Element Cladding Theckness: 1100F A1: 0.03"(0.076 cm); 304 SS: 0.02"(0.051 cm) Core Configuration: Circular array Hexagonal array Core Achve Height:: 15' (38.1 cm) 15' (38.1 cm) No.of Available Fuel,oosibons: 91 121 C&d. Ught water Ught water Moderator: Ught water, ZrH Ught water, ZrH Reflector Graphite Water NOTE-The profile above relates to the generalcharactenstics of the reactors dunng the respecbve penods or operation. In the course d operabons, both of the reactors were modified to a-m uGaie ublization of tie facihty by reactor users; such modifications were camed out by the implementation d appropnate changes b the corresponding Techncal Speerfcations, or by apphcation of the provisions of 10 CFR 50.59. 1-7

e PC0000482/2 I 1.1.2.6 A description of TRDS physical security and material accountability controls that will be ' in place during the various phases of Decommissioning Project activities. - 1.1.2.7. A description of the radioactive waste management and disposal. 1.1.2.8 A cost estimate for decommissioning the TRDS, and the source of funding for these i activities. i 1.1.2.9 A schedule for the subject TRDS Decommissioning Project. 1.1.2.10 A' description of the Quality Assurance Program applicable to the TRDS Decommissioning Project.- 1.1.2.11 A description of the Training Program to be established for personnel performing work in support of the TRDS Decommissioning Project. 1.1.2.12 An Environmental Report conceming the expected impact of performing the activities involved in the TRDS Decommissioning Project. '1.2

Background

' Site and Facility History General Atomics The property, on which is situated the General Atomics TRIGA Reactor Site and Facility, was acquired in 1956 from the City of San Diego, as part of a ~290 acre (~117 hectare) tract, by the General Dynamics Corporation, with the expressed purpose - of the establishment of the John J.- Hopkins Laboratory for Pure & Applied Science, later named General A*.omic Division of the General Dynamics Corporation. One of the first goals of the newly-established General Atomic Division of General Dynamics was the development of a new family of small nuclear reactors, which could be utilized in both industrial and academic applications for training, research, and isotope production. Between 1957 and 1966 three TRIGA reactors were constructed in the 'IRIGA Reactor Facility (IRF), although this Decommissioning Plan addresses the two reactors which are currently licensed (in Possession-Only-License, POL, status), i.e., the 'IRIGA Mark I and Mark F reactors. Figure 1-5 shows the cunent 'IRF configuration. The specific 'IRF rooms and yard areas to be addressed in the 'IRDS Decommissioning Project herein are listed below. 2 Mk1 Reactor and Control Room,- 21/102 (~860 ft area) 2 Vestibule,21/102 (~60 ft area) 2 Offices,21/103-21/104 (~280 ft area) 2 Tool Shop,21/105 (~230 ft area) 2 Counting Room,21/106 (~280 ft area) MkF Reactor Room,21/107 (~870 ft area) 2 2 MkF Control Room,21/108 (~280 ft area) 2 Mezzanine above 21/108 (~280 ft area) 2 ' Mezzanine above 21/109 (~280 ft area) Mkl Controlled Yard (~1100 ft area) 2 2 MkF Controlled Yard (~1440 ft area) Plus additional portions of the Cooling Tower Controlled Yard and other outdoor areas associated with the 'IRF Cooling Tower underground piping system. 1-8

PC 000482/2 Figure 1-4 shows the TRDS area, which is included in the scope of this Decommissioning Project. 'IRIGA Mark I Reactor As part of early nuclear reactor development efforts, General Atomics initiated plans to design, build, and operate a prototype reactor unit on the company's Torrey Pines Mesa site. To this end, in late 1957, GA requested and obtained a Construction Permit and Utilization Facility License from the U. S. Atomic Energy Commission (USAEC) to authorize this activity. Immediately thereafter, working with the Ralph M. Parsons Company as the Architect / Engineer, General Atomics proceeded with construction of the _ Isotope Reactor Building,later named the 'IRIGA Reactor Facility (Building 21), to house i the Prototype TRIGA Reactor and supporting systems (e.g., Instrumentation and Control Systems, Forced Cooling System, -Water Demineralization System, Ventilation / Exhaust System, Radiation Monitoring Systems, etc.). Following building construction and reactor hardware installation, the Prototype TRIGA Reactor was brought to initial criticality on May 3,1958. Continuously operational from that date until late 1997, the Prototype 'IRIGA Reactor was later designated as the Torrey Pines 'IRIGA Reactor, and later yet, as the TRIGA Mark I Reactor. At GA's request, the USNRC issued an amendment to the 1RIGA Mark I utilization facility license on October 29,1997, which placed the reactor in Possession-Only-License (POL) status. ' 1RIGA Mark F Reactor In March 1960, GA submitted an application to the USAEC requesting a Construction Permit and Utilization Facility License for the Flashing. Advanced Irradiation Reactor (FLAIR). These documents were issued to GA by the USAEC and thereafter, working with the Fervor-Dorland Engineering Co., Building 21 was modified by the addition of Rooms 21/107 and 21/108 to house the FLAIR Reactor and Reactor Instmrnentation & Control Systems, respectively. This reactor, which was brought to initial enticality on July 2,1960, was continuously maintained and operated by GA from that time until March 22, 1995, when the Utilization Facility License was amended, at the request of GA, to authodze Possession-Only-License (POL) activities. During the operating period, the reactor installation was designated as the. Advanced TRIGA Prototype Reactor (ATPR) and also later refened to as the TRIGA MkF Reactor. Current Facility Status The TRIGA Mkl Reactor, situated in TRF Room 21/102, was placed in " Possession-Only-License"(POL) status, under Amendment No. 35 to the USNRC License No. R-38, dated October 29,1997 (Ref.10-2), and is presently inoperable. All reactor fuel elements have been removed from the Mkl Reactor pool, and transferrad/ relocated to the MkF fuel storage canal in Room 21/107. Moreover, a number of additional components and hardware items, pieviously installed as part of the Mkl Reactor Control and Instrumentation systems, have been dismantled, surveyed, and mmoved from the TRF for ircycle use; this partial dismantlement and disassembly of the Mkl systems was performed by implementing instructions set forth in a plan, which was prepared, reviewed, and approved in accordance with th: administrative provisions of 10CFR50.59. The 1RIGA MkF. Reactor (situated in. Room 21/107) was previously placed in " Possession-Only-License" (POL) status under USNRC License No. R-67 (Ref.10-3), as amended on March 22,1995, and is also currently inoperable. All reactor fuel elements have been removed from the MkF reactor core / shroud and placed in the MkF Fuel Storage Canal. The non-fuel components of the MkF reactor, including the core support structure, 1-9

PC-000482/2 i - bridge shroud, beam tubes, and associated hardware, remain in the reactor pool. The Fuel. Storage Canal portion of the MkF reactor pool currently houses all of the Spent Nuclear Fuel (SNF) elements previously removed from the MkI, MkF and MkIII Reactors. All required protection barriers and security systems, including those necessary for High Enriched Uranium (HEU) (i.e., electrical service, domestic water supply) storage, are maintained in accordance with GA's NRC-approved physical protection plan. All1RF building utility services required for facility operation and maintenance under POL conditions are active. 1RF building air ventilation and HEPA-filtered building exhaust systems, air supply compressors, and license-required radiological monitoring instrumentation systems are in normal continuous operation. q All manually-actuated and automated fire alarm / suppression systems in the 1RF are operational. l All installed 1RF security and radiological alarm systems are active and normal. Independent water demineralization systems serving the TRIGA MkI and 1RIGA MkF Reactors remain fully operational. A common forced water cooling system serving both the TRIGA Mkl and MkF Reactors remains fully operational. 1.2.1 Reactor Decommissioning Overview Prior to implementing the decommissioning actions described herein, the TRF will have been cleared of all extraneous fixtures, equipment and materials, except for the spent TRIGA fuel. The spent 1RIGA fuel will be stored in the TRIGA MkF Reactor Fuel Storage Canal until approval for off-site shipment is obtained. Decommissioning of the Mkl and MkF will be separate activities but may be conducted concurrently. Activities presented below address both reactors. Summary of Activities 1.2.1.1 Reroute services to isolate the TRIGA MkF Reactor and Control Rooms. (21/107 and 21/108) to maintain fuel storage support. 1.2.1,2 Dismantle, decontaminate or package as LLW, the TRIGA MkI Reactor components, tank and pit structures. The criticality equipment pit will be similarly addressed. 1.2.1.3 Decontaminte any remaining contaminated areas within the TRDS except the TRIGA MkF Reactor and Control Rooms, (21/107 and 21/108). 1.2.1.4 Dismantle, decontaminate, or package as LLW, the TRIGA MkF Reactor components, tank and pool structures except where activitict would potentially interfere with safe fuel storage under normal or accident conditions. l.2.1.5 Obtain necessary approval, and ship the stored spent TRIGA fuel from the TRIGA MkF Reactor Fuel Storage Canal. l 1-10

PC-000482/2 1.2.1.6 Decontaminate any remaining contaminated areas in the TRIGA MkF Reactor and Control Rooms and service yard (21/107 and 21/108). 1.2.1.7 Dismantle, decontaminate or package as LLW, the TRIGA MkF Reactor components, tank and pit structures. 1.2.1.8 Remove any contaminated soils in adjacent or underlying locations. 1.2.1.9 Prepare, package, process, and ship all radioactive waste materials, as appropriate throughout the activities. 1.2.1.10 Perform and document the final radiological survey (s) and submit a request to the USNRC and State of California for performance of confirmatory surveys and subsequent release to unrestricted use. 1.2.2 Estimated Cost The cost estimate is consistent with the scope of work covering D&D of the Mkl and MkF Reactors. D&D of the TRDS will be accomplished without dismantlement of the building. This project cost estimate $5,584K. Cost breakdown is given below. LSNC 960 Mark I D&D 656 Mark F D&D 775 Other D&D Tasks 314 Outside Contracts 100 Waste Management 140 Waste Disposal & Shipping

• 92 QA 339 PrincipalInvestigator 339 Project Management 638 Independent Confirmatory Survey (if required) lQQ Subtotal 4,653 Contingency 20%

231 Total $5,584K

• The estimate for LLW disposal is based upon the waste being buried at the NTS.

1.2.3 Availability of Funds Estimates of the costs of decommissioning all of General Atomics' USNRC (and State of Califomia) licensed facilities and sites in San Diego were provided in GA's May 20,1996 submittal to USNRC (Ref.10.5) which included the TRIGA Reactor Facility. That submittal also described the method by which GA proposed to provide financial assurance for funding its total cost of the subject decommissioning. By letter dated July 9,1996 the USNRC acknowledged acceptance of GA's proposal (Ref.10.6). 1.2.4 Program Quclity Assurance 1.2.4.1 The GA Quality Assurance (QA) program is described in the GA Corporate Quality Assurance Manual. The GA Quality Assurance program meets the requirements of the following quality assurance regulations and standards: 1-11

PC0000482/2 ) Code of Federal Regulations Title 10, Part 71 (10 CFR 71), " Packaging and Transportation of Radioactive Material," Subpart H," Quality Assurance." { ASME-NQA-1-1989 (Ref.10.7), " Quality Assurance Program Requirements for Nuclear Facilities." 'e ANS Standard 15.8 (Ref.10.16), " Quality Assurance Program Requirements for Research Ren.ctors." The GA Corporate Quality Assurance program was reviewed and accepted by the USNRC Transportation and Storage Inspection Section, Spent Fuel Project Otlice, Nuclear Materials Safety and Safeguards, Approval No. 0030, Revision 6, dated July 9, 1996, expiration date June 30,2001 (Ref.10.8). The quality assurance program used for decommissioning of the TRDS is described in a I Quality Assurance Program Document (QAPD) prepared for the Decommissioning of the TRIGA Reactor Facility. The QAPD invokes the use of the GAQA Manual on this project and provides project-specific QA requirements, including Organization, and the QA measures applied to planning, dismantlement, radiological surveys, material shipments, and waste certification. Consistent with the QA Mcnual and USNRC Regulatory Guide 7.10, Appendix A (Ref. ' 10.9), the QA program is applied to the various project activities in a graded approach, i.e., the QAeffort extended on an activity is commensurate with its importance to safety and its impact on project goals. The relationship of the QA function to the Decommissioning organization and to facility management is shown in Figure 2-7. 1.2.4.2 Audits, Inspections, and Management Review Formal Quality Assurance audits will be performed annually in accordance with ASME-NQA-1, to' verify compliance with the TRDS Decommissioning quality assurance program and to verify its effectiveness. These audits will be performed in accordance with written checklists by personnel who do not have direct responsibility for performing the activities being audited. Audit reports will be distributed to responsible management, up to the Senior Vice President level. Follow-up action will be taken, where indicated. Project technical assessments and QA surveillances will be performed frequently to assess compliance with established procedures. These assessments will be coordinated by the project QA manager. The assessment team will consist of quality assurance and technical personnel. Assessments will be performed in accordance with a written plan. Assessment reports will be approved by the project QA manager and distributed to the project manager and other project personnel. Follow-up action will be taken, where . mdicated. Inspections will be performed on procured and fabricated items to verify compliance with controlling documents. Inspections will be conducted by qualified inspectors in accordance with inspection plans prepared by a quality engineer. Discrepancies will be documented in a Nonconformance Report, which will be dispositioned by a quality engineer, or a Material Review Board, as appropriate. 1-12 4

n.. PC-000482/2 Additional assessments or management reviews will be performed when deemed rppropriate by the Project Manager. Such assessments may include Readiness Reviews prior to start of a new task, or Management Assessments. 1 l I i 1-13 j

PC-000482/2 2. DECOMMISSIONING ACTIVITIES 2.1 Decommissioning Alternatives The objective of the TRDS Decommissioning Project is to obtain regulatory release of the ponions of the'IRF and adjacent contiguous controlled yard areas, identified on Figure l-4, to unrestricted use. On this basis safe storage (SAFSTOR) or entombment (ENTOMB) were considered inappropriate to GA's future plans. SAFSTOR poses essentially the same potential risks and environmental impacts as the proposed project, but potentially for a much greater period of time. This alternative would necessitate continued surveillance and maintenance of the TRDS over a substantial time period. During this period, the risk of environmental contamination would continue to exist. Moreover, development of the land around the GA site over the next few years may significantly increase the local employment population density and increase potential for public exposure. ENTOMB would necessitate continued surveillance and maintenance of the TRDS over a substantial time period. During this period, the risk of environmental contamination would continue to exist. Moreover, development of the land around the GA site over the next few years may significantly increase the local employment population density and increase potential for public exposure. DECON is the option chosen. To the extent possible, decontamination of facility equipment and structural com3onents will be conducted to minimize radioactive waste. Structural portions of the bui: ding and surrounding soils and materials, found to be radiologically contaminated and/or activated, shall be remediated, decontaminated, sectioned and removed or processed, as necessary. This would be followed by an extensive and comprehensive limtl radiation and contamination survey demonstrating that the TRDS meets the approved criteria for release to unrestricted use. The results of this final survey will be documented in a report which will be submitted to the USNRC and State along with a request that the site be released to unrestricted use and deleted from GA's licenses. 2.2 Facility Radiological Status 2.2.1 Facility Operating History 2.2.1.1 TRIGA Mark I Startup: May, 1958 Shutdown: October, 1997; USNRC Utilization Facility License. #R-38 presently limited to Possession Only-Licenu (POL) status (see Ref. 10.2). Max. Power: 250 kW(t) Steady State The Mark I TRIGA Reactor was originally constructed by GA to prove the inherent operational safety of (U,Zr)H 1RIGA fuel matrix. Figure 2-1 provides a listing of operations conducted in the dA TRIGA Mkl Reactor. Through October 1997, the integrated power generated during operation of the TRIGA Mkl Reactor is estimated to be 84 MW-days. 2-1 i

PC-000482/2 TRIGA Mark I: Startup: 5/58 Shutdown. 10/97 Max. Power: 250 kW(t) Steady State 5/58 Radiation Streaming thru Dry Tubes 6/58 Reactor Transient Expenments 7/58 Irramaton of UC in Graphite for FP Diffusion 8/58 Transient Reactivity Compensation 12/58 Subcritical Assemblies 4/59 trradiation of PDTe Thermoelectne Elements 4/59 Determinston of Temperature Coefficient 4/59 Transient trradiations by Diamond Ordnance Fuse Lab & Signal Corps 12/59 HTGR Fuel Compact Radiation Flash 2/60 Irra$ation of Thermoelectne Expenment 4/60 Irradiation of Cs Cell for Thermionic Direct Converson 5/00 initial Expenments with in Core TRIGA King Furnace (TKF) 3/61 Expenments with HiQh Hyr'nde SS Clad Fuel 3/61 Continued Cs Cell arradiation 0./61 trramation of Semiconductors 11/61 initial Stearate Run in TKF 2/62 Generation of Ar gas for HCF Stack Monitor Calibration 11/63 Pilot Irrasation of EBOR 2F1 Sxs 2/64 Epithermal Neutron Absorption 6/64 Continued TKF Stearate and FGR Stu@es 7/64 i Transport Expenment 10/64 in-Core irraeaten/ Firing of Explosive Actuators 1/65 Irradiation of Flasionable Matertals in Sealed Canisters 5/65 h-Core inadiation of 'LI 9/65 Modify TKF for PulsinD 3/66 Irradiation of Elemental Na 1/67 Irradiation of Aqueous Pu Solution 2/68 Fission Product Decay Rate Experiments 8/69 trradiation of Cartndge Primer in Pneumatic Rabbit 3a0 trradiation of Encapstt.ated "U. "U. '"Np and 8"Pu 3&O Use of Graphite Pouch for TKF trradiations 10/70 Irradiation of F 29 Capsule Rods in TKF 2/71 in-Core Oscillator Measurements 3/71 Use of Shielding Materials in TKF 5/71 Irradiacon of UZrH in TKF 6/71 Ambient Temperature TKF 1rradations 8/71 High-Capacity TKF runs Out-of Core 9/71 Simultaneous Operation of Multiple TKFs 10a1 installation of Auxillary Cadmium Shielded Pneumatic Transfer System 1/72 installation of New Linear Channel Cornponent 6/72 Installation of New Servo-Controller Linear Channel 6/72 Removal of Freon Cooling System Hardware 8/72 TKF trra$ation of High Bumup Frel Specimens 3/73 Wet Hehum TKF Purge Test Expenments 12/73 installation of B Shielding Pneumatic Transfer System Terminus 4/74 Automated TKF Control System Installation 4/74 Fuel Hydrolysis Experiments in TKF 2/75 Use of AmBe Starter Neutron Sources 5/75 trradiation of Highly-Raeoactive Specimens in TKF 4/76 Use of No Purge Gas for TKF insulation 11/76 Irradiaton of Highly-Radioactive Specimens in TKF 12/76 Irradiaton of PB Compacts in TKF 2/80 installaton of New Operating Consolo 6/80 installation of Uninterruptable Power System 7/80 Use of *B Shielded PTS at Higher Power Levels 4/82 High Pressure Expehments to Determine Diffusion Rates 7/84 Installation of Microprocessor-Based Control Systems Digital Control Console - Phase il 11/85 Pressure Vessel for Neutron Pulse irradiation Tests 3/86 Pulse-trradaten of "U-Doped Concrete 9/86 Digital Control Console installation Phase ill 4/87 Instaflation of PVC Piping m Cold-Leg of Cooling System 12/87 installation of Stepping Motors for Control Rod Drive 2/88 Digital Control Console installatton Phase IV 6/88 Square-Wave to 250 kW SS Operation Experiments 6/88 Phase V Digital Control & Instrumentaten System, 1/89 installaton of Ground Fault Detector Test Circuitry 5/89 Installation of New Scram Timer Circuit 6/89 Installation of New CAM 8/89 Irraeahon of NPR Lithium Ta'Oet Specimens 6/90 installaton of New Reactor Core Top Grid Plate 2/91 Extension of NPR Lithium Target irramatons 3/91 Multiple Pulsing P ram 3/91 Modificaton of NM1 Wide-Range Power Channel 5/91 installaton of NFC-1000 Flux Controller 8/91 installation of Loss of-Magnet Voltage Relay in Scram Loop 3/92 Installation of Large Olameter in Core irrasshon Dry Tubes 9/92 Mo@fication of Di0ltal Cornmunications Network 12/96 TRIGA Reactor Demonstrations and Operator Training Figure 2-1-TRIGA Mark 1 Operat!ag Chronology s 22

PC 000482/2 2.2.1.2 TRIGA Mark F Startup: July, 1960 Shutdown: March, 1995; USNRC Utilization Facility License. # R-67, presently limited to Possession-Only-License (POL) status (Ref.10.3) Max. Power: 1500 kW(t) Steady State The GA 'IRIGA Mark F Reactor was originally constrected by GA as a prototypical testing reactor, to act as a proof test reactor for the 'IRIGA Reactor supplied by GA to the Defense Atomic Support Agency, Bio-Medical Radiation Research Facility, National Naval Medical Center, Bethesda, MD, under Contract No. 27757, dated 4/4/60. In April, 1961, while continuing to operate extensively for the Bethesda testing campaign, GA began to utilize the Mark F Reactor on a multi-user basis for several other irradiation experiments, the most conspicuous of which were the In-Pile Thermionic and Thermoelectric Power Conversion Projects and related experiments. Another primary user of the reactor, beginning in June,1963, was the Department of Defense Special Weapons Testing Center, Los Alamos, NM, involving the in-pile survivability testing of high-explosive ordnance for the U.S. Army. Figure 2-2 provides a listing of the experiments performed using the TRIGA Mark F Reactor. Integrated power generated during operation of the TRIGA MkF Reactor is estimated to be 4,200 MW-days. 2.2.2 Current Radiological Status of the Facility 2.2.2.1 General Routine radiological surveys show that the radiation levels and contamination levels measured at the 'IRF have consistently been low. A radiological study conducted in Man-h 1997, and summarized in Appendix A, confirmed that only minor quantities of residual radioactivity or radioactive contamination are present. The information indicates that the radioactive portions of the facility are primarily confined to the reactor internals and biological shield. Estimates of the radioactive inventory can be determined by considering the constituent elements of the material in question and calculating the duration of exposure to the neutron flux and the energies of the incident neutrons. Direct measurements, however, are generally more reliable and will be used during actual removal and/or dismantlement of components. This information will further define the basis for specifying the necessary safety measures and procedures for the various dismantling, removal, decontamination, waste packaging, and storage operations so that exposure to personnel is maintained ALARA. 2-3

i l 1 PC-000482/2 TRIGA Mark F: l Startup: July,1980 l Shutdown: March,1996 { Max. Power: 1500 kW(t) Steady State j 6e0 Construcean Authoreed 720 Reactor Startup Expenmental Program i 960 BologmalTargets Authorized ) 441 Thermionic Direct Pcwor Conversion 561 Support of Harry Dunnond Laboratory, Forest Glen, MD 861 Theimoelectric Device Targets Authorized a 1061 Uranium-Zirconium Carbide Therrruonic Ernitter 1141 Core Loaded with SS Clad ZrHn Fuel Elements 1141 Support of AFHRI (Anned Forces Radiaton Research Institute), Bethesda, MD ) 1262 Support of Sandia Natonal Laboratory, Albuquerque, NM 1 2E Pulsed, Fueled Expennants Authortzed [ 463 Pulsing Program Conhnuing, to $4.00 8k/k insertion j 663 IrKkre irradiaton of Explosives, Harry Diamond Laboratory, ForsW Glan, MD l 7/83 Instanaconof 2"'TransentRod 863 Fuel Fission Product Release Studes 963 Irradiatonof Ultrapure Al 1123 Irradiabon of Xylenes for Radiaton Damage Studies 364 instanation of FFCRs and D-Ring Trans6ent Rod j 464 trradiation of AgZn/KOH Batisties 664 Irradiaton of Laser Rocs, Squibs, & Electrones 964 h; Device Targets Authorized 366 Irradlebon of 'LIF and Red Phosphorus, Sandia Nabonal Laboratory. A&xmergue, NM ( 1126 Experimental Pulsing Program Authorized j 266 Experimental Pulseng Program Authorized i 366 Fueled TKF Expertments Authorized 366 TKF HTGR Development Work AtAhorized 866 Pulsing Program Congnuing, to $4.60 860k insertion 747 ACPR Pulsing Configuration Authorized 727 in-Core TKF Authorized l 867 Rousne Use of TKF for SS & Pulsing irradiation l 868 Uranium Vaportzanon from Seawater Media 868 600 Cl yttradation Experiment i 1068 instaRaton of FLIP Elements i 120 Irradiation of"U Doped Concrete 1/89 ModHication of Target Thermionic Device Desagn 2f72 Explosive Targets Authonzed 373 Contnued TKF Testng 473 InstaBaton of Mark lil Fuel in Mark F Core 474 Reconfiguraton of Mark F to Smal Core High Power Density 1/15 InstaMahon of Mark lil Console to Mark F 475 Roubne Pulsing Program Development 575 Pulse irradiation Tesong of New TRIGA Fuel 1275 Contnued TKF Teseng 1076 Cold Neutron Radiography of Zr Program (CTI Nuclear) 11/76 Cryogene n Moderator Use Authortzed (CTI Nuclear) 2'77 Teseng of 1/2" dia. Fuel at Steady Smte 12/77 Contrued operations for CTI Nuclear and TKF 4/78 Conbnued Teseng of 1/2" dia. Fuel for Romarna TRIGA Reactor 678 Testing of Central Flux Trap in Pulsing Mode 1140 Smas Core Pulce Tesung 562 High Pressure TKF Teshng 1082 Isotope Producton of"Ar & Br 723 Fuel Performance E valuation and improvement Expenments 964 Reactor Modifcanons for Tremonic Device irradiaton 508 Misc. Modrficatons la Contriving Thermionic Device irradiatbn 1093 Congnued Thermione Device Irradiabon 395 Shutban Figure 2-2-TRIGA Mark F Operating Chronology 24

D PC-000482/2 3 ! 2.2.2.2 Principal Radioactive Components This section is based upon process knowledge and is consistent with information obtained as a result of actual decommissioning experience of a 'IRIGA Mark I Reactor at the University of Texas, Austin, Texas.. The most highly radioactive component is likely to be the stainless steel construction Rotary Specimen Rack in the Mark I Reactor which may be expected to have a dose rate of = 16 R/hr at I ft. Other components to be handled and processed during 1RF Decommissioning which . may range up to = 5 R/hr at the surface are:

• l Upper and Lower Grid Plates-from both TRIGA Mark I and Mark F Reactors; aluminum construction with integral stainless steel fasteners.

