ML022900591

General Atomics - Request for State to Acknowledge NRCs Sole Jurisdiction Over Gas Triga Reactor Related Release Requests

ML022900591
Person / Time
Site:	07000734
Issue date:	10/09/2002
From:	Asmussen K General Atomics
To:	Adams M NRC/NMSS/FCSS
References
-RFPFR, 696/CAL-3525
Download: ML022900591 (28)

Text

+ GENERAL ATOMICS October 9, 2002 696/CAL-3525 VIA EXPRESS DELIVERY SERVICE Ms. Mary Adams Licensing Section 1/Licensing Branch Division of Fuel Cycle Safety and Safeguards, NMSS U.S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

Docket No.70-734; SNM-696: Request to Release "TRIGA Reactor Facility Electrical Pad" to Unrestricted Use and Delete it from GA's License and Ms. Sudana Kwok (in Duplicate)

State of California Department of Health Services Radiologic Health Branch Mail Stop 178 601 North 7th Street Sacramento, CA 95814-0208

Subject:

Radioactive Materials License No. 0145-37; Request for State to Acknowledge NRC's Sole Jurisdiction Over GA's TRIGA Reactor Related Release Requests

Dear Ms. Adams and Ms. Kwok:

As you are aware, General Atomics (GA) is continuing its efforts to decommission and decontaminate, as appropriate, selected facilities and land areas on its site in support of obtaining their release to unrestricted use. GA recently completed its final radiological surveys of an area referred to as the 'TRIGA Reactor Facility Electrical Pad." The electrical pad is a small fenced-in area (-948 ft2 (-88 M 2)) paved with concrete on which is located electrical transformers, substations and breakers that provide power to GA's Building 21 (the TRIGA Reactors Facility).

Although this electrical pad has no history of radioactive material storage or use (i.e, a "non-impacted" area), GA performed radiological surveys to demonstrate that no radioactive contamination was present. Enclosed is GA's report titled "General Atomics' Final Radiological Survey Report For "TRIGA Reactor Facility Electrical Pad," dated 3550 GENERAL ATOMICS COURT, SAN DIEGO, CA 92121-1122 PO BOX 85608, SAN DIEGO, CA 92186-5608 1858) 455-3000

696/CAL-3525 October 9, 2002 Ms. Adams (NRC) and Ms. Kwok (State)

Page 2 of 2 October2002. This report documents the results of GA's radiological survey measurements which demonstrate that no radioactivity above natural background levels were observed, and therefore, that the area meets the criteria for release to unrestricted use.

The "TRIGA Reactor Facility Electrical Pad" was/is used to support TRIGA reactor operations/decommissioning which were/are authorized by the NRC.

During the GA/NRC/State decommissioning coordination meeting held in May 14,2002, it was agreed that the NRC has sole jurisdiction over all TRIGA reactors related release requests.

Therefore, it is GA's understanding that the NRC is the sole agency responsible for coordinating this release request, including conducting regulatory agency confirmatory surveys, if deemed appropriate; the results of which will be made available to the State.

GA hereby requests the U.S. Nuclear Regulatory Commission (NRC) to release the "TRIGA Reactor Facility Electrical Pad," as described in the enclosed final survey report, to unrestricted use and to delete it from GA's NRC special nuclear materials license.

GA hereby requests the California DOHS Radiologic Health Branch (State) to acknowledge that it does not wish to claim any regulatory jurisdiction over this, or future, TRIGA reactors related release requests.

If you should have any questions regarding this request or the enclosed report, please contact Ms. Laura Q. Gonzales at (858) 455-2758, or me at (858) 455-2823. Your assistance in responding to this request is very much appreciated.

Very truly yours, Keith E. Asmussen, Ph.D., Director Licensing, Safety and Nuclear Compliance

Enclosure:

GA report titled: "General Atomics' Final Radiological Survey Report For TRIGA Reactor Facility Electrical Pad," dated October 2002.

cc:

Dr. D. Blair Spitzberg, Chief, NMSS Branch 3, Region IV Mr. Wayne L. Britz, Fuel Cycle Inspector, NRC Region IV Ms. Kathleen Henner, State of CA, Brea, CA Dr. Mina Goeders, State of CA, Brea, CA

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+ GENERAL ATOMICS GENERAL ATOMICS' FINAL RADIOLOGICAL SURVEY REPORT For TRIGA Reactor Facility Electrical Pad Prepared By: William LaBonte, Joseph Sullivan and Laura Gonzales Survey Technicians: Scott Cowan, Barbara Hunter, Barbara Lyon, and Joseph Sullivan October 2002

Table of Contents INTRODUCTION................................................................

1 SITE DESCRIPTION.............................................................

I H istory of U se.............................................................

1 Classification..............................................................

I CRITERIA FOR RELEASE TO UNRESTRICTED USE.................................

