ML20195D487
| ML20195D487 | |
| Person / Time | |
|---|---|
| Site: | 07000734 |
| Issue date: | 05/28/1999 |
| From: | Asmussen K GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER |
| To: | Rogus R CALIFORNIA, STATE OF |
| Shared Package | |
| ML20195D496 | List: |
| References | |
| CAL-3089, NUDOCS 9906090180 | |
| Download: ML20195D487 (35) | |
Text
.
h CENERAL ATCHNt*C May 28,1999 CAL-3089 VIA EXPRESS DELIVERY SERVICE p p p/
Ronald Rogus, Ph.D.
Califomia Department of Health Services Radiologic Health Branch P. O. Box 94732 Sacramento, CA 94234-7320
Subject:
Radioactive Materials License No. 0146-37; Docket Number 110498 0145;
)
- 1) Responses to California DOHS RHB ltems regarding General Atomics' Hot Cell Final Survey Plan, and 2) Submittal of Redssi Final Radiological Survey Plan
Reference:
Rogus, Ronald, Letter dated November 30,1998 to Keith E. Asmussen regarding California DOHS RHB Review Comments on General Atomics' Final Survey Plan for its Hot Cell Facility; Reference Docket Number 110498-0145
Dear Dr. Rogus:
j Enclosed are General Atomics' (GA) responses to the items identified in your letter of November 30,1998 regarding GA's Final Survey Plan for its Hot Cell Facility (Reference).
Also enclosed, for review and approval, is a copy of the revised final survey plan General Atomics (GA) intends to implement to demonstrate that the former site of its Hot Cell Facility meets the NRC-and State of Califomia-approved criteria for release to unrestricted use. The final survey plan was revised primarily to be consistent with the systematic survey plan described in GA's approved Hot Cell Decommissioning Plan and with the surveys currently being conducted.
This revised final radiological sumey plan was prepared taking into account the additional knowledge obtained during the actual decontamination, dismantlement and remediation phases l
of the Hot Cell Facility (HCF) decommissioning effort. Accordingly, it represents a more focused and situation specific plan than that discussed in GA's Hot Cell Facility Decommissioning Plan (latest revision dated January 1998). The enclosed revised plan incorporates and integrates the necessary and appropriate criteria from Chapter 4, " Planned Final Radiation Survey," of the HCF Decommissioning Plan into a complete, stand alone final survey document. Accordingly, this
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plan supersedes Chapter 4 in specifying how compliance with the release criteria will be demonstrated.
GA trusts that this revised final survey plan plus the enclosed GA responses to your l
Items / questions, and the commitments made therein, addresses all open issues regarding the l
approach and method GA will use in performing the Final Radiological Survey of its Hot Cell site.
This approach will clearly demonstrate compliance with the approved release criteria.
GA has completed decontamination and post decontamination surveys at the site, and has in fact, begun the Final Radiological Suwey in accordance with this revised plan. GA regrets the delay in responding to your items / questions, but the unavailability of key personnel, the 9906090180 990528 PDR ADOCK 07000734 C
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. - i, i. i is e ro sox essoa. SAN DIEGO. CA 92186 5608 (619)455-3000 L
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Dr. Ronald Rogus, State of California May 28,1999 CAL-3089 Page 2 benefit of additional information gained from actual decontamination /remediation activities at the Hot Cell Facility, and the desire to revise the plan in the most meaningful manner, all contributed to the delay.
Your timely attention to our request for approval of the enclosed plan will be greatly appreciated, and will enable GA to pursue its aggressive schedule for completion of this project.
If you have any questions regarding the above, please do not hesitate to call Ms. Laura Gonzales at (619) 455-2758, or me at (619) 455-2823.
Very truly yours.
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KdblC. L -
j Keith E. Asmussen, Ph.D.