Core Suppon Structure of both 'IRIGA Mark I and Mark F Reactors; primarily 4 aluminum construction, with stainless steel components. Graphite Reflector Assembly installed radially around 1RIGA Mark I Reactor core. Miscellaneous fasteners, especially stainless steel bolts, nuts, helicoils, and possibly j other reactor-related hardware items. 2.2.2.3 Radionuclides I The radionuclides which are known to be present, or are possibly present in detectable levels within the TRDS are listed in Table 2-1, 2.3 Decommissioning Tasks 2.3.1 Artivities and Tasks. 2.3.1.1 Preparation of the TRF for Decommissioning 2.3.1.1.1 Characterization Surveys As part of Decommissioning Project planning actions, studies have been conducted to determine the type, materials which are, quantity, condition, and location of radioactive and/or hazardous or may be, present in the TRF and surrounding areas. A comprehensive radiological survey of the 'IRF was completed in March 1997 by the GA Health Physics organization. Data and results from these surveys are provided in this . document as Appendix A: " Summary of Characterization Results." 2.3.1.1.2 Transfer of Spent 1RIGA Fuel to TRIGA Mark F Fuel Storage Canal In order to comply with the requirements of the Possession-Only-License (POL) conditions for the 'IRIGAMark I and Mark F Reactors (as set forth in References 10.2 and 10.3, respectively), all irradiated 1RIGA Fuel in the TRDS has been removed from the two reactor cores, and has been physically transferred to the 1RIGA Mark F Fuel Storage Canal. 2-5 q ]

O 1 i p PC-000482/2 1 1 j - Table 2-1: List of Expected Radionuclides Pxsde - hen LNo Decay Notes F (yo Mode "C. 5730. V AP; from n-activation of graphite reflector structure (TRIGA Mkl only) ~"Mn 0.86 ' e,y' AP; short-lived specie; from n. activation of SS hardware l "Fe 2.73' e-AP; from n-activation of SS hardware-i 1 '"Co 5.27 V,y7 AP; from n-activation of SS hardware; expected to be predominant AP specie present : "Ni - 76000. e,y AP; from n-acWyation of SS hardware 3 Ni 100. f AP; from n-actvation of SS hardware "Sr.

29.1 f

FP; probable FP constituent; achvity expected to be proportional to that of *Cs

• • Nb 20000.

f,y AP; ' unhkely AP inventory constituent; possible from n-activation of - SS hardware,! Nb impurities are present . "Tc ~ 2130(. V,y. FP, and minor AP inventory constituent; possible from n-activation of ' l SS hardware, y Mo imputinos are present "Sb 2.76 f,y FP; relatively thort-lived specie

• Cs" 2.07 f,y FP; minor FP inventory conettuent "Cs 30.17 f,ye FP; expected to be predominant FP specie present -

I '"Ca . 0.78 f,y FP; short-lived specie

• Eu !

13.48 V, $*, e, y FP, and minor AP inventory consDtuent; possible from n-activation of concrete, if Eu impurines exist in biological shield structure l l Symbois/ Abbreviations: V = Beta = Posttron e = Electron Capture y = Gamma-Ray AP = Active $on Product .FP = Fission Product + ' Radionuclide Half-Life v>.Jues and Deca f Mode information used above are taken from Ref.10.15. The list of expected r&nuclides prsweded above is based on the assumption that operations of the TRIGA Mark I and Mark F Reactors have resulted in me neWon Mivation of reactor core components and otherintegral hardware or structural members which I are situated adpacent to, or hd% prodmity to, the reactor core during operations. Specific items which are considered to have ' been exposed to neutron actvation Irw tude materials composed of aluminum, steel, stainless-steel, graphite, cadmium, lead. . concrete and possibly otners. Based on earlier studies and experience gained in similar research reactor decv m Mi;ng projects, and reactor-specific calculations which considered measured values for neutron leakage fluence, integrated operating power histones, reactor core / pool structural configurations, and malarial w,ii,n.;in,6 of expcoed pool structures, neutron activaton of materials beyond the concrete liner / biological shield structure (i.e., into *mg soil volumes) is 3,t, expected for e6ther the

TRIGA Mark I nor Mark F Reactors 1

~ 2-6 J + l v.

g PC-000482/2 2.3.1. I.3 General Cleanup of TRF and Adjacent Controlled Yard Areas ~In preparation. for decommissioning ' activities,' non-reactor. related equipment and materials situated throughout the subject area has been collected, surveyed, packaged, and appropriately dispositioned in accordance with established procedures. Examples of items which have been processed and removed from the TRF during these efforts are the 'IRIGA King Furnaces irradiation facilities and associated power and control systems. 2.3.1.1,4 Partial Removal of the TRIGA Mark I Instrumentation and Control System In June,-1998, major portions of the TRIGA Mark I Reactor Instmmentation and Control (I&C) system were dismantled, surveyed, released, and shipped from the 1RF for subsequent off-site recycle use. All of the actions involving the removal of the L'IRIGAMarkII&C system were authorized and performed in accordance with specific I written instructions, which were reviewed and approved under the provisions of 10 CFR 50.59. Specific I&C components thus removed from service at that time included the Control System Console, the Data Acquisition and Control Cabinet, the NM-1000 l Wide-Range Digital Power Monitor, and the Control Rod Drives. Reactor < elated instrumentation systems required for the surveillance and maintenance of the TRIGA i Mark I under current POL conditions, were left in place or rerouted to the 'IRIGA Mark ' F Control Room. 2.3.1.2 Decontamination of the Facility This Decommissioning Plan involves the sequential dismantling of the two reactors, the reactor pits and liners, and any associated systems, in a safe manner and in accordance with ALARA principles, and finally the decontamination and survey of the entire TRDS. There are two distinct reactors addressed. First the TRIGA Mark I Reactor will be dismantled. Second, the Mark F will be dismantled in two steps. Included in the decommissioning step is removal of all equipment in Mark F not associated with fuel storage and.where removal would not affect or compromise safe' secure fuel storage. Following removal of the fuel from the Fuel Storage Canal, the remaining 1RIGA Mark F Reactor components (e.g. the pool) will be dismantled. Figure 2-3 depicts the decommissioning of the Mark I and the two decommissioning steps for the Mark F. Views of the two reactors being addressed herein are shown in Figure 2-4 and Figure 2-5. For each reactor, components above the pool will be removed, including reactor pool deck plates, bridge structure, cables and reactor conduits, and the rotary rack drive dismantled and decontaminated to the extent feasible. Reactor components with induced activity will be removed using grapples and placed in shielded containers for disposal as ? LLW. This will be followed by a survey and discharge of the reactor pool water. Water in the Mk F and Fuel Storage Canal will not be removed until after the fuel has been l r removed. The dismantling of the reactor tanks and pits will proceed after installation of a confinement barrier in the reactor room and a dedicated ventilation system to prevent the spread of airborne contaminants. The aluminum reactor tank will be sectioned in place, removed from the pit and the contaminated sections packaged for dis msal. Surface and coring samples of the concrete biological shield will be performec to determine the contaminated areas. The contaminated sections will be cut away and packaged. Because of the limited removal of material and availability of shoring if required, the structural integity _ of the! pit 'will not be compromised by necessary decontamination. The - remaining portions of the concrete biological shield will remain intact. Any required sampling and analysis of the surrounding soil will be done by coring and repaired after sampling. Shoring and covering of the pit will provide industrial-protection, until the 27 I J J l l a.

PC0000482/2 final confirmatory release surveys have been performed. The remaining tasks am: dismantlement of the confinement barrier, removal of any remaining surface contamination in the rooms, and final confirmatory release surveys. The packaged waste is to be shipped to the U.S. DOE Nevada Test Site (NTS). 2.3.1.3 Dismantling Sequence j Dismantling will occur sequentially to the detailed schedule shown in Section'2.3.2. Items removed from the two reactors will be grouped as follows: ) i Group 1 Equipment which does not have induced radioactivity but which may have surface contamination. Group 2 - Core components and other components which have induced radioactivity (excluding the mactor tank). Group 3 - Reactor tank liner, anchors and concrete in the proximity of the former location of the reactor core and which have been neutron activated. Group 4 Equipment tools and systems which have been contaminated during decommissioning operations. 1 4 Components and equipment in the four groups are identified in Table 2-2, Table 2-3, Table 2-4 and Table 2-5. The Rotary Specimen Rack in the TRIGA Mk1 Reactor pool is expected to have the highest induced radioactivity. This expectation is consistent with the University of Texas experience in a similar TRIGA Reactor decommissioning project. The Rotary Specimen Rack and other Group 2 items will be hoisted from the pool and lowered into a shielded container which will have been prepared to accept the items. Additional shielding will be provided for worker protection if necessary. After components, equipment and parts listed in Table 2-2 and Table 2-3 have been removed, a confinement barrier will be installed. The purpose of this barrier is to contain airborne contaminants generated during reactor pit demolition, and to prevent their spread in the Reactor Room and possibly in the surrounding areas. The confinement barrier will be erected which will surround the reactor pit. Associated with this enclosure will be an independent localized ventilation system which will ensure a negative pressure with respect to the Reactor Room while providing high efficiency filtration on the exhausted air, and a source of clean air supply within the enclosure. 2-8 i L

PC-000482/2 Phase 1 (TRIGA Mk. I Reactor) Phase 2 (TRICA Mk. F Reactor) ' *\\ ( \\ / \\ \\ \\ \\ -former EE*" \\ V' Hot Cell ^\\ (Bldg. 23 uAgg \\ \\ \\ \\ \\ n L w \\ \\ 11 \\ \\] \\ EM .L_J PI s o r- - \\ ) e{ s/ g = j a s u m,,,, E .n n Z:: ~, 2 J% g umues w j'mZ lp ,sug .,z - Q ':' 9 )%"'M ":4f4f5 o i D .t umi ammu '- "::1%% l ~_ \\ \\ r="""*t/" M %: 'S'$T i j "'Z: 'Z""' i I w v ~ ^ \\': "lS1%%c i-1f t [ Figure 2-3-Reactor Decommissioning 2-9

PC-000482/2 T 6' l's sT s s s s s s .s s sr s s n .( B C 5 N O ll CCD b ].$,s LJ u Q ~ a t a. hL X 'i a ou 4 /_ L L_ __I { c OJ - - 8 E l s ( PLAN !r 1 W S__ l h Mk1 a et m. 5 Reactor [Ill Y ~~ \\,,,,,j ,,.( r [~ /; I ? ^ } f b b S p l l j 17 m Coce &s 4 P -l i a p; _,,-,9 '..,.3..-l N Section C-C j Figure 2-4-TRIGA Msrk i Reactor 2-10

• ~

PC-000482/2 y ,s// /// f MkF Control Roon Peactor Roon Tf 6 l I//////////////A '/ / ////A I l i / o e } j )g 1 p: m, f E , 4, e m -- h I 5 I E k 2 Ri b N bi w r, n. <a a ~_ Section A-A v__ q A s x x x x .s x x x x x x x x x x 'x x x I N c s 8 d b o JLb r co a ~ a .x v s g zg s s e w C Q W O l 0 s \\ l (-) )' f \\ O C O ~ / /Q f E O R is g s 5 [ 9 I s s w s 15'" xT' 7s x x x x x x x x x x x xi 2 PLAN R s v s j Figure 2 5-TRIGA Mark F Reactor 2 11

y PC-000482/2 Table 2 2-Components with Potential-Surface Contamination-Group 1 Purification System purification loop and deionizer tank piping domineralizer Other Components cables and conduits pool deck plates rotary rack drive

• l reactor bridge structure pneumatic transfer system i

Table 2-3-Components with Induced Radioactivity-Group 2 Rotary specimen rack (Mkl only) Control rod guide tubes and detector tubes Top grid plate Bottom grid plate Reflector Core support Fasteners and connectors Pneumatic transfer system terminus Table 2-4-Reactor Tank Activated Components-Group 3 Reactor pit liner Concrete Anchors Reinforcement bars Table 2-5-Equipment Used in Decommissioning Operations-Group 4 General ventilation system Localized ventilation system Confined barrier Contaminated tools and equipment Contaminated clothing The Reactor Room will be maintained at a negative pressure with respect to the surrounding areas but less than the pressure diffemntial maintained between the confinement barrier and the Reactor Room. This will ensure that the air will travel from the non-contaminated area to the increasingly contaminated areas. The activated liner section will be separated, removed, and processed, and the activated thickness of the concrete biological shield will be removed. To minimize dust dispersal, a localized fine water mist may be sprayed over the area being demolished. The GA -i Nuclear Waste Processing Facility (NWPF) operates a Filtration Station for the treatment of liquid wastes. The treated water is discharged into the sanitary sewer if it meets the discharge limits for GA's Industrial Wastewater Discharge Permit. Waste water that cannot meet discharge limits is solidified for off-site disposal as low-level radioactive waste. Activated concrete will be removed a section at a time and shoring supports will be placed in the cavity formed as needed, before proceeding with the next section. At the completion of activated concrete removal, dose rate measurements will be made to determine if all necessary portions have been removed. Post-remediation surveys may 2 12 i c )

PC-000482/2 include concrete and soil coring sampling and analysis. As the demolition of activated material proceeds, the radioactive material will be packaged for shipment and disposal. There are two potential radiological safety concerns during performance of this task: 1) extemal exposure from the activated components of the tank,. and 2) inhalation of airborne material. To minimize the risk, work areas will be monitored frequently and . radiation levels will be monitored continuously, to' determine sudden changes in the radiological conditions.- Upon completion of dismantlement tasks in the reactor pit, the confinement barrier will be dismantled and the plastic sheets compacted and packaged. Surface contamination will be removed from contaminated portions of the ventilation. system and they will then be packaged for disposal. The reactor room will then be cleared and all surface contamination removed. 2.3.1.4 Surveys Following' decontamination and remediation activities of each reactor, a final radiation survey of each of the reactor rooms and other applicable locations covering the entire 1RDS will be performed and documented by GA Health Physics. 2.3.2 Schedule The project schedule is presented as Figure 2-6. The scheduled time from regulatory approval of the Decommissioning Plan to submittal for release of the site to unrestricted use - is 41 months. It should be noted that fuel stored in the MkF Reactor Fuel Storage Canal is scheduled for timely removal and shipment off site. If the DOE fails to approve shipment to accommodate the timely continuation of the decommissioning, a day-to-day schedule slippage of Phase 2 of the D&D will occur until such time as the fuel is shipped off the GA site.' 2.3.2.1 Schedule for Off-Site Shipment of GA Spent Nuclear Fuel (SNF) GA plans to handle the spent 'IRIGA fuel currently stored in the TRIGA MkF Fuel Storage Canal as a work activity under the existing USNRC Facility License No. R-67; (non'IRIGA related irradiated fuel materials stored at GA will be shipped under provisions of current USNRC and-State of California Radioactive Material Licenses issued to GA). The U.S. Department of Energy (USDOE) is committed to provide for off-site receipt and storage of GA SNF. However, GA has been notified of a program delay. Receipt of the GA SNF at the established receiving organization (INEEL) is not scheduled to occur before CY2003 under current plans. Risks associated with the off-site shipment, transport, and INEEL receipt of the GA SNF, are addressed in an Environmental Impact Statement (EIS), separately issued by the USDOE to cover the subject tasks. 2.3.2.2 Request for Termination of USNRC Facility License Although all work associated with the Mark I may be completed and Facility License No. 38 termination requested, final completion of the TRDS Decommissioning Project work, as described herein, cannot be accomplished until all of the SNF currenti/ stored in the TRDS has been physically removed from the subject area, (see discussion above, 2-13 L. i

PC-000482/2 I i i ) regarding planned SNF off-site shipment schedule). Upon final removal of spent 1RIGA fuel from the 'IRIGA Mark F Fuel Storage Canal, GA plans to proceed with all remaining tasks to decontaminate and decommission the TRDS in a timely manner. i Based on project schedule information documented here in Figure 2.6, GA estimates that a formal request for termination of Facility License No. R-67 will be submitted to the USNRC approximately six months after the final shipment of SNF has been dispatched from GA. 2.4 Decommissioning Organization and Responsibilities GA is committed to, and retains ultimate responsibility for full compliance with the existing USNRC and State licenses and the applicable regulatory requirements during decommissioning. Company principles, policies, and goals will be followed to ensure high standards of perfonnance in accomplishing the decommissioning tasks. The planned organization for the TRDS Decommissioning as shown in Figure 2-7 will be maintained, individuals performing the functions may vary over the Project duration.) Specialized contractors may be utilized, under the direction of the TRDS Decommissioning Project Manager, when necessary and appropriate. Kev Positions 2.4.1 Decommissioning Project Manager-The TRDS Decommissioning Project Manager has the overall responsibility for successful completion of the Project. The Decommissioning Project Manager functions include: Controlling and maintaining safety during decommissioning activities and protecting of the environment Determining project staff ~mg and organization Assuring performance to cost and schedule e Reporting of performance Approving decommissioning plans and procedures Approving subcontracts Approving budgets and schedules Ensuring, with the assistance of the GA Licensing, Safety, and Nuclear Compliance (LSNC) Organization, that the conduct of decommissioning activities complies with all t the applicable regulations and is in accordance with the GA licenses. The minimum qualifications for the Decommissioning Project Manager are: A four year degree in engineering or natural science Five years of project management experience in the nuclear industry including e decommissioning projects Familiarity with the GA TRIGA Reactor Facility Appropriate training in radiation protection, nuclear safety, hazardous communication, and industrial safety 1 2-14

PC-000482/2 l r i i! i, I l ! l l 6 5 I l r; if_ 4I I i fli. _.]l cf 1 gl 'E i j kqeI i tJiLJ r dj ft!,,, i l glLfL o J l lfl. E I 95 g f.l7 g o-E E3_. _w__. I b a 1 a r a I b l jl I l E E b f l 5 5 8 h! I j 4 ,j '1].'! I j I i ^ 1 I l } 1g 1 m a i 3 q 3 M 6 3 . 1, ] (( i 1 j ] 3 f i l j l 'I I l ll l Il l ] ] l l I i s i rllTi===r""'""~"'~"~'"P! l a Figure 2-6-Decommissioning Schedule (1 of 2) 2-15

E~ PC-000482/2 l l I p(! / 5 l , _~ p.1B * ? ( ' iiL-3* ~ l_ L Iqpsl

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M Figure 2-6-Decommissioning Schedule (2 of 2) 2-16

PC 000482/2 lIk l 8 l I: l l ________________._______t 1 1 .I .i 1-I .p($ g!t b ds i i l I i l 1 1 1 1 I I I I 1 I I 5 m 3 3 I .1 1 1. l l l I I I l-1 l

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l t i-1 l I l ( I I I l l,1l l3 _ _ _ l_ _ _ _ l l I jld 3 I I Figure 2 7-Decommissioning Organization 2 17 .-.1_

i l PC-000482/2 l I 2.4.2TRF Physicist-in-Charge-The functions of the TRDS Physicist-in-Charge include: I Maintaining the TRDS in a safe and proper. condition during the evolution of Decommissioning Project activities,in accordance with the requirements set forth in the applicable USNRC facility licenses Approval of plans and procedures Providing engineering support for the decommissioning activities l The minimum qualifications for this position are: A current senior reactor operator license for the GA TRIGA Reactors issued by the USNRC A four year degree in Engineering or Natural Science e Five years experience in a research reactor facility environment e Substantial knowledge of the TRDS and associated systems e 2.4.3 Manager, Health Physics-The Health Physics Manager is responsible for providing radiological safety support in the decommissioning of the TRDS. This function ensures that activities involving potential radiological exposure are conducted in compliance with the applicable licenses. Federal and State regulations, and GA procedures. The position includes responsibility for maintaining TRDS surveillance and monitoring program and the development of HP radiological protection procedures. The minimum qualifications for this position are: A four year degn=e in Health Physics or a related field Three years supervisory experience in Health Physics e Five years operational experience related to radiation safety 2.4.4 Manager, Quality Assurance-The Quality Assurance Manager is responsible for implementing and managing the Quality Assurance program for the TRDS Decommissioning Project,in accordance with the applicable requirements of ASME-NQA-1, Quality Assurance Program Requirements for Nuclear Facilities and 10 CFR 71, Subpart H, Quality Assurancefor Packaging and Transportation of Radioactive Material, and for certification of radioactive waste to ensure compliance with the applicable Waste Acceptance Criteria of the Radioactive Waste Disposal Facility. The minimum qualifications for this position are: 1 A four-year degree in engineering or natural science Five years experience in nuclear related Quality Assurance e Two years experience in the decommissioning of nuclear facilities and radioactive waste e processmg 2.5 -Training Program Training is conducted and controlled in accordance with applicable GA procedures, license commitments, and the Work Authorization for the 'IRDS Decommissioning Project, and focuses on safety, knowledge ~of applicable regulations, and technical requirements. The training program shall comply with the requirements established by the USNRC in 10 CFR 19.12 (as described in more detail in the GA Radiological Contingency Plan, Ref.10.17) and 10 CFR 71.105(d); by OSHAin 29 CFR 1910.120(e) and 29 CFR 1910.1200(h); by 2-18