2 As Low As Reasonably Achievable (ALARA)....................................

2 Facilities and Equipment (and Asphalt or Concrete Surfaces)........................

2 Exposure Rate Guideline.....................................................

2 INSTRUMENTATION & BACKGROUND MEASUREMENTS...........................

2 Background Measurements for Instruments/Detectors 2

Exposure Rate Background...................................................

3 FINAL SURVEYS PERFORMED...................................................

3 Objectives and Responsibilities...............................................

3 Survey Plans..............................................................

4 SURVEY SUM M ARY............................................................

4 COMPARISONS OF SITE DECOMMISSIONING PLAN REQUIREMENTS WITH FINAL SURVEYS PERFORMED ON THE TRIGA REACTOR FACILITY ELECTRICAL PAD 5 RESULTS OF THE FINAL SURVEYS...............................................

5 Scanning.................................................................

5 Fixed Measurements (a and P)...............................................

6 Rem ovable Activity.........................................................

6 Fixed Exposure Rate Measurements............................................

6 Exposure Rate Scans........................................................

6 CONFIRMATORY SURVEY.......................................................

7 CONCLU SION..................................................................

7 List of Tables Table 1:

USNRC's Acceptable Surface Contamination Levels.........................

T-1 Table 2:

State of California's Acceptable Surface Contamination Levels.................

T-2 Table 3:

TRIGA Reactor Facility Electrical Pad List of Instruments..................

T-3 Table 4:

TRIGA Reactor Facility Electrical Pad Wipe Survey Results.................

T-4 List of Figures (unpaged)

Figure 1:

Main Site and Sorrento Valley Site.

Figure 2:

TRIGA Reactor Facility Electrical Pad in Relation to Other GA Facilities.

ii

Figure 3:

TRIGAO Reactor Facility Electrical Pad, Alpha and Beta Scan Locations and Results.

Figure 4:

TRIGA Reactor Facility Electrical Pad, Alpha and Beta Fixed Measurement Locations and Results.

Figure 5:

TRIGA Reactor Facility Electrical Pad, Wipe Survey Locations.

Figure 6:

TRIGA Reactor Facility Electrical Pad Fixed and Scan Exposure Rate Measurement Locations and Results.

Appendix Appendix A: Final Survey Plan TRIGA Reactor Facility Electrical Pad iii

I+

GENERAL ATOMICS Final Radiological Survey Report For TRIGA Reactor Facility Electrical Pad Introduction General Atomics (GA) is continuing its efforts directed at decontaminating, as appropriate, and obtaining the release to unrestricted use of selected facilities and land areas at General Atomics.

GA has recently completed the final radiological survey of the TRIGA Reactor Facility Electrical Pad. As expected, no radiological contamination was found on the concrete pad.

This report documents the results of GA's radiological measurements completed on the TRIGA Reactor Facility Electrical Pad. The results of these surveys demonstrate that this electrical pad meets the NRC-and State-approved criteria for release to unrestricted use.

Site Description The TRIGA Reactor Facility Electrical Pad is located on General Atomics' Main Site (see Figure 1). The location of the TRIGA Reactor Facility Electrical Pad in relation to other facilities on GA's Main Site is shown in Figure 2. The total surface area of this electrical pad is approximately 948 ft2 (-88 in2).

The TRIGA Reactor Facility Electrical Pad is a small fenced in area which contains electrical transformers, substations and breakers which provide power to the TRIGA Mark I and TRIGA Mark F Cooling and Auxiliary systems. This electrical pad is located within the TRIGA Reactor Facility site and east of Building 27. The electricity was shut off during the performance of the survey for safety reasons.

History of Use The Electrical Pad contains electrical transformers, substations and breakers which provide power to TRIGA Mark I and TRIGA Mark F Cooling and Auxiliary systems. This pad has no history of radioactive material storage or use.

Classification This electrical pad is classified as a Non-Impacted Area for final survey purposes. The GA Site Decommissioning Plan does not require radiological surveys in Non-Impacted Areas, however, a final survey was performed because it is surrounded by sites in which radioactive material was used and/or stored. The predominate isotopes associated with the facilities adjacent to this electrical pad are: mixed fission and mixed activation products (i.e. beta/gamma emitters).

1

+

GENERAL ATOMICS Final Radiological Survey Report For TRIGA Reactor Facility Electrical Pad Criteria for Release to Unrestricted Use As Low As Reasonably Achievable (ALARA)

During decommissioning efforts, GA always attempts to decontaminate to levels as close to "background" as possible and as far below the approved Soil Release Criteria as reasonably achievable.

Facilities and Equipment (and Asphalt or Concrete Surfaces)

The U.S. NRC's and the State of California's criteria for releasing facilities and equipment to unrestricted use are shown in Tables 1 and 2, respectively. The applicable guidelines for beta/gamma emitters including Cs-137 and Co-60 are as follows:

5,000 dpm/100 cm2, averaged over a 1 m2 area 15,000 dpm/100 cm2, maximum in a 100 cm2 area if the average over 1 m2 is met 1,000 dpm/100 cm2, removable activity Exposure Rate Guideline Exposure rates measured at 1 m above the surface are not to exceed 10 jiR/hr above natural background levels.