- Director, Licensing, Safety and Nuclear Compliance
Enclosure:
Responses to Questions from Dr. Ronald Rogus' letter dated October 30,1998; with seven (7) attachments as stated in enclosure; one of the seven attachments, i.e.,," is GA's Revised " Final Radiological Sunley Plan for General Atomics's Hot Cell Facility Area," dated May 1999. (2 copies of all) cc: Mr. Charles E. Gaskin, NRC Headquarters (w /o attachment no. 7)
Mr. David Wesley, State of California, DOHS, Sacramento, CA (w /o attachment no. 7)
Mr. Wayne L. Britz, NRC Region IV (w /o attachment no. 7)
Ms. Kathleen Henner, State of California, DOHS, Los Angeles, CA (w ki attachment no. 7)
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Page 1 of 8 May 28,1999 Laura Go es/ Bill LaBon W-
"S khth Responses to Questions from Dr. Rortald Rogus' letter dated October 30,1998 regarding the " Final Survey Plan for General Atomics' Hot Cell Facility Area" 1.
Comment: Pane 1. section 2.0. paranraoh 2. Please state the source of the fill soil. Please line any pits with burlap or other suitable material to demarcate fill soil from existing soil.
GA 's Responser The fill soil used to date has been ~75% soil which was excavated during the removal of the Hot Cell Stack sample pit and was analyzed prior to using as fill soil. About 25%
has been from an area near the EA-1 bunker facility (Building 27-1) which was also sampled and analyzed prior to using as fill soil. All soil sample results were less than the release criteria.
Pits which have been filled have been lined with burlap or similarly identified in the event that reopening is required. Please note that GA addressed in its letter no. CAL-2981 to Mr. David Wesley dated September 30,1998 the protocol it would follow when refilling of excavation pits-including lining with burlap or other bio-degradable meterial to delineate the excavation boundary.
2.
Comment: Pane 3. section 5.1. Table 1.
Please refer to Table 4-3 in " General Atomics' Hot Cell Facility Decommissioning Plan,"
j revision dated January 1998. Please add Am-241 and the six plutonium radionuclides listed in Table 4-3 of the Decommissioning Plan to Table 1 of the Final Survey Plan.
GA 's Responser The reason Am 241 and the six plutonium radionuclides listed in Table 4-3 of the Decommissioning Plan were not included in Table 1 of the Final Survey Plan is because there is no evidence that these isotopes are present in the soil.
1.
Results for ~1,000 soit samples collected and analyzed by gamma spectroscopy (using a high purity germanium detector) during post decontamination surveys showed no j
measurable Am-241; the typical sensitivity for a 30 minute count is < 0.3 pCi/g.
l 2.
The results of the analyses of these ~1,000 soil samples showed U 235 concentrations at I
or near natural background levels (i.e., typically < 0.2 pCi/g). During the characterization study, U-235 concentrations in ~30 soil samples analyzed were also found to be at or near background levels. On the basis of process knowledge, no plutonium is expected to be present. However, ifit were present, it would be expected to be at levels significantly less than those of U-235, 3.
General Atomics will submit ten (10) soil samples from the Hot Cell site and two (2)
W background soil samples to an outside laboratory fer plutonium analysis.
.Cammcat Please refer to note 1 of Table 1. RESRAD was used to determine release criteria for several radionuclides listed in Table 1 (Table 4-3 in the Decommissioning Plan mentioned above). Please provide the summary reports for each radionuclide.
I 4
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',Y Page 2 of 8 GA 's Rnponser RESRAD calculations used to determine the soil release criteria for Cs-134, Eu 152, Eu-154, Eu 155, Nb 94 and Sb-125 listed in Table I are provided in Attachment 1.
Camment: Please refer to note 2 of Table 1. General Atomics states that release criteria for Co-60, Cs-137, and Sr-90 were based upon precedent with NRC and State of California. Please submit the letter to W. T. Crow, dated October 1,1985, signed by K. E. Asmussen, titled
" Docket 70-734: Plan for Obtaining Release of Certain Areas to Unrestricted Use."
GA 's Responser A copy of the letter dated October 1,1985, signed by K. E. Asmussen, " Docket 70-734: Plan for Obtaining Release of Certain Areas to Unrestricted Use."is provided in. In addition, a copy of the NRC's letter approving this plan (letter dated November 26,1985 signed by W.T. Crow) is provided in Attachment 3.
i Comment: Please refer to note 3 of Table 1. Please submit NRC Policy issue SECY-81-576 dated October 5,1981.