= PC-000482/2 the U.S. Envimnmental Protection Agency in 40 CFR 265.16; by CAL-EPA in CCR 22-66265.16; and by the U.S. Department of Transportation in 49 CFR 172.704. ' 2.5.1 General Employee Radiological Training (GERT 4 Hour)-General employee j radiological training will be provided to all personnel who are required to enter radiological Restricted Areas (with the exception of visitors and infrequent support personnel), but are not authorized to perform hands-on radiological work. 2.5.2 Radiological Worker Training (RWT 16 Hour)-Radiological worker training will l be provided to personnel who require unesconed access to radiological Restricted Areas, and who are authorized to perform radiologicaljob functions. GERT and RWT are administered to employees, as applicable, with refresher training 'provided every year. 2.5.3 Health Physics Technician Training ' Health Physics Technicians must successfully complete Radiological Worker Training. In addition, Health Physics Technicians are trained to the procedures used for their work and must review and understand other HP procedures according to the Health Physics Technician Procedure Review Sign-off Forms. Health Physics Technicians will also review applicable procedure revisions in a timely manner. Health Physics Technicians will also be familiarized with the Site and Facility characterization results and the contents of this Plan. 2.5.4 Equipment Operator Training j All equipment operators will have proper training completed and documented prior to performing unsupervised work with the equipment. Reactor operators must be licensed by the NRC. 2.5.5 Safety / Accident Prevention Training GA has an Injury and Illness Prevention Program (IIPP) which is defined in the IIPP Manual, a.k.a. the Accident Prevention Program Manual (APPM). All employees are required to abide by the requirements set forth in this Manual. Additional specific 'IRDS Decommissioning Project requirements may be specified, as required in Project procedures. 2.5.6 Hazard Communication Training-A hazard communication training program has been developed for this Project in accordance with OSHA 1910.1200 and the GA IIPP. This program promotes awareness of chemical hazards that are present at this Facility, and provides means to communicate those hazards to employees. A designated person will maintain the hazardous material inventory and Material Safety Data Sheets (MSDS) for on-site hazardous materials, and provide all Project personnel with information advising them of the stential for hazardous constituents in the work place. A list of such materials is mainta,ned at thejob site, and copies of the appropriate MSDS are available to site workers upon request. The MSDS form provides more detailed information about the chemical than a label does. A hazardous chemical inventory is maintained 'which reflects the current supplies located in the work area. Any chemicals not previously located and identified or new chemicals received on the job site will be added to the inventory list. 2.5.7 Contamination Control Training-Personnel will be trained in contamination control together with boundary control, ventilation control, etc. Cross contamination will be limited 2 19

r PCo000482/2 by the use of training and radiological controls. Radiological and hazardous material contamination will be strictly controlled during all decommissioning work. This control will be accomplished using qualified workers to perform work identified in approved work procedures. In some instances, special briefings and dry-runs may be used to perfect techniques, demonstrate approaches, and qualify the workers. J 2.5.8 Respirator Training-Each individual who may use a respirator will be required to I receive respiratory protection training, be medically qualified to use respirator protection, and receive a quantitative fit test for each specific device that they are qualified to use. Training will meet the requirernents of the U.S. Department of Health, Education, and Welfare National Institute for Occupational Safety and Health (NIOSH), and ANSI Z88.2-1980, Practicesfor Respiratory Protection (Ref.10.11). Respirator fit tests will be administered before initial assignments tojobs requiring the use of a respirator, and will be conducted as necessary thereafter. Medical qualification will be assessed annually. l 2.5.9 Confined Space Entry Training-Employees required to enter confmed or enclosed spaces will be trained to the OSHA confmed space entry requirements. They will be instructed as to the nature of the hazards involved, the necessary precautions to be taken and the use of required emergency and protective equipment, as prescribed by the Health and Safety Manager or designated person. A confined space permit must be issued prior to access into the confined space. 2.5.10 Emergency Response Training-GA has a GA Site Radiological Contingency Plan, as required by the USNRC and the State of California. The TRDS has a specific procedure in support of these plans. 2.5.11 Hazardous Materials Training Training for hazardous materials is dependent on the job description for each individual and the types and amounts of hazardous materials or hazardous wastes being handled as specified in the position's training plan. In general, the training specified for workers and supervisors directly involved with decommissioning includes some or all of the following training requirements: 2.5.12HAZWOPER Training Course-OSHA 1910.120, 40 hour classroom and 24 hour on-the-job training specific to hazardous materials. An 8 hour annual refresher is provided. 2.5.13 Hazardous Materials Packaging-Reviews the requirements for handling and shipping hazardous materials and wastes as required by 49 CFR, the DOT regulations. A refresher update is required every three years. 2.5.14 Waste Acceptance Criteria-Training is provided to the requirements established for the disposal site. An annual training update is provided. 2.5.15 Dangerous Waste Regulations-Training to familiarize hazardous waste technicians and supervisors with appropriate hazardous waste requirements for waste designations. A refresher is provided annually or as regulations are updated. 2.5.16GA Emergency Response Training-Training.to familiarize emergency response personnel with actions to be taken in responding to an unplanned release of hazardous or radioxtive material from the TRDS. Hands-on training in this area includes conducting drills to evaluate response capabilities. 2-20 L

PC-000482/2 2.5.17 RCRA Facility Standards Overview Training-This class covers the requirements established under 40 CFR 264.16 for personnel who may handle hazardous wastes within the Facility. The class covers the Federal Standards and discusses 3 compliance requirements for generators of hazardous and mixed wastes. An annual update is provided. t . 2. 6 Contractor Assistance 2.6.1 Contractors j f Contractors will have undergone the GA Quality Assurance approval process when j required. Wherever contracting personnel are used on-site, they will: 1) comply with all provisions of GA license:, and permits, and 2) be trained in accordance with GA's j commitments. Contractors will be used on an as needed basis during decommissioning. The use of contractors will be complementary to the GA staff and will normally provide specialty support. 2.6.2 Tasks Tasks where contractors may be used include but are not limited to: Shipment and disposal of radioactive and nonradioactive waste materials Laboratory testing and analysis e Concrete cutting e Construction / dismantlement support Asbestos removal and disposal Design and fabrication of specialty dismantling tooling and equipment e Specialty engineering and design services e Temporary staff augmentation 2.6.3 Potential Contractors Potential contractors for each identiDed task will be required to provide a statement of qualifications as part of their bid submittal. The qualineations required will emphasize the following: Experience with similar work in a radioactive environment Adequacy of qualined workers Ability to meet schedule The Quality Assurance organization at GA maintains an approved supplier list and has an extensive approval process which ensures that contractor qualincations an: adequate to the need. 2.6.4 Subcontractors Subcontractors who will work with licensed radioactive materials will be required to: Attend and complete applicable Radiological Worker Training Provide required exposure history information 2-21

7 PC-000482/2 Read and sign an applicable RWP and comply with instructions i Be issued proper dosimetry by cognizant HP personnel e Follow all special instructions given by HP e . Be escorted by a cognizant authorized person listed on the TRDS WA, unless e specifically listed themselves on the TRDS WA

2. 7.

Decontamination and Decommissioning Documents and Guides Health Physics, Industrial Health criteria. and other standards that guided the activities described in this Decommissioning Plan are discussed in Section 3.1.2, Health Physics Program, Section 3.2.3, Radioactive Waste Disposal and Section 3.2.4, General Industrial Safety Program. Relevant documents and guides used are noted therein and in Section 10, References. 2.8 Facility Release Criteria The proposed. decommissioning alternative that has been presented in this Decommissioning Plan does not necessitate the dismantlement of the 'IRF. The results of the site and facility radiological characterization have indicated that the structures may be directly releasable without need for extensive decontamination. This section provides the specific criteria for release of the 'IRDS. The Final Release approach will use the guidance provided in NUREG/CR-5849 (Ref. 10.10), and described in Section 4. Upon completion of the decontamination and remediation activities (e.g. see Section 2.3), a final radiation and radiological contamination survey of the 'IRDS will be performed and documented by GA Health Physics. The results of the survey (s) will be summarized in a report which will be submitted to NRC, as required by the U.S. Nuclear Regulatory Commission Regulatory Guide 1.86 (Ref.10.18), in support of a license termination request. Since the objective of decommissioning the TRDS is to ultimately release the facility / site to unrestricted use, a final radiation and radiological contamination survey report will demonstrate compliance with the radiological criteria given in Regulatory Guide 1.86. I Specifically, the criteria for release of the 'IRDS to unrestricted use and for termination of the corresponding licenses (which have been amended to allow possession only) are as follows:

1. Surface contamination levels must not exceed the values presented in Table 1,

" Acceptable Surface Contamination Levels," of the U.S. NRC Regulatory Guide 1.86," Termination of Operating License for Nuclear Reactors" (Ref.10.18). Table 2-6 presents the limits from the regulatory guide. Additionally, 2.~ Residual radionuclides - present as a result of facility operation - must not result m an exposure rate in excess of 5 micro R/hr above natural background measured at I meter from the surface (Ref.10.19). Removable surface contamination will be eliminated where possible by wiping or other proven decontamination methods. Release criteria for fixed and smearable residual radioactivity for beta-gamma emitters would be based upon the relative concentrations of ' isotopes on the material and their respective release criteria if more than one category of nuclide for beta-gamma emitters applies from Table 2-6. 2-22

PC 000482/2 Table 2-6-Acceptable Surface Contamination Levels

• j Nuclides*

(dpm/100 cm'f Average

• l Maximumd i

RemovabW U-nat,"U,3"U, & associated decay products 6,000 15,000 1,000 I Transuranics, a2sRa, 22*Ra, 8"Th, 22eTn, aPa, aa'Ac, '2*l, iavl 100 300 m Th nat, 82'Th,

• Sr.123Ra, a2*Ra, 82'U, *1, " i, "'I 1,000 3,000 200 Beta / gamma emitters (nuclK es with decay modes other than alpha 5,000 15,000 1,000 i

emission or soontaneous fission) except "Sr and others noted above. l Where surface contamnanon by both alphaand beta / gamma-emtting nucides exists, sie limits established for alpha-and beta / gamma-emtbng nudides should apply independently

• As used in 9as table dpm (disintegraMons per mnute) means tie rate of emission by radioactive material as determned by correchng the counts psr minute observed by an appropnate detector for background, efficiency, and geometric factors associated with the instrumentaticrt

' Measurements of averaga contamnant should not be a oraged over rnore than i square meter. For objects of less surface area, tie average should be derived for each such object. d The maximum contaminabon level applies to an area of not more than 100 cm', ) The amount of removable radioactve material per 100 cm'of surface area should be determned by wiping that area with dry filter ] (e.g., smear) or soft absorbent paper (e.g., masslin), applying rnoderate pressure, and assessing the amount of radioachve matenal s on the wipe with an appropriate instrument of known effciency. When removable contamnaton on objec,e of less surface area is determinod, then pertinent levels should be reduced proportonally and the entire surface should be wiped.

• lnduding contamination by induced radioactivity, i.e., acbvation.

9 2-23 1

PC 000482/2 3. PROTECTION OF THE HEALTH AND SAFETY OF RADIATION WORKERS AND THE PUBLIC - 3.1 Radiation Protection 3.1.1 Ensuring As Low As Reasonably Achievable (ALARA) Radiation Exposures Decommissioning activities at the GA TRIGA Reactor Facility involving the use and handling of radioactive materials will be conducted such that radiation exposure will be maintained As Low As Reasonably Achievable (ALARA), taking into account the current state of technology and economics ofimprovements in relation to the benefits. ALARA Progagn GA's current practice is as follows: A documented ALARA evaluation will be required for specific tasks if a Project HP determines that 5% of the applicable dose limits for the following may be exceeded: - Total Effective Dose Equivalent (TEDE) - The sum of the Dee > Dose Equivalent (DDE) and the Committed Dose Equivalent (CDE) to any indivic ual organ or tissue other than the lens of the eye Eye Dose Equivalent (EDE) - Shallow-Dose Equivalent (SDE) A documented ALARA evaluation will be required if Project HP determines that TRF e effluent averaged over one year is expected to exceed 20% of applicable concentration in 10 CFR 20, Appendix B, Table 2, Colunms 1 and 2. Decommissioning Project management positions responsible for radiation protection and maintaining exposures ALARA during deconunissioning include the Project Manager, and Project HP Manager. Methods for Occupational Exoosure Reduction Various methods will be utilized during Decommissioning Project work to ensure that occupational exposure to radioactive materials is kept ALARA. The methods include the Work Authorization (WA), the Radiological Work Permit (RWP), special equipment, techniques, and practices, as described in the following subsections. Work Authori7arion (WA) Approval Authorization for work to be performed in acconlance with reactor licenses and/or this Decommissioning Plan, must be obtained through the GA LSNC Division, by preparation and maintenance of a WA. The WA identifies the pro msed work scope and activities, quantity and form of radioactive materials involved, incividuals authorized to perform the work, and applicable work procedures. An estimate of the isotope (s), physical and chemical form, and quantity of radioactive material generated as waste during a twelve- . month period is included in the WA. An assessment of the magnitude and significance of estimated releases of radioactivity to the environment is also provided. Implementation of-operating procedures is contingent upon approval of the WA. Work is performed in strict accordance with the methods and precautions provided in the approved WA. 3-1

PC-000482/2 Radiological Work Permits (RWPs) - RWPs are used when: a work task is not described in the established Work Authorization, provided that the e margin of safety provided by the RWP is comparable to, or greater than, that specified in the WA, personnel not listed as Authorized Individuals on the Work Authorization must perform e

work, or outside contractors or subcontractor personnel must perform limited or routine work in the established Restricted Area (RA).

The RWP is issued in accordance with existing GA Health Physics procedural requirements, and is initiated by the Facility Principal Investigator or other responsible - individual who has good knowledge of the task to be performed and other work being performed in the area. Respiratory Pmtection and TEDE ALARA Evaluations. The use of engineering controls to mitigate the airborne radiological hazard at the source will be the first choice with respect to controlliag the concentrations of airborne radioactive material. There may be, however, circumstances where engineering controls' am not - practical, or may not be sufficient to prevent airborne concentrations in excess of those that constitute an airborne radioactivity area. In such circumstances where worker access is required, respiratory protective equipment will be utilized to limit intemal exposures. Any - situation whereby workers are allowed access to an airbome radioactivity area, or allowed - to perform work that has a high degree of likelihood to generate airborn: radioactivity in excess of 0.1 DAC, the decision to allow access will be accompanied by the performance .of representative measurements of airborne radioactivity to assess worker intake. The results of DAC-hour tracking and air sample results for any intake will be documented. Workers will provide nasal smears for HP evaluation following the use of respiratory protective equipment for radiological purposes as necessary. Control and Storage of Radioactive Materials - The GA HP Program establishes radioactive material controls that ensure: Deterrence ofinadvertent release oflicensed radioactive materials to unrestricted areas.

• . Confidence that personnel are not inadvertently exposed to licensed radioactive materials.

Minimization of the volume of radioactive wastes generated during the decommissioning. All materialleaving the Restricted Area will be surveyed to ensure that radioactive material is not inadvertently released from the TRDS. See Section 3.1.3 " Radioactive Material Controls" for a description of the specific survey methods that will be used. 3-2_ 1

PC 000482/2 3.1.2 Health Physics Program Project Health Physics Pronram-General GA Health Physics has procedures in place which will be implemented during the 3RDS Decommissioning Project. If new additional Health Physics procedures are required at some point in the work to support the decommissioning, they will be developed and approved in accordance with GA Health Physics policy and procedure. GA senior management is readily accessible to ensum timely resolution of difficulties that may be encountered. The HP Manager, while organizationally independent of the Project staff, has direct access to the Decommissioning Project Manager on a daily basis, and has full authority to act in all aspects of protection of workers and the public from the effects of radiation. Conduct of the TRDS Decommissioning Project HP program will be evaluated according to GA policy and procedure by both GA Quality Assurance oversight, and GA site HP audit activities. Audits. Insoections. and Manaoement Review i During Decommissioning Project work, aspects of the Project may be assessed by the GA Quality Assurance Department, through audits, assessments, and inspections of various j aspects of decommissioning performance, including HP as described in Section 1.2.4. Formal audits of the GA Health Physics program are conducted annually in accordance with GA HP procedure, and the requirements of 10 CFR 20. These audits will include aspects of the1RDS Decommissioning Project. Additional assessments or management reviews may be performed when deemed appropriate by the Decommissioning Project Manager and/or the PIC. q Health Physics Eauioment and Instrumentation GA has selected HP equipment and instrumentation suitabb to permit ready detection and quantification of radiological hazards to workers and the puolic, and to ensure the validity of measurements taken during n: mediation and final release surveys. The selection of . equipment and instrumentation to be utilized was based upon detailed knowledge of the radiological contaminants, concentrations, chemical forms, and chemical behaviors that are expected to exist as demonstrated during radiological characterization, and as known from process knowledge of the working history of the 3RF. Equipment and instrumentation selection also takes into account the working conditions, contamination levels, and source terms that are reasonably expected to be encountered during the performance of decommissioning work as presented in this Plan. The following sections present details of the equipment and instrumentation presently selected for use during the decommissioning. It is anticipated that through retirement of ' worn or damaged equipment / instrumentation or increases in quantities of available components or instruments, that new technology will permit upgrades or, at a minimum, like-for-like replacements. GA is committed to maintaining conformance to minimum . performance capabilities stated in this Plan whenever new components or instruments am selected. 33

PC-000482/2 l i F Criteria for Selecting Equipment and Instrumentation for Conduct of Radiation and Contamination Surveys and Personnel Monitoring Asufficient inventory and variety of instrumentation will be maintained on-site to facilitate effective measurement of radiological conditions and control of worker exposure consistent with ALARA, and to evaluate suitability of materials for release to unrestricted use. Instmmentation and equipment will be capable of measuring the range of dose rates and radioactivity concentrations expected to be encountered during conduct of remediation and decontamination of the TRDS, as well as for final survey measurements, and to less than the minimum values required for release or ALARA decision-making. Project HP staff will select instrumentation that is sensitive to the minimum detection limits for the panicular task being performed, but also with sufficient range to ensur: that the full spectrum of anticipated conditions for a task or survey can be met by the instrumentation in use. Consumable supplies will conform to manufacturer and/or regulatory recommendation to ensure that measurements meet desired sensitivity and are valid for the intended purpose. GA will continue review of regulatory information notices and bulletins for applicability to Project HP instrumentation.- Storage. Calibration. Testing. and Maintenance of Health Physics Equipment and Instmmentation Survey instmments will be stored in a common location under the control of 'IRDS Decommissioning Project HP personnel. A program to clearly identify and remove from service any inoperable or out-of-calibration instruments or equipment as described in HP procedures wil) be adhered to throughout the 'IRDS Decommissioning Project. Survey instruments, counting equipment, air samplers, air monitors, and personnel contamination monitors will be calibrated at license-required intervals, manufacturer-prescribed intervals (if shorter frequency) or prior to use-against standards that are NIST traceable in accordance with GA' Calibration Laboratory procedures, HP procedures, or vendor technical manuals. Survey instruments will be operationally tested daily when in use. Counting equipment operability will be verified daily when in use. The personnel contamination monitors are operationally tested on a daily basis when work is being performed. Soecific Health Physics Eauipment and Instrumentation Use and Capabilities Table 3-1 provides details of the HP equipment and instrumentation that has been selected for use in the 'IRDS Decommissioning Project. As discussed earlier, the selection of instrumentation is subject to change as older equipment and instruments am retired. GA will maintain conformance to minimum performance capabilities or better, whenever new components or instruments are selected. 3-4

PC-000482/2 l ) l Table 31-Specific Health Physics Equipment and Instrumentation Use and Capabilities Instrument Model j Detector Type i instrument Range or l Application l l l Detectior' Capability I Ebei1sne-RO-2 and 2A loruzr1 ion chamber RO 2 Beta / gamma exposure rate measurernents l Eberline RO-20 0-5,000 mRhr Minimum detecton: 0.2 mRhr l RO-2A 0-50 R/hr RO 20 0-50 Rhr Eberhro Teletector-6112D/B GM tube 01.000R/hr Teiescoping detector with GM probe for hegn range Ludlum-M239F Floor Monitor Gas proportional 0 500,000 cprr Alpha and beta / gamma floor rnonitor 434 cr79 with 3221 ratemeter/4337

• Cs efficiency approximately 30% 4n probe

"Pu efficiency approximately 17% 4m Ebertine-RM-14.14SA/HP-GM tube pancake RM 14 Beta / gamma surface contaminabon measurements 360 probe or HP100-BGS probe 0 50,000 cpm Can be used with several types of probes-informabcn for HP-260 probe.

probe RM-14SA "Sr efficioxy - 32% 4x 0 5,000.000 cpm 15.! cm2 HPico-aGS probe "Sr a ficiency 36% 4n,100 cm2 Ludlum Model 12 with 43-68 Gas Proporbonal 0-500.000 cptn Beta-Gamma surface conta mination eneasurements probe Canberra Low-Level Gas Proportonal Detecton capability Low-levelal smearsamples AlphsBeta Counbng System typically <25 dpm/100cm2 Ludlum 177 ZnS(Ag) 0 500.000 cpm Hand-held alpha frisker (50 cm area) 2 scintilabon Ludlum Model 19 pR Nal (TI) Scintillator 0-5.000 gRhr Low gamma exposure rates (i.e. 5 mR/hr) Minimum detecton: 1 pR/hr Ebertine SAC-4 ZnS(Ag) Scintillator 6 Decade scalar Alpha laboratory measurement of air samples and smears Ebertine BC-4 Shielded GM 6 9ecade scalar Beta laboratory measurement of air samples and smears ~ pancaketube REGE Canberra S 100 or HPGe Deteo on capability-Gamma laboratory measurement of water, air, smeartnedia samples quivalent Gamma ray 50.D pCI *Cs/g (e g., soit, asphalt, concrete, tar, vegetation) spectroscopy system Ebertine Personnel Gas Proportonal Detection capability-Personnel contam#naton monitor / walk-in monitor with microprocessor Contaminabon controland radon reject capabihty. <5.000 dpm/100cma Monitor PCM-2 SAIC RADeCO H809V N/A 130 cfm High Volume air sampling for minimum detecton capability "HiVol" SAIC RADeCO HD-29A N/A 0.5-3.5 cfm Low volume air samphng for lorig term air sampling " Goose Neck" Tedim;ixi Assoc. GM 10-10 cpm Local airborne monitor with alarm capabihty 5 FM-5ABN-2CH modular air monitors Ametek MG-4 Air Sampler N/A 5 - 4.000 cc/ min. Lapel air sampler for use in chronic exposure situabons Poliev. Method. Freauency. and Procedures The TRDS Decommissioning Project will utilize the existing GA HP Program for the Project. This Program prescribes policy, method, and frequency for effluent monitoring, l conduct of radiological surveys, personnel monitoring, contamination control methods, and protective clothing usage. Efiluent Monitoring-Until such time as the decommissioning effort has reached the point where the HEPA system is no longer needed, the TRDS ventilation system exhaust points will be continuously sampled downstream of each HEPA filtration system by an isokinetic sample collection point (a grab-type sample) which is in continuous operation. The particulate sample change-out frequency is approximately weekly; sample media are analyzed for paniculates using laboratory counting systems in a timely manner after filter 3-5

e. PCo000482/2 media change-out. The GA HP Department also operates several continuous environmental air sample stations on the main GA site to further assess the potential for environmental airbome radiological effluents. Any potentially contaminated liquids that may be generated or stored at the facility will be sampled and analyzed for radioactivity prior to disposal. If these liquids are found to

contain radioactivity, they will be evaluated for disposal options in accordance with applicable permits and State and Federal regulations.