Instrumentation and Background Measurements A list of instruments used during the radiological surveys is shown in Table 3. The table includes: (1) a description of the instrument, model number and its serial number, (2) a description of the detector (if applicable) and its serial number, (3) instrument ranges, (4) calibration due dates, (5) typical background readings and (6) calibration efficiencies (if applicable). All of the instruments used were calibrated semiannually and after repair, except for exposure rate meters which were calibrated quarterly.

Background Measurements for Instruments/Detectors Building 13 on GA's main site was used for conducting background measurements with instruments used for the final survey because: (1) there is no history involving the use or storage of radioactive materials in Building 13, and (2) the various surfaces and construction materials found at the TRIGA Reactor Facility Electrical Pad could also be found within and outside of Building 13. Background information, where appropriate, is included in Table 3.

2

+

GENERAL ATOMICS Final Radiological Survey Report For TRIGA Reactor Facility I

Electrical Pad Minimum detectable activities (MDA's) for instruments used for fixed measurements, for each type of surface (see Table 3), were calculated using equation (5-2) from the NUREG/CR-5849 as shown below:

Equation (5-2) 2.71 + 4.65/--Rxt 2

MDA=

(dpm/100cm 2) txEx A 100 Where:

BR =background rate (cpm) t = count time (min)

E = efficiency A = area of the detector (cm2)

Exposure Rate Background Typical exposure rate background for GA's site using a Ludlum Model 19 micro R meter is 12-18 [tR/hr measured at 1 m from the surface of soil. This range of exposure rates can be measured south of Building 15 (an office building on the eastern portion of the GA site).

Measurements taken offsite in 10 different locations (9 offsite and 1 onsite at a non-impacted area near Building 15) over a period of 15 months also averaged - 15 PR/hr (measured at 1 m from the surface). The range of 12-18 [tR/hr is typical at the GA site for the external dose rates measured at 1 meter from the surface. Background measurements @ 1 m above an asphalt surface are generally higher due to the higher concentrations of naturally occurring radioactive material (NORM). This background fluctuates depending upon the asphalt batch used and the date applied. This background, (measured at 1 m from the surface) ranges from 22-30 [LR/hr.

Final Surveys Performed Objectives and Responsibilities The objectives of the final survey plans were: (1) to demonstrate that the average surface contamination levels for each survey unit were below the approved release criteria, (2) to show that the maximum residual activity did not exceed three times the approved release criteria for average surface contamination value in an area up to 100 cm2, and, (3) that the exposure rate 3

+

GENERAL ATOMICS Final Radiological Survey Report For TRIGA Reactor Facility Electrical Pad measurements taken in these areas, measured at 1 meter above the surface, were less than 10

[tR/hr above background.

Survey Plans A Final Survey Plan was developed based on the previous history of the TRIGA Reactor Facility Electrical Pad and the facilities it supported, the history of use for the TRIGA Reactor Facility Electrical Pad, the radionuclides of concern for this area, the potential for contamination, the various types of surfaces encountered and the classification of the various areas. See Appendix A for the Final Survey Plan for the TRIGA Reactor Facility Electrical Pad.

Surveys were taken in accordance with an approved survey plan(s) by qualified Health Physics Technicians having a minimum of three years health physics experience.

Every survey taken was documented on a daily basis to a worksheet/drawing showing the approximate locations surveyed/sampled. The documentation included the results of the measurements (including units), the technician's signature, date, instrument(s) used (including the model and serial number of both the ratemeter and detector), calibration due date, %

efficiency, background readings (if applicable) and any other pertinent information.

Survey Summary Comparisons of the Site Decommissioning Plan requirements with the Final Surveys performed in relation to the percentage of surface area scanned, number of measurements (i.e., number of fixed radiation measurements), exposure rate measurements ([tR/hr) and soil samples taken are provided as follows:

4

+

GENERAL ATOMICS Final Radiological Survey Report For TRIGA Reactor Facility Electrical Pad Comparisons of Site-Decominissioning P1an Requirements awith

>Final Surveys Perforfijid on the TRIGAReactor FacilityElectrical Pad.~

Surv'e~y'Are Gridding

1. ofDirect **,

1. of Exposure Rate, Surface Scanson asphalt R'equired Measurements Fixed or Measurements c*Ior concrete I

ýa, "13'or-Wipes°n

.n (tiRlhr)

.concrete or asphalt D-Plan*

No None None None Non-Impacted Area -4 Final Surveys No 11 fixed a 13 fixed measurements at 10% of concrete pad Non-Impacted measurements, 8 fixed 1 m from the concrete pad surface and all Area (performed) fI measurements, and surface, 13 fixed accessible surfaces of 4

11 wipe samples measurements at contact the electrical cabinets analyzed for a and 13 with the concrete surface.

were scanned for a and fI activity, for a total of activity.

30 measurements.