GA 's Responser A copy of the NRC Policy Issue SECY-81-576 dated October 5,1981 is provided in Attachment 4.
3.
Comment: Paoe S. section 6.2. nrragranh 1. Please commit to scanning 100% of the surface, 4
and to scan for beta and gamma emitters.
I CA 's Responser Gamma scans will be conducted at 1-2 m intervals over approximately 100% of the site using Nal scintillation detectors and ratemeters with audible indicators. Locations of elevated radiation, suggesting the presence of surface or near surface contamination, will be marked and identified for further investigation.
In addition, approximately 100% of all accessible soil surfaces will also scanned for beta I
2 emitters using a gas flow proportional detector having a 434 cm beta detector.
4.
Comment: nage 7. section 6.5. narnaraph 2. Please provide additional information on how the Sr-90 concentration in the soil will be measured or estimated. What was the Sr-90/Cs-137 ratio that was determined during the characterization study? How many soil samples were analyzed and how much did the ratio vary from sample to sample?
GA 's Responser Table 3-7 of the Final Characterization Report (page 3-58 of Attachment 7) provides the results of 21 samples (16 concrete and 5 soil) analyzed by wet chemistry for Sr-90 by an ofTsite laboratory (TMA). A summary of the data for all 21 samples as well as for the 5 soil samples are provided below:
- of Samples Lowest Highest Range of Sr-90/
Average
- o Sr-90/Cs-137 ratio Sr-90/Cs-137 ratio Cs-137 ratios l
l 21 (concreic and solt) 0.010 0.449 0.010 - 0.449 0.168 i 0.131 5 (soilonly) 0.114 0.309 0.114 -0.309 0.165
- 0.10
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In addition, General Atomics recently (1998) sent five (5) soil samples collected from the Ilot l
Cell site offsite for Sr-90 wet chemistry analysis. De samples included " hot" samples from l
inside the liquid waste drain line which were expected to have the highest concentration of Sr-90 remaining at the site (these drain lines were removed and disposed of as radioactive waste). The i
results of the analysis is provided in the table below:
- of Samnples Lowest Highest Range of Sr-90/
Meam
- a Sr-90/Cs-137 ratio Sr-90/Cs-137 ratio Cs-137 ratios 5
0.01 1.3 0.01 - 1.3 0.46
- 0.51 The results and locations of each of the five samples are provided in the table below (the locations are shown in the drawing on page 7).
Sample #
Location Concentration Concentration (PCL/g)
(pCi/g) 23A-98-158 Vent Stack Area 1.4
- 0.35 1.08
- 0.16 1.3 23A-98159 Vent Yard Area 0.25*0.20 2.19
- 0.26 0.11 23 A-98-160 Depression silt / sand 1.09 i 0.32 75.1
- 8.1 0.01 23 A-98-173 Southwest gate restricted area 0.69
- 0.34 2.03 t 0.58 0.34 23 A-98-174 East rolling gate restricted area 0.90 0.31 1.70
- 0.22 0.53 GA 's Evaluation: De data shows that typically the Cs-137 concentrations are higher than the Sr-90 concentrations, therefore to be conservative, GA will assunee that the concentration ofSr-90 is 1.5 times the concentration of Cs-137. Since the Cs-137 soil release criteria is 15 pCi/g, then the Sr-90 concentration will always be < 23 pCi/g; well below the Sr-90 soil release criteria of I800 pCi/g.
In addition to this evidence, at least 30 soil samples taken during the Final Survey will be analyzed by gross beta to demonstrate that the upper bound for Sr 90 is less than the soil release criteria of 1800 pCi/g.
Comment: Describe the method that will be used to analyze the soil for gross alpha and beta.
What are the alpha and beta emitter MDA's for the methods that will be used for the soil analysis? Are these MDA's sufficiently low relative to release criteria?