Radiation Survevs-Radiation, airborne radioactivity, and contamination surveys during decommissioning will be conducted in accordance with approved HP procedure (s). The purposes of these surveys will be to (1) protect the health and safety of workers, (2) protect the health and safety of the general public, and (3) demonstrate compliance with applicable license, federal, and state requirements, as well as Decommissioning Plan commitments. HP personnel will verify the validity of posted radiological warning signs during the conduct of these surveys. Surveys will be conducted in accordance with procedures utilizing survey instrumentation and equipment suitable for the nature and range of hazards anticipated. Equipment and instrumentatior. will be calibrated and, where applicable, operationally tested prior to use in accordance with procedural requirements. Routine surveys are conducted at a specified frequency to ensure that contamination and radiation levels in unrestricted areas do not exceed license, federal, state, or site limits. HP staff will also perform surveys during decommissioning whenever work activities create a potential to impact radiological conditions. Personnel Monitoring-Internal and External-Extemal monitoring will be conducted in accordance with the prospective external exposure evaluation for the 'IRDS. Prospective extemal exposure evaluations will be performed, at a minimum, on an annual basis, or whenever changes in worker exposures warrant. Visitors to the 'IRDS will be monitored in accordance with requirements specified in GA HP procedures, and according to the radiological hazards of areas to be entered. Internal monitoring will be conducted in accordance with the prospective intemal exposure evaluation for the 1RDS. This prospective internal exposure evaluation will be evaluated on an. annual basis, at a minimum, or whenever significant changes in planned work evolutions warrant it. A comprehensive air sampling program is conducted at the TRDS to evaluate worker exposures regardless of whether internal monitoring is specified. The results of this air sampling program will be utilized to ensure validity of specified intemal monitoring requirements for1RDS personnel. If at any time during the decommissioning, hazards that may not be readily detected by the preceding measures are encountered, special measures or bioassay, as appropriate, will be instituted to ensure the adequate surveillance of worker internal exposure. Monitoring will be required if the prospective dose evaluation shows that an individual (s) dose is likely to exceed 10% of the applicable limits and for individuals entering a high or

very high radiation area.

Resoiratorv Protection-The GA respiratory protection program provides direction for use - of National. Institute for Occupational Safety and Health /Mine Safety and Health Administration (NIOSH/MSHA) certified equipment. This program is administered by GA HP in consultation with GA Industrial Hygiene. NIOSH/MSHA approved equipment are air purifying respirators which includes full face )iece assemblies with air purifying elements to provide respiratory protection against iazardous vapors, gases, and/or particulate matter to individuals in airborne radioactive 3-6 L

PC-000482/2 I l materials areas. Individuals may be rec uired to use continuous or constant flow full-face airline respirators for work in areas witi actual or potential airborne radioactivity. The HP Manager will also ensure that the respiratory protection program meets the requirements of 10 CFR Part 20, subpart H. Maintenance-When respiratory protection equipment requires cleaning, the car: ridges will be removed. The respirator will be cleaned and sanitized after every use with a cleaner / sanitizer and then rinsed thoroughly in plain warm water in accordance with HP procedures. Storage-Respiratory protective equipment will be kept in proper working order. When any respirator shows evidence of excessive wear or has failed inspection, it will be repaired or replaced. Respiratory protective equipment that is not in use will be stored in a clean dry location. Contamination Control-Contamination control measures that will be employed include, as appropriate, the following: Worker training will incorporate methods and techniques for the control of radioactive materials, and proper use and donning / doffing of protective clothing Procedures incorporate HP controls to minimize spread of contamination during work Radiological surveys will be scheduled and conducted by HP e ~ Containment devices such as designed barriers, containers and plastic bags will be used e to prevent the spread of radioactive material Physical decontamination of TRDS areas or items e Physical barriers such as Herculite sheeting, strippable paint, and tacky mat step-off e pads to limit contamination spread Posting, physical area boundaries and barricades e Clean step off pads at the entrance point to contaminated arets Personnel entries into radiological contaminated areas will require the use of protective clothing. This clothing will consist of a suitable combination of items such as the following, dependent upon the conditions outlined in the WAor RWP: '. Heavyweight lab coat Heavyweight canvas, cotton, or cotton / polyester coveralls e Heavyweight hoods e Plastic calf-high bootics e Rubber, plastic or cloth shoe covers e Plastic or rubber gloves which may require cloth liners. e Tyvek paper coveralls or plastic rain suit disposable outer clothing Face shield or other protective device e Access Control-A Restricted Area (RA) will be established and properly posted so.as to prevent unauthorized access. Engineered Controls-Personnel exposure to airborne radioactive materials will be minimized by utilizing engineering controls such as the following: 3-7

y -= PCo000482/2 Ventilation devices-in-place or portable HEPA filters or TRDS ventilation systems, e local exhaust by use of vacuums ' Containment devices-designed containment barriers, containers, plastic bags, tents, and glove-bags Source term reduction-application of fixatives prior to handling, misting of surfaces to minimize dust and resuspension Airborne Radioamyity Monitoring--Monitoring for the intake of radioactive material is required by 10 CFR 20.1502(b) if the intake is likely to exceed 0.1 ALI (annual limit on intake) during the year for an adult worker or the committed effective dose equivalent is likely to exceed 0.10 rem (1.0 mSv) for the occupationally exposed minor or declared pregnant woman. Air sampling will be performed in areas where airbome radioactivity is present or likely. Prospective estimates of worker intakes and air concentrations used to establish monitoring requirements will be based on consideration of the following: The quantity of material (s) handled The ALI for the material (s) being handled e The release fraction for the radioactive material (s) based upon its physical form and use e The type of confinement being used for the material (s) being handled Other factors that may be applicable HP personnel will use technical judgment in determining the situations that necessitate air sampling regardless of generalized, prospective evaluations done for the TRDS. Prior to identifying the location for an air sampler, the purpose of the radiological air I sample will be identified. Various reasons exist for collectmg air samples. The following are a few examples:

• Estimation of worker intakes Verification of confinement of radioactive materials e

Early waming of abnormal airbome concentrations of radioactive materials e Determining the existence of criteria for posting an Airborne Radioactivity Area (ARA). e Smoke tubes and buoyant markers may then be used to determine air flow pattems in the area. Air flow patterns may be reevaluated if there are changes at the TRDS that may impact the validity of the sampling locations. Such factors might include the following: . Changes in the work process ) Changes in the ventilation system e Use of portable ventilation that might alter earlier assessments e

After identifying the purpose for the air sample and flow patterns are established, air sample locations are established as follows

. For verification of confinement of radioactive materials: - Locate samplers in the air flow near the potential or actual release point. Mom than one sampling point may be appropriate when there am more than one potential or actual release points. 3-8 L

PC0000482/2 For estimation of a worker intake: e Sampler intakes will be located as close to the workers breathing zones as practical without interfering with the work or worker General workplace air sampler intakes will not be placed in or near ventilation exhaust ducts unless their purpose is to detect system leakage during normal operation, and if quantitative measumments of workplace concentrations are not required. Locations or number of air samplers will be changed when dictated by modifications to Facility structure, changes in work processes, or elimination of potential sources. A sufficient inventory and variety of operable and calibrated portable and semi-portable air sampling equipment will be maintained to allow for effective collection, evaluation, and control of airborne radioactive material and to provide backup capability for inoperable equipment. Air sampling equipment will be calibrated at prescribed intervals or prior to use agamst certified equipment having known valid relationships to nationally recognized standards. Table 3-1 lists anticipated air sampling equipment. When the work being performed is a continuous process, a continuous sample with a weekly exchange frequency is appropriate. For situations where short-lived radionuclides are important considerations, the exchange frequency will be adjusted accordingly. Longer sample exchange frequencies may be approved by HP management for situations where airborne radioactive material and nuisance dust am expected to be relatively low. Grab sampling forcontinuous processes may also be approved by HP management based upon consideration of variability of the expected source term for the facility and process. Grab sampling is the appropriate means of airborne sampling for processes conducted intermittently, and for short duration radiological work that involves a potential for airborne

release, Potential Sources of Radiation or Contamination Exoosure to Workers and Public as a Result of Decommissionine Activities Sources of radiation or contamination exposure may be assessed by process knowledge, radiological survey data, surveys performed during characterization, job coverage surveys, or daily, weekly and monthly routine surveys. previous and current Classification of potential sources may also be identified by, radionuclide, physical properties, volatility, and radioactivity.

Worker exposure to significant extemal deep-dose radiation fields is considered unlikely during this project due to the nature of the contaminants and/or the work precautions and techniques employed. Worker exposure to airborne radioactivity may occur during decontamination operations / work evolutions which may involve abrasives or methods that volatilize loose and/or fixed contamination. Exposure of the public to extemal or internal radiation from this Decommissioning Project is not ' considered credible because of the containment provided by the Facility and the access control provided for the Facility and the area surrounding it. The type (s) of exposure controls used takes into account the curmnt state of technology and the economics of improvements in relation to the benefits. Control of potential sources of radiation exposure to workers and public as a result of decommissioning activities will be achieved through, but not Ihnited to, the use of administrative, engineering, and physical controls. i. I 3-9 __...______2

) PCo000482/2 Administrative controls consist of but am not limited to: Administrative dose limits that are lower than regulatory limits Training e Radio;o3 cal surveys i e . Physical barriers. such as radiological warning rope / ribbon, in combination with radiological warning tape, lockable doors / gates as well as information signs and flashing lights or other applicable barriers may also be used. Engineering controls may consist of but are net limited to:

• HEPA ventilation / enclosures Protective clothing / equipment e

e Access restrictions / barriers . - Confinement Health Physics Policies for Subcontractor Personnel ' Subcontractor personnel may be used for cenain required work during the TRDS Decommissioning Project. Subcontractors who will work with licensed mdioactive materials will be required to: Attend and complete appropriate radiation safety course Provide required exposure history information Read and sign an applicable RWP and comply with instructions Follow all special instructions given by HP e Be escorted by a coguizant ruthorized person listed on the WA, unless specifically e designated as an Authorized ladividual in the current TRDS WA. 3.1.3 Radioactive Material Controls GA's radiation protection program establishes radioactive material controls that ensure the following: Prevention ofinadvertent radioactive material (licensed material) release to ancontrolled areas. Assurance that personnel are not exposed inadvenently to radiation from licensed radioactive materials.

• Minimization of the amount of radioactive waste material generated during decommissioning.

All materials leaving the 'IRDS Restricted Area will be radiologically surveyed to ensure that radioactive materials (i.e., licensed - materials) are not inadvertently removed. . Decommissioning Project and GA Health Physics procedures will be used to ensure that all potentially radioactive or contaminated items removed from the 'IRDS site are surveyed. The performance of these surveys will incorporate the guidance presented in U.S. NRC Circular No. 81-07, " Control of Radioactively Contaminated Material," and U.S. NRC Information Notice No. 85-92, " Surveys of Wastes Before Disposal From Nuclear Reactor Facilities,"(References 10-20 and 10-21). The following survey methods will be used: 3-10 L

m PC0000482/2 Materialc and Eouipment - Duect frisking with a portable Geiger-Mueller detector e (e.g., Ludlum Model 44-9 or Eberline Model HP-210, or equivalent) having a minimum level of detection above background of less than or equal to 5,000 i - dpm/100 cm'. Smear Samples - Aradysis wi:h a Geiger-Mueller detector (e.g., Ludlum Model 44-9 . or Eberline Model HP-210, or ec uivalent) having a minimum level of detection above background ofless than or equa to 1,000 dpm/100 cm, 2 e' -lhilk MMcnals (e.g., sand and soil)- Analysis of representative sample (s) with a high resolution gamma spectroscopy system having lower limits of detection, above sy' stem background, calibrated to a value of len than or equal to 0.18 pCi/ gram for ' Cs~ (i.e., s180 pCi/kg). Materials will be released if no discemable facility-related activity is detected within the capability of the survey methods presemed above. In evaluation of equipment and materials for flxed or smearable licensed radioactive materials, items painted with other than original manufacturer's paint will not be released unless clear process knowledge demonstrates that the paint was applied to a clean, non-radioactive surface prior to use in the TRDS Restricted Area or approval from Decommissioning Project Health Physics, has been obtained and an acceptable survey course for this situation has been approved. If the potential exists for contamination on inaccessible surfaces, the eouipment will be assumed to be internally contaminated unless (1) the equipment is dismantled allowing access for surveys (2) appropriate tool or pipe monitors with acceptable detection capabilities are utilized that would provide sufficient confidence that no licensed materials were present, or (3) it may readily be concluded that surveys from accessible areas are repn sentative of the inaccessible surfaces (i.e., surveying the intemal surface from both ends of a straight pipe from a nonradioactive process system with cotton swabs would be representative of the inaccessible areas). Radioactive material (licensed inaterial) may be transferred from the TRDS Restricted Area to other locations on, or off, GA's site having appropriate radimetive material licenses issued by the NRC or an Agreement State, or otherwise authorized to possess such radioactive material (e.g., U.S. DOE sites). 3.1.4 Dose Estimates The total projected occupational exposure to complete the Decommissioning of the CA 1RDS is estimated to be 20 person <em. A task-by-task breakdown of this dose estimate is provided herein as Table 3-2. Task-specific dose estimates are based on the nature of the work involved in each task item, the expected number of persons to be assigned to each task, and the individual task duration periods as shown on the overall project Schedule for TRDS D&D (see Figure 21). 3 11

r PC-000482/2 TABLE 3-2: OCCUPATIONAL RADIATION DOSE ESTIMA1ES FOR 1HIGA REACTORS OFCOMMISSIONING TA j Task Task De/wdption,.- Duration No. Avg, Dose Rate Total Doeo Subtotal Total hre. persons remmr pers rem m pere.rsm No. 1 ITRIGA Reactor Facility D&D [ l j l l 2 NRC/ State approval of Decommissioning Plan r i j 3 Decommission Mkl Reactor - 112 2 0.0002 0.0448 I 0.04 f 4 Radiological Survey [,_0_064_ l 0.06 5 Remove Reactor Components above Pool 80 4 0.0002 f l 6 Remove Reactor Components in Pool 7 Grapple / Hoist / Survey 72 3 0.005 1.08 } f 72 3 0.005 1.08 8 Disassemble as necessary 9 Decontaminate or Package as LLW 64 3 0.005 0.96 3.12 l 10 Reactor Tank Water 40 3 0.0002 0.024 11 Survey / Sample / Analyze _0 3 0.0002 0.024 0.05 1 4 12 Discharge / Filter as necessary 13 install Confinement Barrier around Reactor Pit 40 d_ 0.0003 0.036 j 0.04 14 Al Tank Removal 15 Cut / Remove in sections 80 4 0.0025 0.8 64 4 0.0025 0.64 16 Segregate clean sections 17 Package LLW sections 56 4 0.002 0.448 1.89 t-18 Concrete Liner 19 Demolish activated portion 120 4 0.002 0.96 20 Remove / Package 112 4 0.002 0.896 21 SurySy remaining Concrete 32 2 0.0005 0.032 22 l Demolwh remaining portion to expose Soil 80 4 0.0005 0.16 23 l Survey Soit presumad to be clean 40 2 0.0002 0.016 40 4 0.0002 0.032 2.10 f Shore /CoverPit 24 I Survey / Remove Storage Wells,if contaminated 160 4 0.0003 0.192 0.19 25 26 D!amantle Barrier / Package for LLW disposal 40 4 0.0002 0.032 0.03 27 Decontaminate Mkl Reactor Room surfaces 80 4 0.0002 0.064 0.16 2a lDecommissten remaining areas, except MkF 29 Remove Hot Orain Lines 104 4 0.0003 0.1248 30 Remove contaminater sections, exc. from MkF Room 80 4 0.0003 0.096 31 Reroute services to isolate MkF Room 224 4 0.0002 0.1792 32 Remove Make-Up Water Tank 80 4 0.0002 0.064 33 - Dismantle / Dispose of remaining equipment in Yard 160 3 0.0003 0.144 34 ' Shro LLW to NTS 80 4 0.0003 0.096 0.70 l Decommission Mkl Totat, (person-rom): l 8.38 l (CONTINUED) i 3-12 t i

PC-000482/2 TAILE 3-2: OCCUPATIONAL RAulATION DOSE ESTIMATES FOR TRIGA REACTORS DECOMMISSIONING TASKS,(CONTINUED) Yeek~ Task Deectlption Durselon No., Avg, Does Ratei Total Dose Subtotal Total 2 , No, q: hre. - persons remthe pers-rom pers-rom pers-rem 35 l Decommission MkF Reactor l l l [ 36 i Radiological Survey h120 l 2 0.002 l 0.48 0.48 37 Remove Reactor Components in Pool { 38 Grapple / Hoist / Survey 80 3 0.005 1.2 39 Disassemble as necessary 80 3 0.005 1.2 40 Decontaminate or Package as LLW 64 3 0.005 0.96 3.36 l 41 Prepare to Ship Fuel l f ] s 42 Ship Fuel stored in MkF Canal 360 4 0.002 2.88 2.88 43 I Reactor Tenk and Storage Canal Water 44 Survey / Sample / Analyze 40 3 0.0002 0.024 45 D!Scharge/nfter as necessary 40 3 0.0002 0.024 0.05 43 install Confinement Barrier around Reactor Pit 40 3 0.0003 0.036 0.04 47 Tank Removal 48 Cut / Remove in sections 72 4 0.0025 0.72 49 Segregate clean sections 64 4 0.0025 0.64 { 50 Package LLW sections 40 4 0.002 0.32 1.68 51 Concrete Liner I 52 Demolish activated portion 112 4 0.002 0.896 53 Remove / Package 120 4 0.002 0.96 54 Survey remaining Concrete 40 2 0.0005 0.04 55 Demolish romaining portion to expose Soi! 80 4 0.0005 0.16 56 Survey Soll presumed to be clean 40 2 0.0002 0.016 57 Shore / Cover Pit 40 4 0.0002 0.032 2.10 58 Dismantle Barrier / Package for LLW disposal 40 4 0.0002 0.032 0.03 59 Decontaminate MkF Reactor Room surfaces 80 4 0.0002 0.064 0.06 60 Package contaminated tools and equipment 40 6 0.0002 0.048 0.05 61 Sh}p LLW to NTS _] 72 4 0.0002 0.0576 0,06 62 Survey Soft 112 2 0.0002 0.0448 0.04 63 Prepare Survey Report 64 Submittal for Release to Unrestricted Use l Decommission MkF Totai,(person-rem): l 10.83 l lMkl + MkF Decommissioning Project Total, (person-tem): l 19.22 l 3 13

p PC0000482/2 This estimate is provided for planning purposes only. Detailed exposure estimates and exposure controls shall be developed in accordance with the requirements of the GA ALARA program during detailed planning of the decommissioning activities. Area dose-rates used for this estimate are based on process knowledge and current survey maps ~ (where available). The dose estimate to members of the public as a result of decommissioning activities is estimated to be negligible. This is because site perimeter controls will restrict members of the public from the area where decommissioning activities are taking place. This is consistent with the estimate given for the " reference research reactor" in the " Final Generic Environmental Impact Statement on decommissioning of nuclear facilities" (NUREG-0586) (Ref.10-22)..The dose to the public during ~ decommissioning (DECON) and truck transport transportation of radioactive waste from the reference research reactor referred to in the Final Generic Impact Statement is estimated to be " negligible (less than 0.1 man-rem)." Activated pieces and any contaminated debris will be removed and shielded if required to meet U.S. DOI' shipping requiiements and NTS Waste Acceptance Criteria. 3.2 Radioactive Waste Management 3.2.1 Fuel Removal The DOE has agreed that it has a contractual obligation to accept all of the TRIGA reactor fuel at a DOE designated fuel storage facility (see Contract DE-CR01-83NE4436). A date for shipment has not yet been determined and is the subject of ongoing negotiation. The current fuel status is as follows: 'IRIGA Mark F Reactor-All reactor fuel elements have been removed from the 'IRIGA Mark F reactor core / shroud and placed in the Fuel Storage Canal. TRIGA Mark I Reactor-All teactor fuel elements have been relocated to the 'IRIGA Mark F Fuel Storage Canal. 3.2.2 Radioactive Waste Processing The processes of decontamination, remediation, and dismantlement of the 'IRDS will result in solid and liquid low level radioactive waste, mixed waste, and hazardous waste. Limited soil remediation is anticipated which will result in solid radioactive waste. This waste will be handled (processed and packaged), stored, and disposed of in accordance with applicable sections of the Code of Federal Regulations (CFR), California Code of Regulations (CCR), San Diego County and City Regulations, disposal site Waste ~ Acceptance Criteria, respective State Administrative Codes, GA Licenses and Permits, and the applicable implementing plans and procedures. Radioactive waste processing includes waste minimization or volume reduction, radioactive and hazardous waste segregation, . waste characterization, neutralization, stabilization, solidification and packaging. 3.2.3 Radioactive Waste Disposal Low level radioactive waste will be processed and packaged for disposal at the Nevada Test Site under the terms of an agreement with DOE. The volume of low level radioactive waste is estimated at 4,000 cu. ft. Mixed low level waste may be treated at GA's Nuclear Waste 3-14 C

PC-000482/2 j 1 Processing Facility or prepamd for shipment to off-site commercial processing and disposal facilities such as Envirocam of Utah. Low level mixed waste is expected to be minimal, less than'50 cu. ft. 10 CFR 61, Licensing Requirementsfor Land Disposal of Radioactive Waste, Subpart D-Technical Requirements for Land Disposal Facilities, establishes minimum radioactive \\ waste classification, characterization, and labeling requirements. These requirements will be met through the implementation of Project Packaging and Characterization Procedures, Disposal Site Waste' Acceptance Criteria, and the Quality Assurance Program Document. Traimr.g will be provided for Project Waste Certification Officials, Waste Packaging personnel, and Waste Characterization personnel to assure conformance to applicable 10 ' CFR 61 requirements as stated in the specific implementing procedures and plans. Quality Assurance conducts audits and surveillances per the Quality Assurance Program Document based on ASME-NQA-1-1989, which confirms conformance with Disposal Site Acceptance Criteria and applicable 10 CFR 61 requirements. 10 CFR 71 Packaging and Transportation of Radioactive Material, establishes requirements for packaging, shipment preparation, and transponation of licensed material. The radioactive waste that will be packaged and shipped will be LSA material. GA is a USNRC and State of California Licensee to receive, possess, use, and transfer licensed by-product and source materials.10 CFR 71 requirements will be met through the implementation of Project and GA's Nuclear Waste Processing Facility (NWPF) Packaging and Shipping Procedures. Training will be provided for Waste Packaging Personnel and Waste Shipping Personnel to assure conformance to applicable 10 CFR 71 requirements. LSNC's Nuclear Material Accountability Depanment provides compliance oversight and off-site shipment notices. Quality Assurance will confirm conformance to 10 CFR 71 Subpart H (Quality Assurance) requirements through the implementation of the GA Quality Assurance Manual and Quality Assurance Program Document.10 CFR 71 applicable Quality Assurance requirements apply to design, purcha.,e, fabrication, handling, shipping, storing, cleaning, assembly, inspection, testing, operation, maintenance, repair, and modification of components of packaging which are important to safety. 10 CFR 20.2006, Transfer for Disposal and Manifests, establishes requirements for controlling transfers oflow-level radioactive waste intended for disposal at a land disposal facility; establishes a manifest tracking system; supplements requirements concerning transfers and record keeping; and requires generator cenification that transported materials are properly classified, described, packaged, marked, and labeled, and am in proper condition for transport. These requirements will be met through the implementation of Project and NWPF Packaging and Shipping Procedures with the oversight of GA's LSNC's Nuclear Material Accountability Department. Radiological and mixed wastes will be disposed of at disposal sites per the applicable Disposal Site's Acceptance Criteria. Associated implementing plans and procedures will reflect the characterization, processing, mmoval of prohibited items, packaging and transportation requirements. Appropriate documentation will be' submitted to designated disposal sites including, as required, _ cenification plans, qualification statements, assessments, waste stream analysis evaluations and profiles, transponation plans, and - waste stream volume forecasts. Waste characterization, _ waste designation, waste traceability, waste. segregation, waste packaging, waste minimization, and quality assurance and training requirements of the designated disposal sites will be incorporated in implementing procedures to assure conformance to disposal site requirements. Generator State (California) and Treatment / Storage / Disposal Facility States (Nevada, Utah, etc.) requirements for radioactive and mixed waste management will be incorporated into 3-15

r PC 000482/2 plans and procedures to assure conformance with applicable state egulations, licenses, and permits. Applicable state regulations include Califomia Hazardous Waste Management Regulations (California Code of Regulations, Title 22), and Utah Department of Environmental Quality Rules (R313) for the control of ionizing radiation reflected in Envirocare's Utah Radioactive Material License, UT 2300249. The Project will conform to GA CAL-DHS, Radiological Health Branch (CAL-RHB) License No. 0145-80 to possess and use source and byproduct materials as directed by CCR, Title 17. GA will also conform to the CAL-EPA requirements (EPA ID Number CAD 067 638 957) which permit / authorize GA to operate as a generator of hazardous waste, to treat hazardous waste on site under California's Tiered Permit. program Conditional Authorization (CA) or . Conditional Exemption (CE) tiers, and to manage radioactive mixed wastes under Interim Status granted by the State of California Department of Toxic Substances Control (CAL-DTSC). The Project will also conform to the GA Health Permit to manage hazardous materials issued by the County of San Diego Department of Health Services Hazardous Materials Management Division (SD-DHS-HMMD). Project Plans and Procedures will also incorporate Metropolitan Industrial Waste Program (MIWP) requirements for the discharge ofindustrial waste waters into the sanitary sewer system managed by the City of San Diego (San Diego Metropolitan Water District). Radioactive waste will be staged in designated controlled areas in accordance with USNRC 10 CFR 19 and 20 requirements, CAL-DHS 17 CCR requirements, and the requirements of GA's Special Nuclear Material License and State of California Radioactive Material License. Mixed wastes will be staged in designated controlled areas per EPA 40 CFR requirements, CAL-DHS 22 CCR,10 CFR 19 and 20, and per local and state permits. Measures will be implemented through plans and procedures to control the spread of contamination, limit radiation levels, prevent unauthorized access, prevent unauthorized material removal, prevent tampering, and prevent weather damage. The designated controlled areas will be approved by WAs, Radiological Work Permits, and/or Hazardous Work Permits Radioactive and mixed waste material will be packaged for shipment per 10 CFR, 40 CFR, 49 CFR,17 CCR, 22 CCR, and the designated Disposal Site Criteria and placed in pennitted interim storage (staged) until shipped. The quantity of waste packages staged for shipment will be a function of waste generation and packaging rate, shipment preparation rate, shipment rate, and disposal site acceptance rate. To meet this objective, shipments will be scheduled throughout the life of the Project to designated treatment, storage, and disposal facilities. Radioactive material storage areas will be contained inside posted restricted areas according to existing GA procedures and consistent with 10 CFR 20. 3.2.4 General Industrial Safety Program Industrial Safety and Industrial Hygiene personnel, with Project Management, shall be responsible to ensure that the Project meets occupational health and safety requirements of Project personnel and the general public. Primary functional responsibility is to ensure compliance with the OSHA of 1973 as implemented by California Labor Code Section 6400 and the General Industry Safety Orders (GISO 3203). Sxcific responsibilities include conducting an industrial training program to instruct empoyees in general safe work practices; reviewing Decommissioning Project procedures to verify adequate coverage ofindustrial safety and industrial hygiene concerns and requirements; performing periodic inspections of work areas and activities to identify and conect any unsafe conditions and work practices; providing industrial hygiene services as required; administering the Hazardous Work Authorization Program; and advising Project 3-16