Fixed measurements at contact with 12 electrical The pad surface was Plus fixed a and P3 cabinets, and 10% scan of scanned with 434 cm' measurements taken the concrete pad surface proportional detectors on the external surface 100% of the accessible and the cabinets were of each electrical external surfaces of the scanned with small hand

cabinet, electrical panels were held detectors.

taken with a 2" x 2" NaI(TI) detector held within 1" of the surface.

D-Plan = GA Site Decommissioning Plan The total surface area to be released is approximately 88 in2.

Results of the Final Surveys The results for the TRIGA Reactor Facility Electrical Pad Final Surveys are provided in figures and tables as noted below:

Scanning 10% of the surface was scanned for a and P3 activity with large area (434 cm2 ) gas flow proportional detectors held within approximately 1" of the concrete surface. The highest a activity measured (0 - 20 cpm) was less than the background range of 3 to 21 cpm for the instrument used. See Figure 3 for locations and results. The range of P activity measured was 2400 to 2600 cpm. The background for this instrument was 1858 to 2036 cpm. Although the 5

+

GENERAL ATOMICS Final Radiological Survey Report For TRIGA Reactor Facility I

Electrical Pad concrete P3 scans results were higher than background measurements taken with the same instrument, the higher results are due to fluctuations in natural radioactivity concentrations in the concrete; not radioactive material contamination of this pad. The readings are consistent across the entire pad, fixed measurements were all less than the MDA, there was no removable activity, and the exposure rate measurements were background. See Figure 3 for locations and results.

The surface scans of the electrical cabinets detected no a or P3 activity above natural background.

See Figure 3 for locations and results.

Fixed Measurements (a and D)

Eleven (11) fixed a and eight (8) fixed P3 measurements were taken. The highest a activity measured was <20 cpm. The highest P activity measured was less than the minimum detectable activity (MDA) for the instrument used (<313 dpm/I00cm2). All of these measurements are not discemable from natural background activity levels. See Figure 4 for survey locations and results.

Removable Activity Eleven (11) wipe samples were taken. All samples were analyzed for a and P activity. The highest a activity measured was <20 dpm/100 cm2, and the highest P activity measured was <20 dpm/100 cm2. These results are far below the approved release criteria and indistinguishable from natural background levels. See Figure 5 for locations and Table 4 for results.

Fixed Exposure Rate Measurements A total of thirteen (13) fixed measurements were taken at 1m from the pad surface. The highest exposure rate measured was 16 p.R/hr at lm from the surface. These measurements are at or below the natural background range of 15-18 I[R/hr at GA when the detector is held at 1 m from the surface.

In addition, thirteen (13) fixed measurements were taken at contact (within 1") with the external surface of electrical cabinets and thirteen (13) fixed measurements were taken on contact with the pad surface. The highest measurement on the electrical cabinets was 15 [tR/hr. The highest measurement in contact with the pad surface was 18 V.R/hr. See Figure 6 for locations and results.

Exposure Rate Scans 10% of the electrical pad and 100% of the accessible electrical cabinet external surfaces were scanned with a NaI(T1) detector held approximately 1" from the surfaces. The exposure rate 6

+

GENERAL ATOIICS Final Radiological Survey Report For TRIGA Reactor Facility Electrical Pad ranged from 15 to 20 hLR/hr on the electrical pad and were background (6 to 15 [tR/hr) on the electrical cabinets. See Figure 6 for locations and results.

Confirmatory Survey No activity distinguishable from natural background was detected during the Final survey. This factor, combined with the fact that this land area is very small, and it is classified as a Non Impacted Area, lead to the decision that an internal confirmatory survey was not needed.

Conclusion Final contamination and radiation surveys, as documented in this report, demonstrate that the TRIGA Reactor Facility Electrical Pad meets the approved criteria for release to unrestricted use. No activity distinguishable from natural background was detected during the Final survey.

7

Table 1: USNRC'S ACCEPTABLE SUjRACE CONTAMINATION LEVELS

]

Nuclides Averagebf I

Maximumbd$

. Removableb.ef

____uclides______

_ f (dpm/l00cm2)

(dpm/100 cm2

• f(dplm1cm2) J U-nat, 235U, 238U, & associated decay products 5,000 a 15,000 a 1,000 a Transuranics, 226Ra, 228Ra, 230Th, 228Th, 23 1Pa, 227Ac, 100 300 20 1251, 1291 Th-nat, 232Th, 90Sr, 223Ra, 224Ra, 232U, 1261, 1331, 1311 1,000 3,000 200 Beta/gamma emitters (nuclides with decay modes other than alpha emission or spontaneous fission) 5,000 15,000 1,000 except 9"Sr and other noted above.