GA 's Respomer At least 30 soil samples taken during the Final survey will be analyzed by gross beta to estimate the Sr-90 concentrations as described above. The soil is prepared by drying and grinding and filling a clean planchet evenly with the sample. The samples are counted for 60 minutes using a Model 2400 Canberra Low Level Gas Flow Proportional Counter and a 4000 VLC (Vax Computer) Genie ESP (Enhanced Spectroscopy Package) computer.
1
- 7 Page 4 of 8 GA can detect gross beta concentrations of~10 pCi/g in soil (the limits of detection are actually much lower but naturally occurring radioactivity in soil typically is ~ 10 pCi/g).
5.
Cnmment: Pane 8. section 8.0. ww=h 1. For the confirmatory scans that will be done by your internal group, what is the percent coverage for the gamma and beta scans? Will the internal group take any direct measurements or soil samples?
GA 's Responser The internal confirmatory survey will include gamma scanning 10-25% of the soil surfaces using a Nal detector (i.e., microR meter). No beta scans will be performed. At least 30 soil samples will be collected from biased locations and will include sampling locations where elevated radiation levels have been measured.
6.
Comment: Pape 8. section 9.0. narmarank 1. Please describe the scope of the confirmatory surveys that will be done by ORISE Will ORISE scan for pure beta emitters (specifically Sr-90/Y-90), and what measurements will ORISE make on the soil samples? To be consistent with General Atomics' decommissioning plan, ORISE needs to use a NUREG/CR-5849 approach for the confirmatory surveys, not a MARSSIM approach.
GA 's Reinonser ORISE has provided DOE with a proposed verification survey plan for the Hot Cell Facility. A copy of their plan is attached (Attachment 5). ORISE plans to utilize a NUREG/CR-5849 approach and not a MARSSIM approach.
7.
Additinnal Cnmments:
Comment 7A: Please describe what efforts will be made to reduce external background levels to a low level, prior to commencing the Final Survey. Background levels may be elevated, for example, by the presence of gamma emitters being stored adjacent to the Hot Cell area. The sensitivity of the gamma scanning and direct measurements will be improved by lowering the background.
GA 's Responser All radiation sources have been removed including underground drain lines, l
storage wells, radioactive waste, and radioactively contaminated items. GA has removed sources adjacent to the Hot Cell facility as well. Prior to the Final Status Survey, post decontamination surveys were completed. They included scanning the soil and the collection of soil samples and l
remediation of areas, as needed. A total of-1,000 soil samples were collected during the post decontamination survey and prior to initiation of the Final Survey.
Comment 7B: Background levels may change day-to-day and week-to-week as the Final Status l
Survey is conducted. How will these changes in background be documented and accounted for during the Final Status Survey?
GA 's Responser With the removal of all radiation sources and remediation of the contaminated soil, the background levels are expected to remain relatively constant. In addition, an alert level has been established at which time an investigation is required; the alert level has been set at 50% of the limits. &1m Using a microR meter for exposure rate surveys, background levels are typically 15 microR/hr; therefore, any results > 20 microR/hr will be investigated (the release level is 10 microR/hr above background measured at I meter from the surface).
F Page 5 of 8 Comment 7C: Please state that General Atomics will maintain the commitments made in
" General Atomics' Hot Cell facility Decommissioning Plan," revision dated January 1998, including specifically those commitments made in Section 4.3 " Release Criteria - Residual Radiation and Contamination levels,", Section 4.4 " Measurements for Demonstrating Compliance with the Release Criteria, and Section 4.5 " Methods to be Employed for Reviewing, Analyzing and Auditing Data."
Please state that General Atomics will maintain its commitments to the guidance and recommendations provided in NUREG/CR-5849," Manual for Conducting Radiological Surveys in Support of Li::ense Termination."
GA 's Resoonser The applicable commitments made in Sections 4.3,4.4 and 4.5 and guidance in NUREG/CR-5849 draft manual have been incorporated into a revised Final Survey Plan.
The revised Fins 1 Survey Plan (Attachment 6) dated May 19,1999 includes (1) a revised systematic sampling plan which is also consistent with NUREG/CR-5849 and section 4.4 of the Decommissionirig Plan, and (2) additional commitments made for reviewing, analyzing and auditing data.