PC-000482/2 management on industrial safety matters and on the results of periodic safety inspections. The Project is supported by GA Industrial Safety and Industrial Hygiene personnel. All personnel working on the 'IRDS Decommissioning Project will receive Health and Safety training in order to recognize and understand the potential risks involving personnel health and safety associated with the work at the 'IRDS. The Health and Safety training implemented at GA is to ensure compliance with the mquirements of the USNRC (10 CFR), the EPA (40 CFR), and both OSHA and CAL-OSHA (29 CFR and CCR Title 8). Workers and regular visitors will be familiarized with plans, procedures, and operation of equipment to conduct themselves safely. In addition, each worker must be familiar with procedures that provide for good quality control. Section 2.5, Training Program, provides additional information. 3.3 Radiological Accident Analyses The potential radiological accidents for the decommissioning of the TRDS will be mainly associated with the approximately 250 'IRIGA fuel elements stored in an existing Fuel Storage Canal within the former Mark F reactor pool complex. This fuel storage may remain in effect during a pan of the decommissioning of the buildings and facilities mlated to the Mark I and Mark F reactors if arrangements to remove the fuel off site are delayed. Factors considered in assessing potential radiological accidents are:

1) Fuel storage and removal

2) Seismicity

3) Fire

4) Otherconsiderations Fuel Storage The spent TRIGA fuel elements will be stored in racks in the storage canal associated with the Mark F reactor pool. The storage canal is 15 feet deep with adequate radiation protection provided by the depth of water over the stored fuel.

The Possession Only-License conditions set forth in Refs.10.2 and 10.3 requires that fuel be moved and stored in accordance with the existing Technical Specifications and GA procedures, until removed from the site. The proposed decommissioning action does not pose any additional criticality or fission product release risk. Operations to remove Mark F 9 reactor equipment not associated with fuel storage will be conducted so as to avoid possible disruption of the Fuel Storage Canal while it is being used to store fuel. As previously stated in Section 2.3.1.2, GA plans to perform limited decommissioning tasks on the 'IRIGA Mark F reactor prior to removal of fuel from the FSC. These actions, which include the survey, handling, removal. sectioning, packaging, and disposal of hardware items not associated with or requimd for fuel storage, will necessarily be carried out in proximity to the inadiated TRIGA fuel situated in the FSC ponion of the TRIGA Mark F pool. In order to protect the security of stored fuel materials in the FSC during such operations, several administrative and engineering controls will be applied during this work, including the following existing or additional measures:

1) All existing protective deck plates covering the FSC will be installed and secured in place during any decommissioning-nlated activities.

3-17

PC-000482/2

2) All work, including decommissioning-related activities. occurring in the 'IRIGA Mark F Reactor Room will be performed by, or under the direct supervision of, currently licensed Senior Reactor Operator (s).

'3) Prior to the stan of decommissioning-related work involving the 'IRIGA Mark F pool, all unnecessary equipment and materials shall be removed from the 'IRIGA Mark F Reactor Room (refer to Figure 2.5), and a Staging Area on the north side of the 'IRIGA Mark F pool shall be cleared and prepared for receipt of hardware items mmoved from the pool. ~

4) Hardware items to be hoisted and mmoved from the 'IRIGA Mark F pool are primarily aluminum-constmetion pieces _ such as the reactor shroud, grid-plates, beam tubes, neutron / gamma radiation detectors, and etc., with no single item or component i

expected to exceed 200 lbs. i

5) Hardware items removed from the 'IRIGA Mark F pool shall be securely grappled and rigged with appropriately-cenified lifting equipment.

6) Hardware items removed from the 'IRIGA Mark F pool shall be hoisted no higher than deck level which is over the pool, using the installed 3 Ton capacity Electric Hoist or equivalent, and shall be immediately translated in a northerly direction to the Staging Area for subsequent processing. During decommissioning-related work, limit controls shall be installed on the 'IRIGA Mark F Electric Hoist to prevent translation of loads over the FSC.

Seismicity San Diego County has been considered one of the more moderate seismic risk regions in Southem California. The historical pattem of seismic activity has generally been characterized by a broad scattering of small magnitude earthquakes, whereas the surrounding regions are characterized by a high rate of seismicity with many moderate-to-large-magnitude canhquakes. Arecent study (see Appendix B, Ref. 5.8) estimated the probabilities of large earthquakes occurring in California on the major strands of the San Andreas fault system. In addition to the principal traces of the San Andreas fault, earthquakes occurring on the other major faults of the system (San Jacinto, Imperial, etc.) were also considered. The study estimated that the probability of a magnitude 7 or greater earthquake occurring in the next 30 years in Southern Califomia (along the Southern San Andreas, Imperial, or San Jacinto faults) is 0.5 or greater. However, a quake of magnitude close to 7 on these fault lines is not expected to significantly impact the GA site because ofintervening distance. Current information (see Appendix B, Ref. 5.9) however, indicates the Rose Canyon, Coronado Bank, San Diego Trough, La Nacion, and Elsinore fault zones are capable of generating strong ground motion in the San Diego area. Possible Richter magnitudes for canhquakes on these faults can be as high as 7.0, 7.5, 7.5, 6.3 and 7.5, respectively. Passing approximately 3 miles (5 km) west of the GA site, the Rose Canyon fault is the nearest active fault. The presence of thme small, local faults was confirmed by the Woodward-Clyde Consultants field mconnaissance of the site (see Appendix B, Ref. 5.11). An unnamed fault in the nonhern ponion of the site trends east to west through proposed lots 25, 26, 31, and 32. The Salk fault is mapped in the southern ponion of the site and also trends east to west. A northerly trending fault is located in the southeastern ama and crosses the 3-18

W PC-000482/2 L Genesee Avenue canyon. All of these faults'are mapped as being overlain by early - Pleistocene formations which have not been displaced. Therefore, the faults on-site are not considered active. l Decommissioning activities will involve decontamination and remediation, Plans and l specifications for any remediation which could affect the structural integrity of the building l would be reviewed by a structural engineer to assure that these alterations would not render the building unsafe. Decommissioning will not pose added risk to workers during a seismic l* event. Eirc The 'IRDS will not contain combustible material in sufficient quantity to support a major - fire. It is possible for a small fire to occur as a result of an electrical fault, as an example. Portable extinguishers and detection will be provided as needed. Them should be no radiological hazard as a result of fire. Other Considerations Radiological accidents could occur during removal and packaging of activated components and equipment. However, this risk is very low considering the administrative precautions which will be taken during decommissioning. GA experience in D&D projects, including the handling of activated / contaminated components and control of job activities utilizing written and approved procedures, will casure the safe conduct of the project. Consequences of a pool leak are low because the pool water is continuously treated and contains negligible radioactivity. The main function of the pool is to provide shielding for workers positioned near or over the FSC during any required handling, inventory related, or training operations. The water is not required for fuel cooling. Any failure to meet shielding requirements would result in worker restrictions on approach to the FSC until the requirement could be met. The other potential consequence would be due to flowing water carrying loose contamination to a new location within the facility, outside the facili*y, or 'into the soil. Since loose contamination is minimal, the risk of spread of contamination is low. There is no potential for airborne contamination from such an event. e I' 3-19 o

n PC-000482/2 4. PROPOSED FINAL RADIATION SURVEY PLAN The intended course of action for 'IRDS decommissioning, based upon consideration of site and facility radiological characterization results, is to strive to decontaminate structural materials to the extent practica)le in balance with radioactive waste minimization considerations, and dismantle TRDS systems to the extent necessary for remediation, and packaging for burial those materials . that cannot reasonably be decontaminated. As such, the Final Release Survey Plan (and subsequent Final Survey Report) discussed in this section deals with release of the building structure of the TRDS remaining after decontamination and remediation actions, and the 'IRDS propeny to unrestricted use. This section will also discuss the survey methods that will be utilized. 4.1. Description of Final Radiation Survey Plan The purpose of the Final Radiation Survey is to demonstrate that the radiological condition of the 1RDS site structure are at or below established release criteria (see Section 2.8) in anticipation of U.S. NRC approval to terminate the 'IRIGA Reactor licenses and to release the 3RDS for unrestricted use. The Final Release Survey Plan (and repon) will deal with release of the 1RDS structure and site to unrestricted use. GA has developed its Final Release Survey Plan using the guidance provided in NUREG/CR-5849 (draft) (Ref.10.10). 4.1.1Means for Ensuring that all Equipment, Systems, Structures, and Site are Included in the Survey Plan Every item that is to be removed from the TRDS will be evaluated for ability to b decontaminate and radiologically surveyed to ensure that radioactive (i.e., licensed) materials are not inadverently removed from the facility (see Section 3.1.3). When it is impractical or not possible to decontaminate an item such that it exhibits no discernable facility-related activity when surveyed following methods presented in Section 3.1.3, the item will be treated as radioactive waste. The systematic approach to TRDS decommissioning will ensure that every item or structural component in the 3RDS is specifically evaluated for release before beginning the Final Release Survey. The Final Release Survey will treat the TRDS as "affected" to ensure 100% survey coverage prior to requesting 1RDS reactor license termination and release of the property for unrestricted use. 4.1.2Means for Ensuring that Sufficient Data is Included to Achieve Statistical n Goals GA has developed the TRDS Final Release Survey Plan using the guidance presented in NUREG/CR-5849. By using this guidance, the Project will satisfy the U.S. NRC recommended statistical goals. '4.2 Background Survey Results The Final Release Survey Guideline values for residual activity are taken to be levels above the naturally occurring backgronad radiation. The final release measurements will consist of a combination of general aza radiation values and area surveys. In addition, a detailed micro-R radiation survey of the remaining structure and site will be performed and compared to background measurements. 4-1

i PCo000482/2 i Background radiation as encountered at any location includes contributions due to both natural radiation sources and manmade sources. Natural radiation sources include terrestrial radioactivity due to naturally occurring radioisotopes in soils and construction media, airborne radioactivity (principally radon and radon progeny) from the radioactive decay of certain of these naturally occurring radioisotopes, and cosmic radiation from high speed particleinteractions in the earth's atmosphere. Manmade background radiation as it would impact the Final Release Survey would primarily consist of atmospheric fall-out of fission products due to weapons testing and reactor accidents and any contribution that might exist i as a result of other licensees' activities. The general area background radiation as would be measured with the micro-R meter is influenced by a number of factors, principally the naturally occurring radioactivity in soils and other nearby materials, radon and radon progeny concentrations in the air, and extent of cosmic radiation (which varies with elevation). Due to the number of influences, the natural background varies appreciably from location to location, day-to-day (even time of day) and season-to-season as related to changing weather conditions and materials in the surroundings. The site and facility characterization study included measurements to establish background radioactivity in soils, concrete, and asphalt that were considered representative of those that would be encountered in the Final Release Survey. One of the principal constituents of global fallout, '"Cs, which is found principally as a result of atmospheric weapons testing and reactor accidents is also the principal fission product contaminant at the 'IRF. '"Cs has been seen to be persistent in the upper 15 cm (6 in.) of soil with concentrations decreasing beyond this depth (Ref.10.12). Release criteria (e.g., Regulatory Guide 1.86) were established as an increment in excess of background values. Therefore, the Final Release Survey will include the establishment of background area radiation levels using the guidance of NUREG/CR-5849. Asphalt, concmte and other construction material background values will be established by taking measurements on unaffected facilities and/or portions of the GA property representative of i unaffected TRDS construction materials. 4.3 Final Release Criteria-Residual Radiation and Contamination Levels The criteria for release of the 'IRDS facility / site to unrestricted use, after completion of the decommissioning activities described in this plan, am presented in Section 2.8. In summary, they are: 1) those given in the U.S. NRC Regulatory Guide 1.86, " Termination of Operating Licenses for Nuclear Reactors," and 2) an exposure rate due to residual radionuclides - as a asult of facility operation - not in excess of 5 micro R/hr above natural background measured at 1 meter from the surface. (Ref. " Action Plan to Ensure Timely Cleanup of Site Decommissioning Management Plan Sites," FR Vol. 57 No. 74 April 16, 1992). 4.'4 Measurements for Demonstrating Compliance with Release Criteria 4.4.1 Instrumentation-Type, Specifications, and Operating Conditions Instrumentation utilized during the Final Release Survey (and equipment and materials survey) will be selected based upon the need to ensure that site residual radiation will not exceed the micase criteria. In order to achieve this goal, instrumentation that is sensitive to the isotopes of concern and capable of measuring levels below 75% of the guideline values for those isotopes will be selected. Instrumentation selected will be based upon the recommendations of NUREG/CR-5849. Instrumentation that is available for the Final 4-2

PC 000482/2 Release Survey, and their respective detection range capability was presented in Table 3-1 of this plan. Instrumentation that is used in the surveys will be calibrated against sources and standards that are NIST traceable and representative of the representative isotopes encountend at the TRDS. Instruments will be operationally tested daily, or prior to each use, whichever is less frequent. Instruments will not be used in conditions that are not in conformance with manufacturer recommendations. 4.4.2 Measurement Methodology for Conduct of Surveys The entire TRDS site will be treated as an "affected" area in accordance with the definition provided in NUREG/CR-5849. The yard area was characterized during facility radiological characterization scoping survey. This Decommissioning Plan presumes that the 1RDS has ~ been decontaminated to the extent practicable prior to the Final Release Survey. The TRDS structure and site will be methodically remediated as necessary prior to conduct of the Final Release Survey. The characterization results and the continuous feedback from remediation surveys will be the basis for mmediation efforts. The only radionuclides identified in the TRF and adjacent yards during radiological characterization efforts were "7Cs (predominant nuclide), "Co and to a lesser extent (in only one soil sample) "#Cs. These isotopes am readily detectable using p--y sensitive instrumentation. Furthermore, all of these isotopes are readily detectable with gamma I spectrometry techniques as well. To support the final survey, portions of the TRDS will be gridded into areas that are 10 meters by 10 meters. Each grid will be surveyed initially with a surface scanning instrument system to ascertain locations of any elevated concentrations. In addition, systematic measurements may be performed within each grid at locations equidistant between the center and each of the four grid block corners.

If any location within a grid requires remediation in order to support a decision in favor of release to unrestricted use, the entire affected grid will be scanned again after completion of remediation efforts.

4.4.3 Fixed Contamination Survey Protocol The surfaces of equipment and materials will be surveyed in accordance with Project and GA HP procedures for release of equipment and materials to unrestricted use. Dhect frisk will be performed with either a portable Geiger-Mueller, or a gas flow proportional detector, as dictated by the minimum detectable activities of the instrument / probe, or beta-scintillator for the contaminants of concern and the associated release criteria. In any situations where process knowledge would suggest a potential for alpha activity, survey with alpha detection instruments or counters will also be employed. In evaluation of equipment and materials for fixed or smearable licensed materials, items painted with other than original manufacturer's paint will not be released unless (1) clear process knowledge ) demonstrates that the paint was applied to a clean non-radioactive surface prior to use in the .] t restricted area, (2) the paint is removed or (3) Health Physics approved paint sampling . survey demonstrates that radiation levels under the paint are below the release criteria. If the 1 potential exists for contamination on inaccessible surfaces, the equipment will be assumed to'be internally contaminated unless (1) the equipment is dismantled allowing access for surveys, (2) appropriate tool'or pipe monitors with acceptable detection capabilities are l utilized that would provide sufficient confidence that no licensed materials were present, or (3)it may readily be concluded that surveys from accessible areas are representative of the inaccessible surfaces (i.e.,' surveying the internal surface from both ends of a straight pipe from a nonradioactive process system with cotton swabs would be representative of the inaccessible areas). The results of contamination surveys will be recorded either on survey 4-3 J

PC-000482/2 maps or special release logs. Results of all surveys will be compared to average and maximum criteria prior to any material being released. 4,4.4 Removable Contamination Survey Protocol 2 Removable contamination will be assayed by collection of 100 cm smears from surfaces, or as practicable. The smear samples will be evaluated using suitable hand held instruments or low level beta counting systems. As discussed in Section 4.4.3, smears will be evaluated for alpha contaminants if process or survey information recommends this, though 'IRDS Decommissioning Health Physics personnel routinely evaluates a portien of its positive smears for alpha contamination. Survey evaluations are recorded in the same manner described in Section 4.4.3. 4.5 Methods to be Employed for Reviewing, Analyzing, and Auditing Data 4.5.1 Laboratory / Radiological Measurements Quality Assurance During decommissioning survey activities, many direct and indirect measurements and sample media samples will be collected, measured, and analyzed for radiological contaminants.The results of these surveys will be utilized to evaluate the suitability of the material or item for release to unrestricted use, or whether decontamination of structures, components, and the surrounding site have achieved the desired result. Sample collection, analysis, and the associated documentation will adhere to written procedures and meet the guidance of the U.S. NRC, as well as comply with recognized industry recommendations and good practices. Outside (i.e., non-GA) laboratories selected to analyze 'IRDS decommissioning samples shall be approved by the GA Quality Assurance organization and listed on the QA Approved Suppliers List maintained by the GA Quality Assurance Group. Organizations that perform radiological monitoring measurements recognize the need to establish quality assurance programs to assure that radiological monitoring measurements are valid. These programs are established for the following reasons: (1) to readily identify deficiencies in the sampling and measurement processes to those individuals responsible for these activities so that prompt corrective action can be taken, and (2) to routinely monitor the survey and laboratory measurement results in order to assure that results and conclusions are valid. 4.5.2 Supervisory and Management Review tf Results Radiological surveys are conducted by Health Physics Technician staff members who are trained and qualified. In addition, radiological surveys and sample results are reviewed by a senior level member of the Health Physics staff other than the individual that performed the survey. Final Radiation Survey data is also reviewed by the HP Manager and the 'IRDS Decommissioning Project Manager. i 44

PC-000482/2 ] 5. TECHNICAL SPECIFICATIONS Currently applicable Technical Specifications for the GA 'IRIGA Mark I Reactor are set forth in Amendment No. 35 to Facility License No. R-38 (IRIGA Mark I Reactor)--General Atomics (TAC No. M97502), Issued by the USNRC, dated October 29,1997 (Reference 10.2). Currently applicable Technical Specifications for the GA TRIGA Mark F Reactor are set forth in Amendment No. 43 to Facility License No. R-67 (IRIGA Mark F Reactor)-General Atomics ) (TAC No M90380), Issued by the USNRC, dated March 22,1995 (Reference 10.3) ] As decommissioning progresses, further requests for changes to the Technical Specifications will be submitted in an application for amendment to the license pursuant to 10 CFR 50.59. 1 1 e i { I 1 l 4 5-1 i

PC-000482/2 6. PHYSICAL SECURITY PLAN All GA radiation restricted areas are secured from unauthorized entry. During non-working hours, all nuclear facilities are locked. GA maintains 24 hour security watchmen to patrol the site. Existing physical security and material control and accounting plans approved by the Nuclear Regulatory Commission, as may be amended, will continue to be implemented. These existing plans meet the requirements in 10 CFR 70.38 for decommissioning, and will be maintained as required by the MkF Possession Only License amendment (Ref.10.3), and the Mk1 Possession Only License amendment (Ref.10.2). Compliance with Parts 50 and 73 of the physical security plan is assured because all of the elements of the plan are maintained until the fuel is removed offsite. Decommissioning activities will be conducted with the fuel in the FSC and all physical security and surveillance in place. Once isolation of cornmon services has been implemented the security of the Mark F reactor and control rooms can be maintained without impact on decommissioning activities in the Mark I reactor room. Workers will be limited in number and appropriately trained before entry to the site. Oversight will be provided during any entry into the Mark F room for purposes of reactor equipment removal not associated with the FSC or fuel, i 61

) PC-000482/2 1 7. EMERGENCY PLAN GA has a Radiological Contingency Plan, supplemented by procedures specific to the 'IRF, as required by the USNRC and State of California. Training on the Radiological Contingency Plan is provided to the Emergency Response and Recovery Director and Alternates. Emergency Response Team members receive training appropriate for responding to emergencies. ~ 0 ) 71

PC-000482/2 8. ENVIRONMENTAL REPORT The Environrnental Report is provided as Appendix B. 2 h 81

y PC 000482/2 s. CHANGES TO THE DECOMMISSIONING PLAN As the decommissioning progresses, changes to the Technical Specifications up to termination of tl.e license will be via a Request for License Amendment pursuant to 10 CFR 50.90. GA requests that other changes to the Decommissioning Plan be allowed without prior USNRC approval which involve decommissioning activities unless an unreviewed safety questions-is involved. An unreviewed saiety question involves: .1. The increase of probability of occurrence or the increase of consequences of an accident or malfunction of equipment important to safety compared to that situation previously evaluated in the SAR, or i f

2. The possibility for an accident or malfunction of a different type than previously analyzed in the

{ S AR, or

3. The reduction in margin of safety as defined in the S AR, 1

Reports, records of change, and retention of documents will be in accordance with the applicable ) portions of 10 CFR 50.59. { u i 91