I a

Where surface contamination by both alpha-and beta/gamma-emitting nuclides exists, the limits established for alpha-and beta/gamma-emitting nuclides should apply independently.

b As used in this table dpm (disintegrations per minute) means the rate of emission by radioactive material as determined by correcting the counts per minute observed by an appropriate detector for background, efficiency, an geometric factors associated with the instrumentation.

c Measurements of average contaminant should not be averaged over more than 1 square meter. For objects of less surface area, the average should be derived for each such object.

d The maximum contamination level applies to an area of not more than 100 cm e

The amount of removable radioactive material per 100 cm 2 of surface area should be determined by wiping that area with dry filter or soft absorbent paper, applying moderate pressure, and assessing the amount of radioactive material on the wipe with an appropriate instrument of known efficiency.

When removable contamination on objects of less surface area is determined, then pertinent levels should be reduced proportionally and the entire surface should be wiped.

f The average and maximum radiation levels associated with surface contamination resulting from beta-gamma emitters should not exceed 0.2 mRad/hr at 1 cm 2 and 1.0 mRad/hr at 1 cm2, respectively, measured through not more than 7 milligrams per square centimeter of total absorber.

T-1

Table 2: STATE OF CA ACCEPTABLE SURFACE CONTAMINATION LEVELS 1 Nuclides' Averageb',',

Maximumb"d Removablebt I

(dpm/100cm')

(dpm/100cm2 )

(dpm/ll0cmi)

U-nat, 235U, 238U, & associated decay 5,000 15,000 1,000 products Transuranics, 226Ra, 228Ra, 230Th, 228Th, 100 300 20 "23 1pa, 227Ac, 1251, 1291 Th-nat, 232Th, 9°Sr, 223Ra, 224Ra, 232U, 1261, 1,000 3,000 200

1331, 1311 Beta/gamma emitters (nuclides with decay modes other than alpha emission or 5,000 15,000 1,000 spontaneous fission) except 9Sr and other noted above a Where surface contamination by both alpha-and beta/gamma-emitting nuclides exists, the limits established for alpha-and beta/gamma-emitting nuclides should apply independently.

b As used in this table dpm (disintegrations per minute) means the rate of emission by radioactive material as determined by correcting the counts per minute observed by an appropriate detector for background, efficiency, an geometric factors associated with the instrumentation.

c Measurements of average contaminant should not be averaged over more than 1 square meter. For objects of less surface area, the average should be derived for each such object.

d The maximum contamination level applies to an area of not more than 100 cm '.

e The amount of removable radioactive material per 100 cm2 of surface area should be determined by wiping that area with dry filter or soft absorbent paper, applying moderate pressure, and assessing the amount of radioactive material on the wipe with an appropriate instrument of known efficiency. When removable contamination on objects of less surface area is determined, then pertinent levels should be reduced proportionally and the entire surface should be wiped.

f The average and maximum radiation levels associated with surface contamination resulting from beta gamma emitters should not exceed 0.2 mrad/hr at 1 cm2 and 1.0 mrad/hr at 1 cm2, respectively, measured through not more than 7 milligrams per square centimeter of total absorber.

Guidelines For Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses For byproduct, Source, or Special Nuclear Material, also known as "Decon-1" incorporated into GA's State of CA Radioactive Materials License.

T-2

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RF_

f2

[-.: p TABLE V LIST

.F.NStftP1YM tNTS* < >,.

4W3/4...

4 7....

'Detector'.-'

Range 4<"s> ' Calibration Due Eyý,,ack d

-Descriptioni,.i i

,*Ludlum,;,:"f:

Ludlum Model 43-37 gas Four Linear Ranges 06/02/02 21 29%

3 - 2 1cpm (concrete )Active Probe Area =434 cm'. Ile detector and rate meter S

Model12221,**,i*

(434cm') proportional 0-500,000 & one Log are combined and mounted on a roll around cart The SN n

148425 Alpha detector 50-500,000 instrument features a static-flow system, quick connects, a S

S/N 086236 (CPM) portable gas bottle and a means to adjust the height of the

'1'*

,detector from the floor for optimum performance Ludlum Ludlum Model 43-37 gas Four Linear Ranges 09/27/02 31 08%

1858 -2036cpm (concrete)

Active Probe Area = 434 cm'. The detector and rate meter

-Model 2221 o.

(434cm2) proportional 0-500,000 & one Log are combined and mounted on a roll around cart. The "S/N 84459 Beta detector 50-500,000 instrument features a static-flow system, quick connects, a SIN 086215 (CPM) portable gas bottle and a means to adjust the height of the

.detector from the floor for optimum performance, Ludlum.

Ludlum Model 43-68 Four Linear Ranges 01/08/02 24 43%

1850290cpm( concrete)cm gas flow proportional counter Model 2221 (434cm) proportional 0-500,000 & one Log aeo idnmutonrlaudc.T 1

N 8442359,

Beta detector 50-500,000

... -~

S/N 119444 (CPM)

",Ludlum -n.

Ludlum Model 44-10 Four Ranges 02/05/02 NA 10 - 18 2i r

2 inch x 2 inch Nal (TI) scintillator. Used for measurng

'Model Nal (210

) Scintillator 0-500 0

R/hr external dose rates on the surface and at one meter.