Comment 7D: Please commit to taking sufficient radiological measurements such that the total inventory of residual activity from licensed operations over the Hot Cell footprint may be determined. Results are to be provided in the Final Status Survey Report.
GA 's Rexnonser As past of the final survey report, an estimate of the total amount of residual activity remaining will be provided.
Comment 7E: Describe how the soil will be analyzed for H-3, and for the Th, U, and Pu radionuclides that cannot be measured by gamma ray spectroscopy.
- GA 's R sponse Tritium use was contained inside an enclosed system within an enclosure
'which was confined to a single room (room 109) within the Hot Cell building. Tritium which was released (as effluent) was in a gaseous form. At the end of the project, DOE personnel came onsite to remove the tritium and the potentially contaminated equipment including the enclosure from the facility. Subsequently, during Hot Cell decommissioning and dismantlement, the walls and floors of this room (along with most of the building) were disposed of as radioactive waste.
Therefore, no tritium analysis will be performed. Thorium and uranium can be analyzed by gamma spectroscopy at levels well below the release criteria.
Ten (10) soil samples will be sent offsite for plutonium analysia to verify that there is no plutonium contamination in the soil. The criteria for determining which samples to analyze will i
l include (1) sampling areas with the highest potential for contamination, (2) analyzing samples containing Am-241 and (3) samples having elevated U-235 concentrations.
Comment 7F: Please' submit a report on the characterization Survey for the Hot Cell.
GA 's Response A copy of the Characterization Report is provided in Attachment 7.
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Page 6 of 8 Cam--* 7G: Please commit to taking direct gamma and direct beta measurements at each location where soil is sampled. Please commit to taking these direct measurements at the surface and at a height ofI m.
GA 's Rs ponser While this is not required by GA's approved Site Decomissioning Plan, dose rate measmements (microR/hr) will be taken on the surface and at I m at each location where a soil sample was collected.
Comment 7H: Please provide a table summarizing the sensitivities, in terms of MDA's and as a percentage of the appropriate release criteria, for the various detectors and types of measurements that will be made as part of the Final Status Survey.
i GA 's Responsesr To demonstrate compliance, GA is releasing the site based on exposure rate measurements taken at I m from the surface and the results of soil samples analyzed by gamma spectroscopy. The Minimum Detectable Activities (MDA's) for gamma emitters measured using GA's high purity germanium detector varies according to the radionuclide, geometry, type of sample, and counting time. 'Ihe typical detection sensitivities provided below are values which can be measured in a 30 minute counting time. These data clearly demonstrate GA's ability to detect levels significantly below the approved release criteria. Actual MDA's are much lower than these values. The percentage of the appropriate release criteria is also provided below:
Instrument Typical Detection Sensitivity
% of release criteria j
MicroR meter 12 microR/hr
~20%
Gamma
< 0.1 pCi/g Cs-137
- 0.6 %
8 Spectroscopy
<0.1pCi/g Co-60
~ 1.3 %
i
< 0.1 pCi/g Cs-134
~l%
< 0.3 pCi/g Eu-152
- 2.7 %
< 0.3 pCi/g Eu-154
-3%
< 0.3 pCi/g Eu-155
< 0.1 %
< 1.0 pCi/g Nb-94
~13.3 %
I
< l.0 pCi/g Sb-125
~2.7 %
< l pCi/g Th-228 (indicates Th-232)
~20 %
< l pCi/g Ac-228 (indicates Th-228)
~20 %
i
< 3 pCi/g U-238
~B.6 %
l
< 0.2 pCi/g U-235
~20 % (if 93% enriched;less for lower I
enrichments)
< 0.3 pCi/g Am 241
~1.2%
Gross Beta
< 10 pCi/g gross beta 8
-0.6%
' Based on a 500 ml marinelli sample size & 30 minute count.