U PC 000482/2 i 10. REFERENCES E10.1 ' NUREG-1537 Rev. O, " Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors". 10.2 Amendment No. 35 to Facility. License No, R-38 '(TRIGA Mark I Reactor)-General - Atomics (TAC No, M97502), Issued by the USNRC, dated October 29,1997. ~ 10.3 Ameadment No. 43 to Facility Licence No. R-67 (TRIGA Mark F Reactor)-Genend Atomics (TAC No.'.M90380), Issued by the USNRC, dated March 22,1995. 10.4 ' USNRC License No. R-100 (terminated). 10.5' Asmussen,- Keith E. letter No. 696-2581 to Document Control Desk, USNRC, A'ITN: Mr. Alexander Adams, Jr. And Mr. Charles E. Gaskin. " Docket Nos. 70-0734, 50-89 and 50-163; Decommissioning Financial Assurance," dated May 20,1996. 10.6 Weiss, Seymour H. And Robert C. Pierson Letter to Dr. Keith E. Asmussen, " Financial. Assurance for USNRC Licenses SNM-696, R-38, R-67/ Docket Nos. 70-0734,50-89, 50-163," dated July 9,1996. .10.'7 ' ASME-NQA-1-1989," Quality Assurance Program Requirements for Nuclear Facilities". j 10.8 General Atomics Quality Assurance Program Approval by the USNRC Transportation & Storage Inspection Section, Spent Fuel Project Office, Nuclear Materials Safety and 1 Safeguards, Approval No. 0030 Rev. 6, July 9,1996. 10.9 USNRC Regulatory Guide 7.10. " Establishing Quality Assurance Programs for Packaging Used in the Transport of Radioactive Material".- 10.10 NUREG/CR-5849, " Manual for Conducting Radiological Surveys in Support of License Termination," Draft for Comment, June 1992, j

10. I 1. ANSI Z88.2-1980, " Practices for Respiratory Protection".

10.12 National Council on Radiation Protection and fuasurements (NCRP), NCRP Report No. 50, " Environmental Rt.diation Measurements," December 27,1976. ~10.13 U. S. Nuclear Regulatory Commission Regulatory Guide _4.15. " Quality Assurance for Radiological Monitoring Programs (Normal Operations)--Effluent Streams and the Environment," Revision 1, February 1979. 10.14 " General Atomics Site Decommissioning Plan" Licensing, Safety, and Nuclear Compliance g Organization, General Atomics, San Diego, CA'; Dated September,1996, Revised December,190'i, April,1997, January,1998, and July,1998. 10.15 '"Nuclides and Isotopes, Chart of Nuclides;.14th Edition " Nuclear Energy Operations, General Electric Company, San Jose, CA; 1989. 10.16 ANS Standard 15.8," Quality Assurance Program Requirements for Research Reactors." 10.17. GA Radiological Contingency Plan. 9 Q 10-1

PC-000482/2 10.18 U.S. Atomic Energy Commission, Regulatory Guide 1.86, ' Termination of Operating Licenses for Nuclear Reactors," dated June 1974. 10.19 U.S. Nuclear Regulatory Commission, " Action Plan to Ensure Timely Cleanup of Site Decommissioning Management Plan Sites," Federal Register /Vol. 57, No. 74/ Thursday, April 16,1992. .10.20 U.S. Nuclear Regulatory Commi.<sion, IE Circular No. 81-07, " Control of Radioactively Contaminated Material," May 14,1981. 10.21 U.S. Nuclear Regulatory Commission, IE Information Notice No. 85-92, " Surveys of Wastes Before Disposal From Nuclear Reactor Facilities," December 2,1985. 10.22 U.S. Nuclear Regulatory Commission, NUREG-0586, " Final Generic Environmental Impact Statement on decommissioning of nuclear facilities," August 1988. p 10.2 1 .f. 7

i I PC 000482/2 l APPENDIX A

SUMMARY

OF i CHARACTERIZATION RESULTS i 4 I I l 1 1 A-1 i 1 f ij

PC-000482/2 LIST OF TABLES Table A-1-TRF Area Classifications for Characterization........................................... A-4 Table A-2-Results of Radiochemical Analyses for1RF Soil Media Samples..................... A-5 Table A-3-Results of Radiochemical Analyses for1RF Asphalt / Concrete Media Samples...... A-6 LIST OF FIGURES Figure A-1-Grid Map of1RIGA Reactor Facility used for Media Sample Locations for Radiological Scoping S tudy.................................................................... A-7 Figure A-2-Grid Ma? ofTRIGA Reactor Facility showing Radiological Measurement Results from Raciological Scoping Study...................................................... A-8 Figure A-3---Schematic of the Room Layout for the1RIGA Reactor Facility, Building 21....... A-9 - LIST OF SURVEY RESULTS Rm. 21/102, S urvey #21 00004.............................................................. A-10 -00005.................................................................A-ll -0002 3.............................................................. A-1 2 -00009................................................................. A-1 3 -00019..................................................................A-14 Rm. 21/105, S urvey #21 00030.................................................................. A-15 -00036.....................................................................A-16 -00032....................................................................A-17 -00037...................................................................A-18 -00031..................................................................A-19 R m. 21/106, S urvey #21 00029................................................................ A-20 -00038...................................................................A-21 -0003 3............................................................... A-2 2 -000 3 9................................................................ A 23 -00034..................................................... ........ A-24 Rm. 21/107, S urvey #21 97-00010.................................................................. A-25 -00011..................................................................A.-26 -00024.................................................................A-27 -00012.................................................................A-28 -00014....................................,...........................A-29 Rm. 21/108, S u rvey #21 00025.............................................................. A-30 -00027..................................................................A-31 -00040................................................... ... A-3.2 -0002 6................................................................ A-3 3 -0002 8............................ ..................................A-34 Rm.' 21/109, S urvey #21-97-0004 6................................................................ A-35 ) -00048..................................................................A-36 -00044.............................. ..........................A-37 -00050....................................................... ....... A-3 8 -0004 5............................................................... A-3 9 . Rm. 21/1 10, S urvey #21 00041................................................................ A-40 -00047.................................................................A-41 -00043.................................................................A-42 -0004 9........................................................... A-4 3 -0004 2...........................................................,. A-44 1 l A-2

i PC-000482/2 Rm. 21/1 11. S urvey #21 00016.................................................................. A-45 -M17....................................................................A46 o -0003.3......................................................................A-47 -W18..................................................................A48 o -@l5....................................................................A49 Rm. 21/1 12, S urvey #21 00052..................................................................... A-50 654.....................................................................A-51 u a- -WJJ...................................................................A-5, o -@59................................................................A-53 -00058....................................................................A-54 Rm. 21/113, S urvey #21 -97 00051................................................................... A-55 -M53.............................................................A-56 ,M56..................................................................A,57 o s o 6....................................................................A-58 -000 5 7............................................................. A-5 9 Rms. 21/114 & 115, S urvey #21 00063........................................................ A-60 -N...........................................................A-61 o -0006,..........................................................A,63 -M1........................................................A-63 21/Roo f, S u rvey #21 00006....................................................................... A-64 ~ - 7......................................................................*6v4 }Q

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PC-000482/2 APPENDIX A

SUMMARY

OF CHARACTERIZATION RESULTS Radiological Scoping Study A radiological scoping study was performed on the 'IRIGA Reactor Facility (1RF) to support decommissioning planning. Due to the operational status of the TRIGA Mark I Reactor, the radiological scoping characterization was not an invasive study that involved defacing facility structures by collection of building construction media samples. Outside the TRF media samples were obtained for surrounding soils, asphalt, and concrete. The 1RF was first evaluated from process knowledge and past radiological surveillance. Based upon this evaluation, various portions of the complex and its associated yard are classified as either "affected" or " unaffected." Affected areas are areas that have potential radioactive contamination (based on process knowledge) or known radioactive contamination (based on past radiological surveillance). Unaffected areas are all areas not classified as affected. Table A-1 shows the - classifications of areas within the facility. Table A-1-TRF Area Classifications for Characterization Octed Areas Unaffected Areas Room 102-Mark I Reactor and Control Rcom Room 100-Office Room 105-Tool Shop Room 101-Office Room 106-Counting Room ^ Room 101 A-Dark Room Room 107-Mark F Reactor Room 103-Of0ce Room 108-Mark F Control Room Room 104-Office Room 109-Mark III Control Room Restrooms Room 110-Mark III Experimental Area Entry and Office Area Corridors Room 1Il-Mark Ill Reactor Electrical Pads Room ll2-Thermal Stability X-Ray Room Room ll3-Thermal Stability Lab Room i14-North Entry Room ll5-Decontamination Room All Yard Area / Roof Mark i Shed Cooling Tower Yard Area Storage Shed Machine Shop Sampling protocol, sample preparation, survey and media result documentation, and analytical methods for the scoping study were based upon Refs. A-1 through A-7. Pages A-10 through A-68 are copies of the survey maps from the study. Surrounding Soils. Asphalt. antConcrete Agrid map of the'IRF, including building surrounding areas (soils, asphalt, concrete) is provided m Figure A-1. ) Systematic media samples of the TRF were obtained at grid intersections shown in Figure A-2, In addition,onejudgment sample location was used to obtain soil / asphalt samples based on process . knowledge. Thirty-two soil media samples, 21 ~ asphalt media samples, and one concrete media sample were obtammi for radiochemical analysis.The first approximate 6 inch depth of soil in the shape of a 4 inch diameter cylinder, carved out by a coring tool, was obtained for soil media samples. In one case, location (X,1), no soil could be collected due to the depth of the asphalt. Asphalt and concrete media samples were obtained similarly using the coring tool to produce i approximate 6 inch tall, 4. inch diameter cylinddcal samples of asphalt / concrete. Figure A-2 1 presents the media sample radiological tesults entered on the grid map, for the 1R F. A4

1 PC-000482/2 The results of radiological analyses for soil media samples including sample location and identifica-tion number are provided in Table A-2, The results of radiological analyses for asphalt / concrete media samples including sample location and identification number are provided in Table A-3. Facility Affected Areas The radiological scoping survey showed the facility an as to be well maintained with only minor amounts of residual radioactivity discovered. It is recognized that components associated with the 1RIGAreactors, and some surrounding structural materials will be activated as a result of mactor operations. Inside of the facility itself, surveys of affected areas showed very little residual radioactivity. Rooms 102 and 107, the Mark I and Mark F Reactor rooms respectively, both showed severallocations of fixed radioactivity on the floor surfaces, and Room 107 also had one i location ofloose surface activity. Figure A-3 is a schematic of the room layout for the TRF. l l l Table A 2-Results of Radiochemleal Analyses for TRF Soll Me:lla Sample.s Location & Remarks Sample ID Gamma Isotopic Results (pCi/g) Grid (X,4). soil sample beneath asphalt 21S-97-001 natural activity only Grid (X,5). soil sample beneath asphalt 21S-97-002 0.04 '"Cs Grid (Y,4), soil sample beneath asphalt 21S-97-003 natural activity only Grid (Z,5), soil sample beneath asphalt 21 S-97-ON 0.N '"Cs, 0.10 '"Cs Grid (Y,6), soil sample beneath asphalt 21S-97-005 natural activity only Grid (Z,6), soil sample beneath asphalt 21S-97-006 0.06 "'Co. 0.37 '"Cs Grid (Y+0.5,6.5). soil sample beneath asphalt 21S-97-007 0.26 '"Cs Grid /(Y,7), soil sample beneath asphalt 2]S-97-008 0.03 "'Co, 0.53 '"Cs Grid (X,6), soil sample only 21S-97-009 0.45 *Co, 0.02 '"Cs,1.24 '"Cs Grid (Y,5), soil sample beneath asphalt 21S-97-010 natural activity only Grid (Z,7), soil sample only 21S-97-011 9.24 *Co. 29.59 '"Cs Grid (W. 4). soil sample beneath asphalt 21S-97-012 natural activity only Grid (Z,2), soil sample only 215-97-013 0.43 "Co 0.59 '"Cs Grid (Z,1), soil sample only 21S-97-014 0.69 "Co, 0.43 '"Cs Grid (2,0), soil sample only ' 21S-97-015 0.30 "Co. 0.30 '"Cs Grid (Y,0). soil sample only 21S-97-016 0.16 *Co, 0.42 '"Cs Grid ( A,1). soil sample only 21S-97-Ol7 0.95 *Co,1.26 '"Cs Grid (Z, -1), soil sample only 21S-97-018 0.11 *Co. 0.17 '"Cs Grid (Y, -1), soil sample only 21S-97-019 0.06 *Co. 0.20 '"Cs I Grid (X, -I), soil sample only 21S-97-020 0.22 *Co, 0.29 '"Cs l Grid (U,1), soil sample only 2 t S-97-021 011 "Co. 0.60 '"Cs ~ Grid (A 4), soil sample beneath asphalt 21S-97-023 0.10 '"Cs l Grid ( A,3), soil sample beneath aspt alt 21S-97-024 natural activity only j Grid (A,2), soil sample beneath concrete 2 t S-97-025 0.04 '"Cs j Grid (V,2), soil sample beneath asphalt 21S-97-026 natural activity cnly j Grid (V, I), soil sample beneath asphalt 21S-97-027 natural activity only { Grid (X,0), soil sample beneath asphalt 21S-97-028 natural activity only j Grid (X,3), soil sample beneath asphalt 21S-97-029 0.06 '"Cs Grid (V, OL soil sample beneath asphalt 21S-97-030 natural activity only Grid (W, OL Soil sample beneath asphalt 'lS-97-031 natural activity only l Grid (W IMoil sample beneath asphalt 21S-97-032 natural activity only j Grid (Y.1), soil sample beneath asphalt 21S-97-033 natural activity only i i 4 A5 )

PC-000482/2 Table A 3-Results of Radiochemical Analyses for TRF Asphalt / Concrete Media Samples Location & Remarks Sample ID Gamma Isotopic Results (pCi/g) Grid (X,4), asphalt sample 21B-97-001 natural activity only Grid (X,5), asphalt sample 21B-97-002 natural activity only Grid (Y,4), asphalt sample 21B-97-003 natural activity only Grid (Z, 5), asphalt sample 21 B-97-0(M 0.48 "'Cs Grid (Y,7), asphalt sample 21 B-97-005 0.38 "'Co,1.38 "'Cs Grid (Y,6). asphalt sample 21B-97-006 0.30 "'Cs i Grid (Z,6), asphalt sample 21B-97-007 1,32 "'Cs j Grid (Y+0.5,6.5), asphalt sample 21B-97 008 2.90 "'Cs Grid (W,4), asphalt sample 21B-97-009 natural activity only Grid (Y,5), asphalt sample 21 B-97-010 0.40 "'Co, 0.16 "'Cs Grid (X, 3), asphalt sample 21 B-97-011 0.22 "7Cs Grid (A,4), asphalt sample 21 B-97-012 0.31 "'Co, 0.25 "'Cs Grid (X. 0), asphalt sample 21B-97 013 natural activity only Grid (Y,1), asphalt sample 21B-97-014 0.35 "'Cs Grid (V,2), asphalt rample 21B-97-015 natural activity only Grid (V,1), asphelt sample 21B-97-016 natural activity only Grid (W,1), asphalt sample 21B-97-017 natural activity only l Grid (V,0), asphalt sample 21B-97-018 natural activity only Grid (W, On, asphalt sample 21B-97-019 natural activity only Grid (X,1), asphalt sample 21B-97-020 0.73 "'Cs Grid (A,3), asphalt sample 21B-97-021 natural activity only Grid ( A,2), concrete sample 21C-97-001 natural activity only Unaffected Areas The remaining rooms and areas of the TRF are considered unaffected areas. For these unaffected areas, radiological surveys consisted oflarge area masslin smears of the floor and walls to roughly 2 meters above the floor, at 1 m intervals, floor monitor / surface scan surveys, and contamination 2 surveys of floor drains and sinks. No areas of contamination were discovered in surveys of unaffected areas, A-6

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PC-000482/2 1 l i l l APPENDIX B l ENVIRONMENTAL REPORT S B1

c PC-000482/2 TABLE OF CONTENTS

1. PURPOSE AND NEED FOR A CTION........................................... B - 4

2. FACILITY DESCRIPTION, PROPOSED ACTION AND ALTERNATIVES, AND ADMINISTR ATIVE CONTRO LS.......................................... B - 4 2.1 Facility Description.................................................................................. B -4 2.2 Proposed Action and Altematives..........................................

....B-10 2.3 Administrative Controls.................................................... ....................B-ll

3. DESCRIPTION OF THE AFFECTED ENVIRONMENT.......................B-12 3.1 M an-M ade En vironment........................................................................B - 12 3.1.1 Radioactive Materials..................................................................B - 12 3.1.2 H azardous Materials......................................................................B - 14 3.1. 3 Transportation................................................................................ B - 14 3.1.4 Cultural and Historical Resources...........................................................B-15 3.1.5 Population and Land Use..................................................................B-15 3.1. 6 N oi s e......................................................................................... B -

3. 1. 7 Aesthe tic s.....................................................................................B - 3.2 N atural Environmen t................................................................................B - 16 3.2.1 Topography, Geology and Seismicity....................................................B-16 3.2.2 Climate and Air Quality..................................................................B-17 3. 2. 3 H y dro l ogy..................................................................................... B - 19 3. 2.4 B i o l o gy........................................................................................ B -2 0 3.2.5 Socioeconomics and Environmental Justice...............................................B-21

4. POTENTIAL ENVIRONMENTAL CONSEQUENCES OF PROPOSED A CTION AND ALTERNATIVES................................................B - 21 4.1 H uman He alth Effects.............................................................................B -21 4.1.1 Hazard Identification........................................................................B -21 4.1.2 Potential Exposures............................................................................B-22 4.1.3 Transponation.............................................................................. B -23 4.2 Waste Disposal........................................................................................ B -23

4. 2.1 H azard ous Waste.........................................................................B -2 3 4.2.2 Low-Level Radioactive and Mixed Waste................................................B-23 i

4.2.3 Non Hazardous Solid Waste..........................................................B-24 { 4.3 Noise...........................................................................................B-24 4.4 S e i s mi c i t y..................................................................................... B -24 4. 5 Air Q u ality......................................................................................... B -24 4.6 Regulatory Issue s..............................................................................B-2 5 4.7 Areas N ot Affected............................................................................B -25 4.8 Cu mul ative Effects................................................................................... B -25 4.9 Altematives to Proposed Action................................................................ B -2 7

5. R E F E R E N C ES...................................................................B - 2 7 4

i B-2

PC 000482/2 LIST OF FIGURES Figure B-1 -Regional L o c a t i o n...................................................................... B - 5 Figure B-2-GA Site and Surrounding Uses...................................................... B-6 Figure B-3-TRIGA Reactor Facility Site and Adjacent GA Structures...........................B-7 Figure B A 'IRIGA Reactor Facility Areas Within Decommissioning Plan Scope...............B-8 Figure B-5-TRIGA Reactor Facility, Room Detail, PlanView..................................B-9 LIST OF TABLES Table B-1-List of Potential Radionuclides.........................................................B-13 Table B-2-Applicability of Environmental Statutes and Regulations............................B-26 = B-3

l l PC-000482/2 APPENDIX B ENVIRONMENTAL REPORT

1. PURPOSE AND NEED FOR ACTION As a result of nuclear research training and isotope production, activities conducted since 1958 for the DOE and its predecessor agency, the Atomic Energy Commission ( AEC), and commemial customers, the 1RIGA* Reactor Facility (TRF) has become contaminated with varying amounts of radioactive materials and small amounts of hazardous materials. GA decided to shut down the TRF due to reduced demand for irradiation services and continuing private industrial development around the site. Decontamination and Decommissioning (D&D) of the TRF will eliminate the potential for future inadvertent environmental releases. The goal of the proposed D&D activities is to obtain from the United States Nuclear Regulatory Commission (USNRC) and the State of Califomia -

Department of Health Services (CAL-DHS) release of the site for " unrestricted use." The term " unrestricted use" means that there will be no future restrictions on the use of the site, other than those imposed by the City of San Diego zoning ordinances.

2. FACILITY, DESCRIPTION, PROPOSED ACTION AND ALTERNATIVES, AND ADMINISTRATIVE CONTROLS 2.1 Facility Description

. The 1RF is located within the General Atomics (GA) Torrey Mesa " Main Site," in San Diego, CA. GAcccupies approximately 120 acres (48 hectares) on two contiguous areas approximately 13 miles (21 km) north of downtown San Diego, California which is situated southwest of the convergence ofInterstates 5 and 805, and approximately one mile east of the Pacific Ocean. The two locations am referred to as the " Main Site" and the "Sorrento Valley Site', or collectively as the GA site. Figures B-1 through B-5 depict the specific location of GA and the1RF. The TRF occupies GA Building 21 and an outdoor adjacent service yard. The interior of 2 Building 21 has approximately 7,600 ft of floor space consisting of offices, three reactor 2 rooms, operating rooms and auxiliary areas. Building 21 is surrounded by a 43,800 ft fenced service yard. The1RIGA Reactor Facility has housed thme TRIGA reactors, which have been variously used since 1958 to provide controlled neutron and gamma irradiation for diverse laboratory research projects. Current Facility Status The TRIGA Mk1 Reactor, situated in TRF Room 21/102, was placed in " Possession-Only- - License"(POL) status, under Amendment No. 35 to the USNRC License No. 38, dated October 29,- 1997 (Ref. 5.14), and is presently inoperable. All TRIGA Reactor fuel elements have been removed from the TRIGA Mkl Reactor pool, and transferred / relocated to the TRIGA MkF Fuel Storage Canal in Room 21/107. Moreover, a number of additional components and hardware items, previously installed as part of the TRIGA Mkl Reactor Control and Instrumentation systems, have been dismantled, surveyed, and removed from the TRF for recycle use; this partial

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PC 000482/2 dismantlement and disassembly of the TRIGA Mk1 systems was performed by implementing instmetions set forth in a plan, which was prepared, reviewed, and approved in accordance with the administrative provisions of 10CFR50.59. The TRIGA MkF Reactor (situated in Room 21/107) was previously placed in " Possession-Only-License" (POL) status under USNRC License No. R-67 (Ref.), as amended on March 22,1995, and is also currently inoperable. All reactor fuel elements have been removed from the TRIGA MkF reactor core / shroud and placed in the TRIGA MkF Fuel Storage Canal. The non-fuel components of the TRIGA MkF reactor, including the core support structure, bridge shroud, beam tubes, and associated hardware, remain in the reactor pool.The Fuel Storage Canal portion of the TRIGA MkF reactor pool currently houses all of the Spent Nuclear Fuel (SNF) elements previously removed from the TRIGA MkI, MkF and MkIII Reactors. All required protection barriers and security systems, including those necessary for High Enriched Uranium (HEU) (i.e., electrical service, domestic water supply) storage, are maintained in accordance with GA's physical protection plan. AllTRF building utility services required for facility operation and maintenance under POL conditions are active. TRF building air ventilation and HEPA-filtered building exhaust systems, air supply compressors, and license-required radiological monitoring instrumentation systems are in normal continuous operation. 1 All manually-actuated and automated fire alarm / suppression systems in the TRF are w operational. All installed TRF security and radiological alarm systems are active and normal. Independent water demineralization systems serving the TRIGA MkI and TRIGA MkF Reactors remain ftilly operational. A common forced water cooling system serving both the TRIGA Mkl and MkF Reactors remains fully operational. 2.2 Proposed Action and Alternatives The Proposed Action and the Altematives are as follows: Proposed. Action (DECON)-Decontamination and Decommissioning of the TPS followed by the release of the site for unrestricted use by the USNRC. Altemative 1 (SAFSTOR)-In safe storage, the TRF is placed and maintained in a condition that allows it to be safely stored and subsequently decontaminated to a level permitting release of the propeny by the USNRC. Altemative 2 (ENTOMB)-In entombment, radioactive materials are encased m a structurally long-lived material such as concrete. The entombed structure is appropriately maintained and surveillance is continued until the radioactivity decays to a level permitting release of the property by the USNRC. Implementation of the Proposed Action willinvolve performance of the following tasks: B 10

P C-00048202 2.2.I Dismantle, decontaminate or package as low level waste (LLW) the TRIGA Mkl Reactor components, tank and pit. 2.2.2 Decontaminate any remaining contaminated areas except the TRIGA MkF Reactor and Control Rooms. 2.2.3 Reroute required utility services to isolate the TRIGA MkF Reactor and Control Rooms. 2.2.4 Obtain USDOE approval and ship the spent TRIGA fuel from the TRIGA MkF Fuel Storage Canal. DOE is contractually committed to take spent fuel at INEEL but the actual shipping date is uncertain. The Decommissioning Plan has been modified to describe the arrangements and shipment " schedule" both in the Appendix and in Section 2.3.2. The shipping schedule and the time required to complete Phase 2 of the plan, in turn, determines the date for the license termination mquest. 2.2.5 Dismantle, decontaminate or package as LLW, the TRIGA MkF components, tank and pit. 2.2.6 Ship the LLW generated as a result of decommissioning activities. 2.2.7 Perform final radiological survey and submit a request to the USNRC for release of the subject areas for unrestricted use and the termination of the TRIGA Reactor licenses. 2.3 Administrative Controls 2.3.1 To minimize the risks ofinadvertent exposure, contamination and/or radioactive releases, all Decommissioning operations will be implemented in accordance with appropriate technical and administrative controls, including: 2.3.2 Performance of all project work pursuant to approved procedures implementing USNRC and CAL-DHS-approved Decommissioning Plan. GA will continue to be responsible for assuring and demonstrating compliance with USNRC and CAL-DHS licenses, as well as other applicable federal, state or local laws, regulations, licenses and/or permits. 2.3.3 Utilization of containment structures, tents, and bags under negative pressure and/or appropriate contamination barriers to isolate operation areas and prevent inadvertent release of contaminants. 2.3.4 Employment of monitored, high-efficiency particulate air (HEPA) filtration systems for air ventilation in the work areas. 2.3.5 Maintenance of emergency ventilation, power, and supplies, as appropriate. 2.3.6 Application of ALARA principles such as emphasizing radiation protection for workers and the general public, employing personnel and area dosimetry, using personal protective equipment and clothing and conducting work through approved Radiological Work Authorization Permits. The term "ALARA" means as low as reasonably achievable, taking into account the state of technology and the economics ofimprovements in relation to the benefits to public health and safety, and other societal and socioeconomic considerations.