S/N 15184423 Gamma Detector K

"<'t; ',

S/PN 154618 Ludluiiih, Ludlum Model 44-10 Four Ranges 01/08/02 NA 10 - 18 p/hr 2 inch x 2 inch Nal (TI) scintillator Used for measuring

,,Model<3'

],

Nal (TI) Scintillator 0-500 gR/hr external dose rates on the surface and at one meter.

S/N 153551.

Gamma Detector

-" ?

S/N 155109

• 'Ludlum-iiiv'.

Ludlum Model 44-9 Four Ranges 01/17/02 2026%

80 - 120cpm Active Probe Area = 15cia2 Model 3 l

N!5cm beta/gamma probe 0-500,000 cpm Used for beta/gamma surveying

,'SSN 143349 S/N 145967 tudlum rn".

4 Ludlumn Model 43-64 Four Ranges 01/10/02 21.58%

1 - 20cpm (concrete)

Active Probe Area =50cm2

' Model 12 Alpha Scintilator 0-500,000cpm MDA=297dpm/I100cm 2 Used for Alpha surveying

.. S/N 138738,,

ZnS (Ag)

"S/N 148346 C~iiberraLoI_*ei Gas Flow N/A As needed 30%

Varies with Sample Canberra Model 2404 Low Level / gas proportional 6/fl Counter' Proportional Detector counting system used to count wipes for removable

, '?Model 4 2404' contamination Results are usually reported as dpm/100cm2.

Canberra Gamma high Purity N/A As needed Vanes with Vanes with Sample Gamma Spectroscopy MCA system using a high purity Specfro6c*o System Germanium Detector Sample Germanium detector.

T-3

T4 Table 4:TRIGA' Reactor Facility Electrical Pad Wipe Survey Results Sample Number a Activity in dpm/100cm2 (3 Activity in dpm/100cm2 1

<20

<20 2

<20

<20 3

<20

<20 4

<20

<20 5

<20

<20 6

<20

<20 7

<20

<20 8

<20

<20 9

<20

<20 10

<20

<20 11

<20

<20

Figure 1: Main Site and Sorrento Valley Site Building Numbers Names Building 1 Administration N

Building 2 Science Laboratories A, B, C 7-A Building 7 Cafeteria Building 9 Experimental Building W

E Building 10 Maintenance Building Building 13 Technical Office Building TS Building 14 Technical Office East S

Building 15 Technical Office East T*

Building 19 Swimming Pool Building Building 21 TRIGA Building Building 22 TRIGA Fuel Lab Building Building 23 Hot Cell Building 25 Waste Yard Building Building 27 Experimental Area Building 27-7 Experimental Area Building 29 Experimental Area r--T Building 29-2 Emergency Vehicle Storage Building 7

5 Building 30 LINAC Complex Building 31 TRIGA Storage Building Building 31-1 Neutron Radiography Building Building 31-2 ECF Critical Building Building 31-3 Storage Building Building 33 Fusion Building RrJNHILL Building 33-1 Fusion Lab Building

-IL ST Building 33-5 Fusion Building Annex 5 2

Building 34 Fusion Doublet III Building Building 34-1 Fusion Doublet III Capacitor Building 034-4 Building 34-2 Fusion Doublet III Lab Building Building 34-3 Fusion Doublet III Storage Building 4-1 Building 35 Test Tower Building Building 35-1 Facilities (Shipping & Receiving) Building Building 36 Blower Assembly Building 45 Building 37 Sorrento Valley Building 0

Building 39 Sorrento Valley Building

35.

Building 39-1 Storage Building L0 R3E L.

Building4l Raw Stock Facility Building 42 NDT Facility BuIlding 45 Helium Circulator Test Facility vG SITE Building 63 3550 Dunhill St

.?

Building 64 11030 Roselle St Building 65 11D40 Roselle St Building 66 3520 Dunhill St.

OPENSPACE Building 66 3510 Dunhill St CONTROLLED MAIN SITE TRIGA Reactor LOTS Facility Eletrical Pad 31-1

/.

S*

22 GENEAL j!

tLOTS 3

29 0S INSYUSTRY 27-1 0

2 UC2 GEEA LOTS LU IPROPERTY LINE INDUSTRYNG 0

250 500 750 1000 liii SCALE IN FEET

Figure 2 : TRIGA Reactor Facility Eletrical Pad Area in Relationship to Surrounding Areas JV S

TRIGA REACTOR FACILITY ELETRICAL PAD FORMER HOT CELL LAND

.INAC LAND TORREY PINES EAST TORREY PINES CENTRAL

Figure 3: Building 21 (TRIGA) Backyard Electrical Pad Alpha and Beta scans Date: Dec. 09,2001 Technician : B.Hunter, B.Lyon, S.Cowan, J.Sullivan COMMENTS:

Alpha and Beta scans of equipment cabinets with handheld instruments showed only background levels. All readings are in cpm.

Meter Information, Model........

Ludlum 2221 434cm2 SN.......... 84459 PN........

086215 EFF.........

31 08%

Cal Due...... Sept 27, 2002 BKGD.......

Concrete... 1858-2036 Meter Information.

Model......

LUDLUM 12 50cm2 ra SN-.........138738 PN:.......

148346 EFF........ 21.58%

Cal Due......

Jan 10, 2002 MDA........... Concrete..... 297 dpm/100cm 2 BKGD......

20 cpm/50cm2 Meter Information Model......

Ludlum 2221 434cm 2 a SN..........

148425 PN......... 086236 EFF:.......

21.29%

Cal Due-.... Jun 2, 2002 BKGD........

Concrete

...3-21 Meter Information Model:.......

LUDLUM 3 15cm 2p SN.......

.143349 PN

....... 145967 EFF:........... 20.26%

Cal Due....... Jan. 17, 2002 BKGD.......80-120 cpn/l5cm 2

=

= equipment N

V S

Figure 4: Building 21 (TRIGA) Backyard Electrical Pad Alpha and Beta Fixed

=

= equipment

= Beta Reading in dpm/100cm2

//#=

Alpha Reading in dpm/100cm 2 Meter Information.

Model LUDLUM 100cm 2 13 SN........ 84423 PN.....

119444 EFF:......... 24.43%

Cal Due.... Jan 08, 2002 MDA:.......

Concrete.

... 313 dpm/100cm 2

BKND......

Concrete.

..1042 cpmnO0crM2 Meter Information, Model..

LUDLUM 12 50cm 2 a SN........... 138738 PN......... 148346 EFF:.......... 21 58%

Cal Due

.... Jan 10, 2002 MDA'........Concrete...... 297 dpm/100cm 2 BKGD........ 20 cpml50cm2 N

S Date: Dec. 09,2001 Technician: B.Hunter, B.Lyon, S.Cowan, J.Sullivan COMMENTS:

Alpha and Beta measurements of equipment cabinets with handheld instruments showed only background levels.

Figure 5: Building 21 (TRIGA) Backyard Electical Pad Wipe Survey N

A V

S Date : 12/09/01 Technician:

B. Lyons, B.Hunter, S.Cowan,J.Sullivan

Figure 6: Building 21 (TRIGA) Backyard Electrical Pad Exposure Rate scans and Fixed Readings N

s Meter Information Model......... LUDLUM 3, 2"x2" g. R SN.......

151348 PN.......

154618 EFF:............. n/a Cal.Due.....

Feb 05, 2002 BKGD...

15-18giR/Hr 4-15-20*R Meter Information, Model...... LUDLUM 3, 2"x2" *. R SN.....

....... 153551 PN.....

....... 155109 EFF:...

.. n/a Cal Due Jan. 08, 2002 BKGD........ 15-18 ILRPHr

= Scan Measurement Date: Dec. 09,2001 Technician : B.Hunter, B.Lyon, S.Cowan, J.Sullivan COMMENTS:

Scans of equipment cabinets with handheld instruments showed only background levels.

All readings are in ptR/Hr I "

I < 17 I

15-20 g:

I -~-'----

=

= equipment 1_8 = Measurement @ Contact 16 = Measurement @ 1 Meter 12* = Measurement @ Contact 12*

12*

12*

General Atomics' Final Radiological Survey Report For TRIGA Reactor Facility Electrical Pad Appendix A Final Survey Plan

Prepared By:

0" Date:

/Z

/01 Approved By:

L.~t t~ozae Date:

01 L. Q. Gonzales Final Survey Plan for TRIGA Reactor Facility Electrical Pads This survey plan is for the release of the TRIGA Reactor Facility Electrical Pad located behind Building 21 at the Northwest comer of the building. This Electrical Pad will be surveyed to show compliance with the GA Site Decommissioning Plan criteria. This survey does not include the open land areas associated with TRIGA Mark-I or Mark-F. Figure-1 shows the area to be released relative to the remainder of GA's Main Site (Torrey Pines Site). Figure-2 shows the area to be included in this survey.

Classification This Electrical Pad contains electrical transformers, substations and breakers that provides power to TRIGA Mark I and Mark F Cooling and Auxiliary systems. This pad has no history of radioactive material storage or use. This electrical pad is classified as a Non-Impacted Area for final survey purposes. The GA Site Decommissioning Plan does not require radiological surveys in Non-Impacted Areas, however, the minimum surveys identified in this plan will be performed.

If any measurement is above 75% of the release limits presented below, the area will be re classified and survey requirements will be expanded.

Survey Objectives and responsibility The purpose of performing a final survey is to demonstrate that the radiological conditions satisfy the NRC and State of California guidelines for release to unrestricted use contained in the GA Site Decommissioning Plan as reproduced below for applicable measurements.

Samples will be taken by qualified Health Physics technicians having a minimum of 3 years Health Physics Technician experience following approved Health Physics procedures and this plan.

Release criteria (per GA Site Decommissioning Plan)

1.