GA Health Physics staff would have the authority to stop any operations which they believe may involve unusual, unnecessary or excessive radiological risk to the worker, the public or the environment..

2.3.7 Maintenance ofindustrial security access control to the work site and facility, to restrict unauthorized individuals from the work area. B 11

PC-000482/2 2.3.8 Integration of GA Quality Assurance and GA Health and Safety requirements into Decommissioning Project documents.

3. DESCRIPTION OF THE AFFECTED ENVIRONMENT 3.1 Man Made Environment 3.1.1 Radioactive Materials The public is continuously exposed to radiation from natural sources; primarily from cosmic radiation; extemal radiation from natural radioactive material in the earth and global fallout; and intemal radiation from natural radioactive materials taken into the body via air, water, and food. The public receives and accepts the risks associated with radiation exposures from medical X-rays, nuclear medicine procedures, and consumer products. On average, a member of the public in the United States receives approximately 300 mrem /yr from natural sources of radiation; approximately 50 mrem /yr from medical procedures; and approximately 10 mrem /yr from consumer products, for a total of 360 mrem /yr (Ref. 5.1).

In San Diego, at elevation near sea level, the background radiation from natural sources is about 240 mrem /yr and the total background radiation is approximately 300 mrem /yr. Residual radioactive contammation resulting from past 'IRIGA Reactor operations is contained within the 'IRF Building which is continuously monitored under an extensive surveillance and maintenance program. Existing monitoring data, historical information, and current surveys indicate that TRF building contamination is comprised of cenain fission product and activation product nuclides. Some 'IRF reactor components are contaminated with radionuclides. This is primarily the result of deposition and adherence of airborne and water-soluble contaminants. The radionuclides listed in Table B-1 potentially exist in the'IRF. Radioactive atoms undergo spontaneous nuclear transformuions and release excess energy in the form ofionizing radiation. Such transformations are referred to as radioactive decay. As a result of the radioactive decay process, one element is transformed into another; the newly formed element, called a decay product, will possess physical and chemical properties different from those of its parent, and may also be radioactive. A radioactive species of a particular element is referred to as a' radionuclide or radioisotope. Radiation emitted by radioactive substances can transfer sufficient localized energy to atoms to remove electrons from the electric field of their nucleus (ionization). In living tissue this 1 energy transfer can destroy cellular constituents and produce electrically charged molecules (i.e., free radicals). Extensive biological damage can lead to adverse health effect (Ref. 5.3). The adverse biological reactions associated with ionizing radiation, and hence with radioactive materials, are skin injury, cancer, genetic mutation and birth defects (Ref. 5.4). B 12 i (

PC-000482/2 N 9 Table B-1: List of Expected Radionuclides Nuchde HoH-LWe Decoy Notes (yr) Mode "C 5730. AP; from n-activate of graphite reflector structure (TRIGA Mkl only) "Mn 0.86 e,y AP; short-lived specie; from n-activation of SS hardware '"Fe 2.73 e AP; from n-activation of SS hardware "Co 5.27 $,y AP; from n-activation of SS hardware; expected to be predominant AP specie present ) "Ni

76000, e,y AP; from n-activation of SS hardware

• "Ni 100.

p-AP; from n-activation of SS hardware "Sr 29.1 $~ FP; probable FP constituent; activity expected to be proportional to that of "'Cs Nb 20000. ,y AP; unlikely AP inventory constituent; possible from n activation of SS hardware 1Nb impurities are present

• • Tc 213000.

$~, y FP, and minor AP inventory constituent; possible from n-activatien af SS hardware,! Mo impurites are present "'Sb 2.76 D,y FP; relatively short-lived specie "*Cs 2.07 ,y FP; minor FP inventory constituent '"Cs 30.17 - $,y FP; expected to be predominant FP specie present "'Ce 0.78 p,y FP; short-lived specie

• Eu 13.48 p, $*, e, y FP, and minor AP inventory constituent; possible from n-activation of concrete, g Eu impurities exist in biological shield structure Symbols / Abbreviations:

- = Beta = Positron e = Electron Capture

• ~ -

y = Gamma-Ray AP = Activation Product FP = Fission Product Radonuclide Half-Life values and Decay Mode information used above are taken from Ref.10.15. The list of expected radionuclides provided above is based on the assumption that operations of the TRIGA Mark I and Mara F Reactora have resulted in the neutron activation of reactor core components and other integral hardware or structural members which are situated adjacent to, or in close proximity to, the reactor core during operations. Specific items which are considered to have been exposed to neutron activation include materials composed of aluminum, steel, stainless steel, graphite, cadmium, lead, concrete and possibly others. Based on earlier studes and experience gained in similar research reactor decommissioning protects, and reactor specific calculations which considered measured values for neutron leakage fluence, integrated operating power histories, reactor core / pool structural configurates, and material casyositica of exposed pool structures, rautron actrvation of materials beyond the concrete liner / biological shield structure (i.e., into surrounding soit volumes) is g expected for either the TRIGA Mark i nor Mark F Reactors. B 13 +

PC 000482/2 Major types of ionizing radiation include alpha particles, beta, and gamma or X-ray radiation. Alpha particles expend their energy in short distances and will not usually penetrate the outer layer of skin. Alpha particles repmsent a significant hazard only when taken into.the body, where their energy is completely absorbed by small volumes of tissues. Beta particles constitute external hazards if the radiation is within a few centimeters of exposed skin surfaces and if the beta energy is greater than 70 kev. Internally, beta panicles deposit much less energy to small volumes of tissue and, consequently, inflict much less damage than alpha' particles. Gamma radiation are of the most concem as external hazards. 3.1.2 Hazardous Materials . Based on pmliminary surveys and inspections of the subject work areas, the specific hazardous materials of concern in terms of potential exposure to project workers, on site GA employees and off-site persons are elemental lead, cadmium and asbestos. 3.1.2.1 Elemental Lead-The predominant hazardous material in the TRF, in terms of mass, is elemental lead (used primarily in various radiation shielding applications). Most lead contained in the facihty consists of solid, non-dispersible bricks, fittings, liners and weights. Lead is a cumulative poison. Increasing amounts can build up in the body - eventually reaching a point where symptoms and disability occur. The effects of exposure to lead dust through inhalation and ingestion may not develop quickly. Symptoms may include decreased physical fitness, fatiguc, sleep disturbance, headache, aching bones and muscles, constipation, abdominal pains and decreased appetite, lead can also cause irritation to the skin and eyes. These effects are reported to be reversible if exposure

ceases. Systemic effects am possible if a long-term exposure occurs and binh defects have been reported.

3.1.2.2 Asbestos-Asbestos is present in TRF construction materials (e.g., floor tiles, roofing material).' Asbestos is not a hazard unless it is " friable," that is in powder or fiber form. Inhalation of the fibers can cause asbestosis and lung cancer. Gastrointestinal cancer can be caused by ingestion. Asbestos found to be present in the TRF will be removed by a licensed asbestos abatement contractor. 3.1.2.3 Cadnuum--Cadmium is present in the TRF in the form of metal foil. Inhalation or ingestion of cadmium dust or fumes can affect the respiratory system, kidneys, arostate and blood. Symptoms are: pulmonary edema, dyspnea, cough, tight chest, su)stemal pain, headache, chills, muscular aches, nausea, diarrhea, anosmia, emphysema. 3.l'.'3 Transportation The main roadways in the vicinity of the GA site are shown on Figure B-2. They include Genesee Avenue beyond the southern boundary, John Jay Hopkins Drive beyond a ponion of the western boundary, North Torrey Pines Road further to the west, and Interstate 5 to the cast. Genesee Avenue is a six-lane primary arterial. North Torrey Pines Road north of i Genesee Avenue is a six-lane primary arterial. North of Science Park Road, North Torrey Pines Road becomes a four-lane primary anerial. John Jay Hopkins Drive is a four-lane collector street which connects Genesee Avenue with North Torrey Pines Road. The GA site is generally accessed from the Interstate 5 freeway, exiting on Genesee Avenue and traveling west, turning north on John Jay Hopkins Drive and east on General Atomics Coun. The site can be entered through two entrances shown on the map (Figure B-2) from General Atomics Coun and from John Hopkins Court. Traffic onto the site is controlled by a guard posted at a guard station and by personnel at an office reception area. B PC-000482/2 Off-hour access is through a keycard gate at the south entrance. The nearest entrance to the GA site is approximately 1,500 ft. (457 m) from the TRF. 3.1.4 Cultural and - Historical Resources - 'No significant archeological or cultural resources have been found in surveys of the GA site. The National Register of Historic Places mentions no historical structures or sites ~ within the boundary of the plant. There is a state park, called Torrey Pines State Park, located one mile to the northwest of the site, which contams a umque species of pine tree. e No historical, archaeological or cultural properties are believed to be under consideration on or near the 'IRF. e 3.1.5 Population and Land Use The site is located within the Torrey Pines Mesa area and is currently zoned SR (Scientific Research). The University Community Plan designates open space and scientific research land uses for the site. Land uses surrounding the GA site include scientific research and development parks to the north and to the east across Interstate 5, undeveloped land asse::iated,vith Torrey Pines State Park, research and development parks and a hospital to the west and the University of California at San Diego (UCSD) to the south. Surrounding land uses are shown graphically on Figure B-2. The present population within the University Census Tract Subregion, in which the main site lies, is primarily of an industrial and university campus makeup, with an estimated daytime total of up to 52,000 people (Ref. 5.5) inc.tuding about 1,200 GA employees. The University Subregion contains six Census Tracts. The immediate vicinity of the Flintkote Avenue facilities is zoned for industrial activity. Estimates of future growth indicate that the University subregion could have a daytime total of 57,000 people by year 2000, based upon future industrial growth in the Sorrento Valley area and an increased number of students on the univerrity campus. Because of terrain, zoning, and current land use, most future residential develcpment will occur beyond a two mile radius from the site. - Nearby sensitive human populations include: GA non-radiological workers; Agouron Pharmaceuticals, located 0.25 miles (0.4 km) to the west; Children at a day care center, located on John Jay Hopkins Drive, approximately 0.45 miles (0.7 k.m) to the west; Scripps Green Hospital, located 0.5 miles (0.8 km) to the west; UCSD dormitories located about 0.9 miles (1.5 km) to the south; and

• - Aresidence along Torrey Pines Road across from the UCSD campus (about 1.2 miles or 2 km to the southwest)..

3.1.6 Noise Within GA site boundaries, the ambient noise environment is generated by vehicular traffic, jet aircraft, general aviation aircraft and building, heating, ventilating and air conditioning equipment. I B 15 t

1 i PC 000482/2 3.1.7 Aesthetics The 'IRF is located against a backdrop of coastal bluffs interspersed with steeply sloping canyons. It is in the interior of the GA site and is not visible to adjacent neighbors. However, the 'IRF is visible at a 0.5 mile (0.8 km) distance from Interstate 5 to the east and Scripps Green Hospital to the west. The TRF will be visible from future science-related devehpment to the northeast. 3.2 Natural Environment .3.2.1 Topography, Geology and Seismicity 3.2.1.1 Topography Site to mgraphy is typical of coastal San Diego County, with bluffs and mesas interspersed l with c.iffs and ravines. The mesa runs in a northerly direction paralleling the coast and rising to a height of 400 ft. (122 m) above sea level between the site and the ocean. The topography of the site is characterized by steeply sloping canyons and relatively level mesa areas. The main GA site is on Torrey Pines Mesa about one mile east of the ocean at an elevation of 340 ft. (105 m) above sea level. 3.2.1.2 Geology The TRF has been built on materials that have been mapped as artificial fill (Ref. 5.6). Areas immediately adjacent to the artificial fill are mapped as Ardath Shale, a member of the La Jolla Group of Eocene Deposits, that is predominantly weakly fissile, olive-gray shale. Across section on the Del Mar quadrangle shows subsurface formations approximately 750 ft. (228 m) northeast of the 'IRF. Based on this cross section, the Ardath shale deposit in the 'IRF area is approximately 300 ft. (91 m) thick, is underlain by approximately 500 ft. (150 m) of Torrey Sandstone over approximately 250 ft. (76 m) cf Del Mar Formation. 3.2.1.3 Soils Soils present at the 'IRF have been mapped as Huerhuero loam,5 to 9 percent slopes and eroded (Ref. 5.7). The Huerhuero series soils have developed in sandy marine sediments and consist of moderately well drained loams that have a clay subsoil. A representative Huerhuero profile has a surface layer that is brown and pale-brown, strongly acid and medium acid loam about 12 inches (0.3 m) thick, an upper subsurface layer that extends to a depth of about 41 inches (1.0 m) and is brown, moderately alkaline clay and an underlying brown, mildly alkaline clay loam and sr.ndy loam layer that extends to a depth of more than 60 inches (1.5 m). Small areas of Las Flores and Olivenhain soils and alluvium derived from metabasic and metasedimentary rocks are included in the area. Soils immediately downslope of the TRF have been mapped as Altamont Clay,15 to 30 percent slopes (AtF) Huerhuero loam,5 to 9 percent slopes and eroded. The Altamont series consists of well-drained clays that formed in material weathered from calcareous shale. A representative Altamont profile has a surface layer that is dark-brown and light olive-brown, moderately alkaline heavy clay loam about 8 inches (0.2 m) thick that lies over soft calcareous shale. Small areas of Linne clay loam and areas where the soil is only 10 inches (0.2 m) over shale are included in the survey area (Ref. 5.7). There may be localized areas of soil contamination. The extent of contamination will be defined through the site characterization process. B-16 l [.

PC-000482/2 3.2.1.4 Seismicity San Diego County has been considered one of the more moderate seismic risk regions in Southem Califomia. The historical pattem of seismic activity has genendly been charactenzed by a broad scattering of sinall magni:ude earthquakes, whereas the surrounding regions are characterized by a high rate of seismicity with rnany moderate-to-large-magnitude earthquakes. A recent study (Ref. 5.8) estimated the probabilities of large earthquakes occurring in Califomia on the. major strands of the San Andreas fault system. In addition to the principal traces of the San Andreas fault, earthquakes occuning on the other major faults of the system (San Jacinto, Imperial, etc.) were also considered. The study estimated that the probability of a magnitude 7 or greater earthquake occurring in the next 30 years in Southern Califomia (along the Southern San Andreas, Imperial, or San Jacinto faults) is 0.5 or greater. However, a quake of magnitude close to 7 on these fault lines is not expected to significantly impact the GA site because ofintervening distance. Current information (Ref. 5.9) however, indicates the Rose Canyon, Coronado Bank, San Diego Trough, La Nacion, and Elsinore fault zones are capable of generating strmg ground motion in the San Diego ama. Possible Richter magnitudes for earthquakes on these faults can be as high as 7.0, 7.5, 7.5, 6.3 and 7.5, respectively. Passing approximately 3 miles (5 km) west of the GA site, the Rose Canyon fault is the nearest active fault. Recent excavations (Ref. 5.10) showed definite evidence of Halocene (within the last 10,000 years) activity. It is clear that San Diego has experienced major earthquakes in the recent geologic past. The presence of three small, local faults was confirmed by the Woodward-Clyde Consultants field reconnaissance of the site (Ref. 5.11). An unnamed fault in the northem portion of the site trends east to west through proposed lots 25, 26, 31, and 32. The Salk fault is mapped in the southem portion of the site and also trends cast to west. A northerly trending fault is located in the southeastem area and crosses the Genesee Avenue canyon. All of these facits are mapped as being overlain by early Pleistocene formations which have not been displaced. Therefore, the faults on-site are not considered active. 3.2.2 Climate and Air Quality 3.2.2.1 Climatology The Torrey Pines Mesa and Sorrento Valley, as with most of San Diego County's coastal areas, has a semi-arid Mediterranean climate characterized by hot, dry summers and mild, wet winters. The mean annual temperature in the project vicinity is 61 F (33.8 C), with summer high temperatures in the low-90s (50 C) and winter lows in the mid-30s (16 C) (Ref. 5.12). The dominating meteorologic feature affecting the region is the Pacific High Pressure Zone, a semipermanent high pressure cell located over the Pacific Ocean. This high pressure cell maintains clear skies for much of the year, drives the prevailing westerly to northwesterly winds, and creates two types of temperature inversions (reversals of the normal decrease of . temperature with height) that act to degrade local air quality. When a buoyant parcel of polluted air rises, it cools by expansion. If the air around the parcel is warm, as in an mversion, the parcel sinks back down toward its source and is effectively prohibited from dispersing. In sumraer, a marine / subsidence inversion is formed when the warm, sinking air mass in the Pacific High Pressure Zone is undercut by a shallow layer of cool marine air flowing onshore.This inversion forms over the entire coastal plain and allows for mixing I B 17

PC-000482/2 below the invenion base at 1.100 - 1,500 ft. (457 m), but not any higher. During the winter offshore flow regime, cold air pools in low areas and air in contact with the cold ground cools while the air aloft remains warm. A nightly shallow inversion layer [at about 800 ft. (244 m)j forms between the two air masses which can trap pollutants. In the summer, when the high pressure system is at its most nonherly extent, eastward-traveling storm and pressure centers are blocked, msulting in little rain due to frontal activity.The migration of this system to its most southerly extent in the winter allows the transient storm and pressure centers to pass through the area, resulting in winter rains in southern California. The predominant pattem is sometimes interrupted by so-called Santa Ana conditions, when high pressure over the Nevada-Utah nrea overcomes the prevailing westerlies, sending strong, steady, hot, dry winds east over the mountains and out to sea. Strong Santa Anas tend to blow pollutants out over the ocean, producing clear days. However, at the onset or breakdown of these conditions or if the Santa Ana is weak, air quality may be adversely affected. In these cases, emissions from the South Coast Air Basin to the north am blown out over the ocean, and low pressure over Baja California draws this pollutant laden air ^ mass southward. As the high pressure weakens, prevailing nonhwesterlies reassert themselves and send this cloud of contamination ashore in the San Diego Air Basin. There is a potential for such an occurrence about 45 days of the year, but the region is adversely impacted on only about five of them. When this impact does occur, the combination of transported and locally produced contaminants produces the worst air quality measurements recorded in the San Diego basin. 3.2.2.2 Local Winds and Dispersion Data 4 ' The prevailing day time wind direction is westerly, although easterly winds are almost as common during the winter months. During the day, the westerly winds developing from ~ he Pacific high-pressure system are reinforced by the sea-land breeze caused by the Pacific t Ocean resulting m stronger average wind velocities (6 to 9 mph (10 to 15 km/h)] than from - the easterly land breeze [1 to 7 mph (1.6 to 11.6 km/h)]. The land breezes are most common during stable conditions and dominate the flow toward the ocean during the night .and early moming hours. The airflow in either direction is channeled effectively by topographical features of the area. Strong winds are infrequent, the strongest recorded was 51 mph (82 km/h) from the southeast in 1944. Data from an on-site meteorological system were used to provide atmospheric stability and wind frequency results. The on-site annual wind data are consistent with the wind rose data from the Miramar Naval Air Station. 1 3.2.2.3 Precipitation The average annual rainfall for the city of San Diego is 10.4 in. (26.4 cm), but relatively j ~ large variations in monthly and seasonal totals occur. The average monthly precipitation from 1940 through 1970 ranges from 2.15 in. (5.5 cm) in February to 0.01 in. (0.03 cm) in July. Approximately 75% of the annual precipitation occurs from November through March. The maximum annual precipitation during the last 60 years was 24.9 in. (63.3 cm) occurring in 1941. ' 3.2.2.4 Air Quality Under state regulations, the study area is within the San Diego Air Basin (SDAB). The concentration of pollutants within the SDAB is measured at eight stations maintained by the B 18

w I PC-000482/2 County of San.Diego Air Pollution Control District (APCD) and the California Air Resources Board (ARB). Air quality at a panicular location is a function of the type and amount of pollutants being emitted into the air locally and throughout the basin and the dispersal rates of pollutants within the region. The air quality monitoring station nearest the project area is located in a school ground at Ninth and Stratford Court in the City of Del Mar. This is four miles (6.4 km) nonh of the site. Air quality measurements are expressed as the number of days on which air pollutant levels exceed state and federal clean air standards. Under federal regulations, the GA facility is located in the southwestem portion of the San Diego Interstate Air Quality Control Region. The Environmental Protection Agency (EPA) has designated this region as an " attainment area" for sulfur dioxide and nitric oxides, indicating that the concentrations of these pollutants are below the federal air quality standards. The region was classified as a "nonattainment area" with respect to carbon monoxide, ozone, and small suspended paniculates (PMw) some years ago, but in recent years only ozone federal standards have been exceeded. In 1993 at the APCD monitoring station in Del Mar, ozone exceeded the state standard on 19 days and the federal standard on three days. This is characteristic of the entire SDAB. In 1992 and 1993, the maximum 24-hour measured level of particulates less than 10 microns in size in the SDAB was found to exceed the state standard on several days. Annual average measured PM levels were marginal with state standards. However, m neither the 24-hour nor the annual federal standard for PM was exceeded. m 3.2.3 Hydrology 3.2.3.1 Groundwater . The TRF is located within the Southwestern portion of the Soledad Basin. The Soledad Basin makes up the nonhwestern part of the Los Penasquitos hydrographic subunit and has not been developed for water supply purposes. No groundwater wells are present at or immediately adjacent to the TRF. Ground water beneath the TRF is approximately 300 feet below ground surface. Test borings on the GA site ranging from approximately 6 to 30 ft. (1.8 - 9.1 m) did not encounter groundwater. There is currently no reason to suspect that any groundwater contamination exists under the 'IRF, Funher studies may be conducted if warranted during D&D activities. 3.2.3.2 Surface Water Based on ground surface elevations and surface drainage patterns, surface run-off from the TRF Controlled Yard Area currently flows primarily northerly, across paved and unpaved surfaces in the service yard. The TRF is located within the Los Penasguitos Creek drainage basin. Drainage runs ' through the Scledad Valley into Los Penasquitos Creek, which flows to the nonhwest and empties into the Pacific Ocean. Detention basins and silt collection structures have been constructed for the development of the Torrey Pines Science Park that surrounds and includes the GA site to ensure that adverse downstream impacts will not occur from - stormwater run-off. Surface ' water downstream from the site cannot be used domestically because of its intermittent flow and dirty' condition during periods following rainstorms or heavy run-offs. No freshwater recreation areas exist within the local vicinity. Agriculture is not B 19 L 4 + n 3