Contamination limits The applicable release criteria for the surfaces of the asphalt/concrete pads, based on Beta/Gamma emitters, is:

5,000 dpm/100 cm', averaged over 1 m2 area 15,000 dpm/100 cm 2, maximum in a 100 cm2 area 2

1,000 dpm/100 cm, removable activity

2.

Exposure Rate Measurements The guideline value for exposure rates measured at 1 m above the surface is 10 I[.R/hr above background.

Alert Levels Note: The Alert levels provided below are based on the background cpm plus the meter cpm value taking into account the instrument efficiency and probe surface area.

1.

Alpha Monitoring

>100 cpm alpha using the large area (434 cm 2) probe. If>100 cpm, check with a hand held alpha meter.

>60 cpm using a hand held alpha probe, notify Health Physics Management.

2.

Beta Scanning using 434 cm 2 probe

> - 1900 cpm beta using the large area (434 cm 2) probe (#84459)

> -2300 cpm beta using the large area (434 cm2) probe (#73701)

> -300 cpm above background using any other 434 cm2 probe

3.

Beta Measurement Using the 100 cm 2 probe

> -200 cpm (400 counts in 2 minutes) above background for a beta 100 cm 2 gas flow proportional counter.

4.

Beta Measurement Using the Pancake GM probe

> 150 cpm Decontamination Required-when (1) Pancake GM measurement > 150 cpm or (2) values greater than those provided above using the 100 cm2 probe.

5.

Exposure Rate Measurement Exposure rate measurements at 1 m above the surface: 5 [.tR/hr above background or any reading > 20 hIR/hr at 1 m, which ever is less. The alert level for surface scans is 25

[tR/hr.

Final Survey Requirements The minimum survey requirements are identified in Table-1 as follows:

Table-I: TRIGA Electrical Pad Minimal Final Survey Requirements Area Dose Rate a and P Scan Fixed Soil Samples Measurements Measurements Measurements Non-Impacted Scan 10% of Scan 10% of Take a Fixed Not Applicable Areas concrete surface concrete surface measurement at contact with a 434 cm2 every 7m.

(meter/probe Beta detector Alternate Fixed held within 1" of and 10% of the Alpha, and the surface) with surface with a Fixed Beta a 2" x 2" Nal 434 cm2 Alpha measurements, (TI) detector.

detector. Scan and, Swipe Take 10 equally the external samples spaced dose rate surfaces of each (analyzed for measurements at electrical panel a,[).

lm from the with a 15 cm2 concrete surface.

Beta detector Take 1 dose rate and with a 50 measurement at cm Alpha contact with detector.

each electrical panel.

Documentation Every survey conducted must be documented on a daily basis on a drawing showing the approximate locations surveyed. Include the results (including units), the technician signature, date, instrument(s) used, efficiency, background readings (if applicable) and any other applicable information.

Figure 1: Main Site and Sorrento Valley Site Names Building 1 Building 9 Building 9 Building 10 Building 13 Building 14 Building 15 Building 19 Building 21 Building 22 Building 23 Building 25 Building 27 Building 27-7 Building 29 Building 29-2 Building 30 Building 31 Building 31-1 Building 31-2 Building 31-3 Building 33 Building 33-1 Building 33-5 Building 34 Building 34-1 Building 34-2 Building 34-3 Building 35 Building 35-1 Building 36 Building 37 Building 39 Building 39-1 Building 41 Building 42 Building 45 Building 63 Building 64 Builig 65 Building 66 Building 66 Administration Science Laboratories A, B, C Cafeteria Experimental Building Maintenance Building Technical Office Building Technical Office East Technical Office East Swimming Pool Building TRIGA Building TRIGA Fuel Lab Building Hot Cell Waste Yard Building Experimental Area Experimental Area Experimental Area Emergency Vehicle Storage Building LINAC Complex TRIGA Storage Building Neutron Radiography Building ECF Critical Building Storage Building Fusion Building Fusion Lab Building Fusion Building Annex 5 Fusion Doublet III Building Fusion Doublet III Capacitor Building Fusion Doublet Ill Lab Building Fusion Doublet III Storage Building Test Tower Building Facilities (Shipping & Receiving) Building Blower Assembly Building Sorrento Valley Building Sorrento Valley Building Storage Building Raw Stock Facility NOT Facility Helium Circulator Test Facility 3550 Dunhill St 11030 Roselle St.

11040 Roselle St 3520 Dunhill St 3510 Dunhill St TRIGA Reactor Facility Eletrical P UCSD FENCING PROPERTY LINE 0

250 500 750 1000 Ii"'

SCALE IN FEET Building Numbers N

W+E S

SITE OPEN SPACE LOTS

Figure 2 : TRIGA Reactor Facility Eletrical Pad Area in Relationship to Surrounding Areas 4

S TRIGA REACTOR FACILITY ELETRICAL PAD FORMER HOT CELL LAND JNAC LAND TORREY PINES EAST TORREY PINES CENTRAL