- s PC-000482/2 pmvalent because soils am not well suited for agriculture, precipitation is limited, and groundwater quality (primarily in Penasquitos Valley)is considered marginal or inferior for irrigatien. Water use in the vicinity of the site is limited by the ephemeral nature of many streams and the high suspended solids content of flow during the winter. Floods do not repmsent a danger to the site as it is situated approximately 340 ft. (103 m) above the valley floor on a mesa. Also, drainage downstream from the site to the Pacific Ocean is unrestricted. The TRF is not located within a 100-Year Flood Zone. 4 Wastewater collection services are supplied to the GA site by the San Diego Department of Public Utilities. Wastewater from the site is discharged through the City's sewer system to - the Point Loma trearsner.t plant. Any wastewater released to the city treatment system must j s l meet the requirements of the San Diego Industrial Waste Discharge Permit. 3.2.4 Biology 3.2.4. I Vegetation The GA site is professionally landscaped. The open space surrounding the TRF and the GA site is a combination of disturbed / developed lands, several eucalyptus groves and three distinct types of native or naturalized plant communities; coastal mixed chaparral, coastal sage scrub, and southern California grassland. No federally-listed endangered plant species are known to exist on or near the GA site (Ref. 5.13). The most significant natural areas in the vicinity of the site are Torrey Pines Park, Torrey Pines. State Reserve, and Los Penasquitos Lagoon and associated marsh. These areas are located west and northwest of the site along the coast (Figure B-2). In addition to providing relatively undisturbed refuge-like habitats, the park and reserve contain a rare species of pine tree, the torrey pine (Pinus torreyana). This species is endemic to California, known to occur only in San Diego County and on Santa Rosa Island. 3.2.4.2 Regional Wetlands Stormwater run-off from the TRF and the GA site flows into the Los Penasquitos Lagoon. The Los Penasquitos Lagoon and associated marsh are designated by the California Department of Fish and Game as a wetland area. The saltwater marsh and lagoon _ support a diverse fish fauna and a mussel fauna of about 20 species. The Pacific little-neck cochral and common little-neck clam are the most common mussel species. A total of approximately 30 species of salt-marsh plants occurs in the Los Penasquitos Lagoon. The predominant vegetation in the marsh and lagoon is pickleweed (Solicormia). Solicomua subtenninalis occurs in the drier areas; Solicarmia virginica, in the lower-lying areas. Pickleweed filters out most of the suspended material brought in by upstream drainage. 3.2.4.3 -Wildlife A 1994 survey of the area adjacent to the TRF conducted by Natural Resource Consultants identified several mammal, birds and reptile species, with the majority of these occurring in the brushland habitats (coastal sage scrub and coastal mixed chaparral). Raptors utilize the grassland and to a lesser extent the brushland habitats on the site for foraging. Raptors are protected in Califomia and are considered sensitive due to the general trend of declining populations in many species and their importance in the ecological structure of biological communities. Two species observed in the brushland habitats around the site, black-tailed gnatcatcher (Polioptila melanurla californica) and the orange throated whip tail (Cnemidophorus hyperythrus heldingi) appear to be experiencing declines in their B 20 s

PC-000482/2 populations in coastal San Diego County. The black-tailed gnatcatcher is a species of special concern and is listed by the Califomia Depanment of Fish and Wildlife Service as endangered. The Torrey Pines Park, Torrey Pines State Reserve, and Los Penasquitos Lagoon and associated marsh area provides habitat for several species of shorebirds and waterfowl, as well as two federally listed endangered species of birds, the light-footed clapper rail (Rallus longirostris levipes) and the Califamia least tern (Sterma albifrons browni). These species have been declining because of human disturbance and water pollution that destroyed nesting and feeding habitats. The Belding's Savannah sparrow (Passerculus sandwichensis beldingi), listed by the state as endangered, is also associated with the pickleweed habitat of the lagoon. It, too, has been declining because of a. human developments affecting its habitat. None of these unique wildlife species have ever been observed on the site. During the biological survey conducted of the adjacent area (Natural Resource Consultants, May 10,1994), a total of three bird species were observed on the site. These inciude the house finch (Carpodacus mexicanus), common raven (Corvus corax), and mourning dove (Zenaida macroura). A single fence lizard (Sceloporus occidentalis) was also observed.There are no wildlife species recognized as rare or endangered by any resource protection agencies known to habitat within the TRF boundary. 3.2.5 Socioeconomics and Environmental Justice The socioeconomic environment of the GA facility consists of a well-established, diverse, middle-income community consisting of research m, stitutions, a medium-sized university, light industry, tourism, and residences. The setting is attractive, with the coastline, Torrey Pines Park, and Village of La Jolla nearby. The road system is adequate with both interstate highways and secondary roads. GA operations do not constitute a large percentage of the area's economy.

4. POTENTIAL ENVIRONMENTAL CONSEQUENCES OF PROPOSED ACTION AND ALTERNATIVES This section discusses the potential direct c.nd cumulative effects of the proposed action on human health and the environment.

4.1 Human Health Effects Types of exposures that could lead to human health effects considered in this repon are worker and off site exposures to hazardous chemicals or radioactive materials during routine activities or potential accidents on site, or during a transportation accident off-site (involving hazardous or radioactive waste removal). This section identifies and discusses potential hazards that may affect workers on-site or people off-site during normal or routine 1RF Decommissioning activities. Impacts of the hazards relative to human health and safety are summarized in Section 4.1.2. 4.1.1 Hazard Identification During the initial site characterization and the final site survey, site workers would be taking readings and measurements of any contamination using direct reading instmments and sampling techniques. Hazards during this work are mostly those involving external B-21

!? 1 PC-000482/2 radiation, inhalation of hazardous or radioactive materials, or dermal contact with these materials. For the Decommissioning activities, the key hazards would involve external radiation, inhalation of hazardous or radioactive materials, or dermal contact with those materials during decontamination, dismantling, packaging and disposal of reactor and ancillary equipment, the TRF structure, and contaminated soil (if necessary). Generally, the Decommissioning steps described in Section 2 of the Decommissioning Plan could involve the hazards as itemized below: 4.1.1,I Hazards-Hazards include: . External radiation for workers working around radioactively contaminated equipment and materials. . Dermal contact with both radioactive and hazardous materials. Inhalation of any hazardous or radioactive materials. Possible confined spaces in tents, bags or small rooms with associated oxygen content and asphyxiant concerns. Heavy equipment movement dangers. Ngic: No flammables or explosive materials are expected to be present. 4.1.1.2 Controls-For. workers, project procedures and conformance with GA licenses and - regulatory requirements including but not limited to: Radiological Work Permits, Work Authorizations, and Hazardous Work Authorization procedures, as required; 29 CFR 1910.120 requirements for PPE, air monitoring, work zone controls, medical e surveillance and bio-assay program, personnel training, emergency response, and - health and safety plan; personal dosimetry per 10 CFR 20; e confined space entry procedures per 29 CFR 1910.146; e HEPA filter removal of contaminants; dust filter removal of contaminants. e-4.1.2 Potential Exposures The collective dose equivalent estimate to workers for the entire Decommissioning project is ~20 person-rem. The decommissioning tasks will take approximately 2 years. Total person hours involving radiological exposure is estimated to be 6,000 hours. ( B 22 i

PC-000482/2 The potential exposures to the public as a result of decommissioning activities and radioactive waste shipments is estimated to be negligible. This is consistent with the { estimate given for the " reference research reactor" in the " Final Generic Environmental Impact Statement on d: commissioning of nuclear facilities"(NUREG-0586) (Ref. 5.16). The estimated dose to the public during decommissioning (DECOM) and truck transport transponation of radioactive waste from the " reference research reactor" as given in the Final Generic Impact Statement is " negligible (less than 0.1 man-rem). The anticipated potential exposures to the public after license termination is also negligible. The site will have been released to unrestricted use, wiA all areas having been remediated to levels not to exceed 5 R/hr above background and meeting the surface contamination criteria given in U.S. NRC Regulatory Guide 1.86. 4.1.3 Transportation The primary project impacts to the environment due to transportation could occur when shipments of waste travel from the site. Transportation would be conducted in accordance with applicable USDOr, USEPA, and USNRC regulations. During such transport, hazardous and radioactive materials would be effectively packaged to prevent signif: cant radiation extemal to the truck. Thus, the primary impacts are accident risk and emissions / noise from the trucks themselves. The truck route into or from the GA propeny coming from or going to San Diego is along Genesee Avenue west from the Interstate 5 freeway, then along John J. Hopkins Drive to General Atomics Coun to the gated GA entrance. This enthe route from Interstate 5 to the GA gate covers a distance of about 1-mile. Tmck shipments of concern consist of hazardous waste and radioactive waste leaving the site. During TRF Decommissioning activities, short-term transportation effects would include employee trips, which occur under existing conditions, a small number of contractor trips, and less than 12 truck trips for hazardous and radiological waste transfer. Traffic, circulation and parking effects are expected to be minor due to the small increase in trips and the short duration of this action and would not significantly impact the surrounding roadways. 4.2 Waste Disposal - 4.2.1 Hazardous Waste Small amounts of solid and liquid hazardous waste from TRF Decommissioning activities +. would be accumulated in satellite accumulation areas. After accumulation for up to 90 days, the waste would be transferred by a licensed contractor to authorized off-site commemial treatment and disposal facilities or recyclers. The Hazardous Only waste will be included as pan of the regular " milk run" shipments made by GA's subcontractor. 4.2.2 Low Level Radioactive and Mixed Waste Low-level radioactive waste, including any contaminated soil, would be packaged in accordance with the Nevada Test Site Waste Acceptance Criteria. Liquid waste is filtered or solidified and solid waste is compacted, whenever possible, in accordance with the appropriate regulations. The waste would be shipped to USDOE's Nevada's Test Site for disposal. Low-level radioactive waste generated during the TRF Decommissioning are expected to consist of two (2) shipments (approximately 150 ft') of irradiated hardware requiring a B-23 m.

PC 000482/2 Type B container such as the 10-142 cask, and four (4) truck shipments (approximately 3850 ft') of" strong tight" containers. Mixed Waste generated during the 1RF Decommissioning are expected to consist of primarily activated /contammated lead and cadmium. Estimated volumes of activated / con-tammated lead and cadmium are 45 cubic feet lead and 5 cubic feet cadmium. General Atomics expects to make one (1) shipment to Envirocare to disposition these wastes. 4.2.3 Non Hazardous Solid Waste 1RF Decommissioning activities will generate uncontaminated construction debris which would be sent to a local sanitary landfill. I 4.2.4 Spent TRIGA Fuel Elements GA assumes that all of the spent 1RIGA Reactor fuel elements can be shipped in 5 off-site transport trips, utilizing the General Electric Co, Model No. 2000 shipping cask or appropriate equivalent package. 4.3 Noise During 1RF Decommissioning activities, noise will be generated by equipment such as jackhammers, scabblers and concrete saws. Backhoes and other heavy equipment could also be used for partial dismantling activities. On-site workers will be outfitted with ear protection devices. The closest off-site business is Agouron Pharmaceuticals,Inc. which is approximately 0.25 miles away. Noise from 1RF Decommissioning activities would not impact employees or off-site businesses. 4.4 Seismicity 1RF Decommissioning activities would involve the removal of surface contamination or possibly structural dismantlement activities. Any dismantlement plans and specifications would be reviewed by a structural engineer to assure that activities would not render the

1RF building structurally unsafe, should an earthquake occur. Decommissioning activities -

would not increase the risk to 1RF workers during a seismic event. 4.5 Air Quality Several Decommissioning related activities could nnnimally impact air quality due to both mobile arid stationary source emissions. A small amount of mobile source emissions such as carbon monoxide and nitrogen oxides could be released from contractors' trucks and cars. However, tne San Diego Air Pollution District does not set thresholds for determination of significant emissions from mobile source emissions. Due to the temporary nature of the truck trips and the small number, mobile source emissions would be low. Smtionary source 1 emissions could be released during decontandnation, i;ullding distnantlement aci solid remediation but are expected to be negligible. Any releases from decontamination would occur within the 1RF. Hazardous materials would be located inside the building. Standard asbestos abatement procedures, under the oversight of the San Diego County Air Pollution Control District, will be used to remove any asbestos. Site workers would be protected during decontamination and soil excavation activities through air monitoring and the use of PPE and respirators when required, i ) B 24 o

P C-0004 83/2 The proposed action is only a temporary potential source of air emissions. Negligible ariounts of mobile source, stationary source, and soil remediation emissions would be produced and would not affect regional attainment standards. 4.6 Regulatory Issues Table B-discusses the applicability of various state and federal regulations for the proposed action. 4.7 Areas Not Affected The proposed actim) would not affect the following areas: Population and Land Use-The proposed action would increase the compatibility of GA with other science research activities on-going within the GA site. Future use of the Building 21 site could result in the addition of employees or tenants at GA. Cultural Resources-There are no cultural resourccs on the GA site. Aesthetics-The proposed action would only be visible from Interstate 5, located approximately 0.5 mile (0.8 km) to the east and Scripps Green llospital, located 0.5 nnie (0.8 km) to the west. The 'IRF is not currently visible to adjacent neighbors. Temporaq Decommissioning activities will be compatible with continuing industrial development of the surrounding areas. The remaining site would be used for other industrialrelated purposes. Biology-There are no known sensitive or endangered species on the TRF site. Hydrology-The site elevation is approximately 340 feet above mean sea level. It is not in a wetland, nor is it in a 100-year flood plain. 4.8 Cumulative Effects No significant cumulative effects are expected from the proposed action, as discussed below: S Human Health-The tot lose estimated for decommissioning workers is 20 person-rem for the entire project evolution. This estimate will be achieved by utilizing ALARA practices including planning of work activities, utilization of engineered safeguards, and minimization of exposure times. The decommissioning will be conducted under a Work Authorization system using written procedures to ensure proper planning, training, and evaluation of potential risks. It should be noted that a total dose of 20 person-rem is consistent with 18.6 person-rem given in Table 7.3-3 " Summary of radiation safety analyses for decommissioning the reference research reactor" of the " Final Generic Environmerdal Impact Statement on decommissioning of nuclear facilities" (NUREG-0586) (Ref. 5.16). The dose to members of the public as a result of decommissioning activities described in GA's TRIGA facility decommissioning plan are expected to be negligible. The dominant internal exposure pathway for members of the public is inhalation. The dose to the public is estimated to be negligible because access to the area surrounding the facility is restricted and because decontamination activities with potential for airborne activity will be conducted utilizing engineered safeguards such as HEPA equipped enclosures. Further, continued operation of the facility HEPA system provides additional protection for all decontarnination activities conducted within the building. Thus, potential airborne i B 25 l 'a

m PC 000482/2 Table B 2-Applicability of Environmental Statutes and Regulations 5tatute/ Regulation Evaluation Applicability Nabonal Erwirorimental Policy Act (NEPA) The evaluabon for potenbal environmental irrgIxts are contaned in this Yes document Enoangered Species Act No cnbcai hatNtats exist in the affected area, and no adverse impacts to No threatened or endangered species are expected to result from the proposed achon. FWWaWWetlands Regulabons The proposed achon is not located within a weGand or in a ik.uipMsq. No Fish and Wik5ife Goordinabon Act The proposed achon does not modify or ampact fish and wildlife in any way or ho modify any bodes of water more than 10 acree in surtav area. Farmland Protecton Policy Act The proposed acDon does not affect pnme or unique lamMrls. No National Historc Preservation Act There are no histoncal sites or areas in the k.wbun of tne pM cebon No Amencan indian Rehgious Freedom Act The proposed acbon does not interfere with the nght of Nabve Eencans to No exercise their tradibonal freedom. Wild and Scenic Rivers Act The proposed acDon dobs not involve waterways dessgnated as wild and No scene nyers. Resource and Conservabon Recovery Act The proposed aCDon may include the generation, packaging and im mportabon Yes (RCRA) of rnixed waste. Comprehensive Environmental Response, Any required release reporbng would be performed in compliarce with Yes Compensabon and Liability Act (CERCLA) CERCLA requirements. Federal ineecticide. Fungecide and Rodenbcide The proposed achon is not involved in the distnbubon, use or disposas of any No Act (FIFRAt insecheides fungcides or rodenticides. Toxic substances control Act (T5GA) Asbesion may be encountered dunng D&D operabons wruch would be Yes property packaged and disposed of in acrordance with TSCA. Clean Air Act(GAA) Asbestos rney be encountered during the propect which will be contained in No enclosed spaces, property pacAaged and disposed of. Glean Water and 5afe Dnnking Water Act The proposed acDon is not expected to affect surface water boches or water No supplies. Air emissions would be below warning levels. Noise Gontrol Act Noise levels that could adversely affect workers and staff will be mrbgated by No provickng earprotecton for workers and relocabon of staff to areas away from the activmes. T ne public is not expected to be impacted from the noise Hazardous Matenals Transportation Act The proposed acDon will requne shipment of radcachve matenals and nuxed Ye6 (HMTA) wastes. All waste will be packaged and shipped in appropriate containers and disposedof atbeensedfacilibes f Nabonal Errussions Stanoards for Hazardous The EPA has stated that NE5 HAPS to NRG bcensed facihties. Yes Air Pollutants (NESHAPS) Compliance with errussson standard be demonstrated. Atomic Energy Act Laconse required. Gomphance with environmental and worker protection Ye6 standard. Califorrua Environmental Quality Act (GEGA) Proposed acbon does not tngger discrobonary review by a state agency. No Galiforrua Health and Safety Gode. Div. 20. Proposed acbon rnust comply with worker safety regulations. Yes Chapter 7.6. Arbetes 13.14 Galifornia Integrated Waste Management Act Transportation of low-level radioactive waste would r6 quire Yes notrficatoryconsultaban and manifest. Gahfomia Gode of Regulabons Title 17. Div.1, License required. Comphance with environmental, worker, and pubhc Yes Chapter 5. Subchapter 4. Radiabon protecbon standard radioactive will be negligible; and, therefore, the potential internal dose to the public is also negligible. The estimate of negligible dose to members of the public can also be obtained from the estimate given for the reference research reactor in the " Final Generic Environmental Impact Statement on decommissioning nuclear facilities" (NUREG-0586) (Ref. 5.16). In Section 7.3.1 of NUREG-0586, the dose to the public as a result of decommissioning operations at the reference research reactor - including truck transportation of radioactive waste - is " estimated to be negligible (less than 0.1 person-rem)." This estimate of less than 0.1 person-rem includes both internal (from inhalation and ingestion) and external exposure '3 doses. Waste Generation-The proposed action could generate approximately 4,000 cubic feet of low-level radioactive waste from 'IRF Decommissioning activities. The Nevada Test Site is designated for the disposal of this waste and has sufficient capacity to receive the waste. Cultural Resources-No cultural resources would be impacted by the proposed action. Pooulation and Land Use-Only temporary employment for a few contractors would be provided by the proposed action. No increase in population would occur. Land use would not change. B 26

PC 000482/2 Noise-TRF Decommissioning activities would occur in an industrial area and would largely occur within GA Building 21. The proposed action would not contribute significantly to off-site background noise levels due to the relative isolation of the work site. Aesthetics-TRF Decommissioning activities would not be visible to most adjacent site neighbors, with the exception of the areas ofInterstate 5 and Scripps Green Hospital, both located approximately 0.5 miles (0.8 km) away. Following releue to unrestricted use, the TRF site would be used in a manner consistent with the existing GA site land use practices. Imflig-The temporarv contractor and waste transport trips would contribute an insignificant amount to the average number of daily trips designed for Genesee. Avenue and g John Jay Hopkins Drive. Geology. Soils. Seismicity and Hydrolocy-All TRF Decommissioning activities would be localized; stormwater runoff from exposed areas considered to be radiologically contaminated would be contained and tested. Regional Air Ouality-The San Diego Air Basin is a non-attainment area for carbon monoxide, ozone, and small suspended particulates (PM ). The proposed action is m temporary. A small number of vehicle trips would be generated during off-site shipment of waste materials and would contribute only negligible amounts of these polletants to the basin. Hydrology-No changes to any land forms would occur and no radionuclides or hazardous materials would be irleased to storm water run-off, resulting from the proposed action. Biological Resources-No biological resources have been identified on the 'IRF site; moreover, 'IRF Decommissioning activities are not expected to effect off-site biological ~ resources. 4.9 Alternatives to Proposed Action Alternative I to Pronosed Action-Safe Storace (SAFSTOR) This alternative poses essentially the same potential risks and environmental impacts as the proposed project, but potentially for a much greater period of time. This alternative would necessitate continued surveillance and maintenance of the TRF over a substantial time period. During this period, the risk of environmental contamination would continue to exist. Moreover, development of the land around the GA site over the next few years may sipiificantly increase the local employment population density and increase potential for public exposure. This alternative is not environmentally preferable. Alternative 2 to Prooosed Action-Entombment (ENTOMB) This alternative would necessitate continued surveillance and maintenance of the TRF over a substantial time period. During this period, the risk of environmental contamination would continue to exist. Moreover, development of the land around the GA site over the next few years may significantly increase the local employment population density and increase potential for public exposure. This alternative is not environmentally preferable.

5. REFERENCES 5.1 National Council on Radiation Protection and Measurements (NCRP). longine Radiation Exoosure of the Pooulation of the United States. Report No. 93.1987.

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PC-000482/2 L5.2 Walker, F. W., Perrington, J. R., and Feiner, F. Nuclides and Isotopes. General Electric Company.14th Edition.1989. 5.3 -U.S. EPA. " Risk Assessment Guidance for Superfund, Volume l' Human Health Evaluation Manual (Part A)." Office of Emergency and Remedial Response, U.S. EPA, J . Washington D.C.1989. 5.4 U.SJ EPA. " Risk Assessment Methodology Draft Environmental Impact Statement for ~ Proposed NESHAPS for Radionuclides." Vol.1. U.S. Environmental Protection Agency, ~ Office of Radiation Programs. Washington D.C. 5.5' Source Point. "1990 Census Total Population and Housing Units." San Diego Association of Governments. April 1991. 5.6 - Kennedy. " Geology of the San Diego Metropolitan Area, Califomia." Bulletin 200A. 1975. 5.7 USDA Soils Conservation Service. " Soil Survey San Diego Area, California." 1973. 5.8 Algermissen, S. T. et al. "Probabilistic Earthquake Acceleration and Velocity for the United States and Pueno Rico." U. S. Geological Survey Map MF-2120. 1 5.9 Berger, V. And D. L. Schug, "Probabilistic Evaluation of Seismic Hazard in the San Diego-Tijuana Metmpolitan Region," Environmental Perils - San Dieno Region. P. L. Abbott and W. J. Elliott, Editors, San Diego Association of Geologists,1991. 5.10 Lindvall, S. C., T. K.' Rockwell, and C. E. Lindvall. 'The Seismic Hazard of San Diego, Revised: New evidence for magnitudes 6+ Halocene canhquakes on the Rose Canyon fault zone." Proceedings,4th U. S. Conference of Earthquake Engineering May 1990. 5.11 Woodward-Clyde Consultants. " Preliminary Geotechnical Reconnaissance of the Torrey Pines Science Park." January,1988. 5.12 San Diego Air Pollution Control District,1993 Annual Reoort. 5.13 City of San Diego Planning Department, Environmental Quality Division. Environminial Imnact Report: Torrev Pines Science Center Planning Industrial Develoomentc EDQ No. 86-0884. 1986. 5.14' Amendment No. 35 to Facility License No. R-38 (IRIGA Mark I Reactor)-General Atomics (TAC No. M97502), Issued by the USNRC, dated October 29,1997. 5.15 -Amendment No. 43 to Facility License No. R-67 ('IRIGA Mark F Reactor)-General Atomics (TAC No. M90380), Issued by the USNRC, dated March 22,1995. 5.16 U.S.- Nuclear Regulatory Commission,- NUREG-0586, " Final Generic Environmental Impact Statement on decommissioning nuclear facilities," August 1988. B-28 L

- - - - - ~ - - - ' ' ' ' l 8 P O. BOX 65608 SAN DIEGO, CA 92186 5608 (619) 455-3000 ....}}