2 Based on a 60 minute count.
l
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i Page 7 of 8 List of Attachments : Soil Release Criteria RESRAD calculations for Selected Radionuclides (Cs-134, Eu-152, Eu-154, Eu-155, Nb-94 and Sb-125). : Letter dated October 1,1985, signed by K. E. Asmussen, " Docket 70-734: Plan for Obtaining Release of Certain Areas to Unrestricted Use." : Letter from NRC dated November 26,1985 signed by W.T. Crow approving GA's Decommissioning Plan (Attachment 1). : NRC Policy Issue SECY-81-576 dated October 5,1981. : Letter dated February 11,1999 from Timothy Vitkus to Rod Cummings with the enclosed " Proposed Verification Survey Plan for the llot Cell Facility, General Atomics, San Diego, California". : Revised Hot Cell Final Radiological Survey Plan dated May 25,1999. : PC-000456 " General Atomics' Hot Cell Characterization Report" dated December 1995.
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r Letter dated October 1,1985, signed by K. E. Asmussen," Docket 70-734: Plan for Obtaining Release of Certain Areas to Unrestricted Use."
l 1
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r b ly Refer To: 696-8023 GA Technologies Inc.
M lg'o % omeAs:*as bec: AWC (Dean Rowsell) esisuss xmo F. Bold /T. Colandrea L. R. Quintans R. Rademacher (w/o encls.)
. William T. Wow Office of Nuclear Material R. Wolf (w/o encls.)
Safety & Safeguards U.S. Nuclear Regulatory thenission Washington, D.C. 20555
Subject:
Docket 70-734: Plan for Obtaining Release of Certain Areas to Unrestricted Use.
(8 copies)
Reference:
(a) GA letter #696-6077 dated 11/16/84.
(b) GA letter #696-6085 dated 12/6/84.
(c) GA letter #696-6092 dated 12/21/84.
Dear Mr. Crow:
Enclosed are eight (8) copies of a plan prepared by GA Technologies Inc.
(GA) for obtaining approval to release certain portions of its site to unrestricted use. This plan is a revised version of a previously sub-mitted plan and supporting information (References a, b and c).
It has been modified in response to recommendations contained in an NRC draft evaluation of the oiiginal plan as well as to reflect GA's current strategy for rbtaining release following discussions with Messrs. Thomas and B. Brock / Segior U.
Further, the enclosed plan includes an updated schedule.
Your early approval of our criteria and plan are respectfully requested.
Thank you for your timely support in this regard.
If you have any questions or comments, please contact me at (619) 455-2823 Very truly yours, blW $. he w" Keith E. Asmussen Licensing Administrator KEA:he
Enclosure:
Plan for obtaining Approval to Release Discrete Areas to Unrestricted Use.
cc: Mr. John B. Martin, NRC, Region V (1 copy)
Department of Health, State of California (Attn: Ben Kapel) (1 copy) a.:.4"!0;9lpr-O
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PLAN FOR OBTAINING APPROVAL TO RELEASE DISCRETE AREAS TO UNRESTRICTED USE 1
l I.
Objectives The objectives of this plan are to provide:
l 1.
a description of sites to be released to unrestricted use 2.
identification of areas where levels of radioactivity approxi-mate or exceed the regulatory levels for release to unrestricted l
use (prior to decontamination) 3 methods to identify and quantify levels of radioactivity in
{
these areas j
4.
criteria for release to unrestricted use l
5 a procedure for a detailed final survey (after decontamination) to demonstrate that radioactivity levels in the areas meet the criteria for unrestricted release.
e e
I 1
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0 II. Summary of Plan Our plan for releasing the sites to unrestricted use is as follows:
1.
Identify the activities and their site location, and for each site provide:
a.
a brief history of the activity; b.
a characterization of any residual radioactive materials, including a listing of the principal nuclides, and estimates of their concentrations, and total quantity; c.
proposed disposition of contaminated materials; d.
schedule proposed dates for clean-up, survey and release to unrestricted use.
2.
Decontaminate any such location to:
a.
seet the license criteria for release of a facility or equipment to unrestricted use (Table 1) and/or
)
b.
remove any contaminated soil and/or vegetation until the residuals meet the NRC policy (SECY 81-576) option 1 cri-teria. This option assures that no individual is likely to receive en external radiation exposure at a rate greater
\\
than 10 ph/hr above background measured at one (1) meter above the surface or 20 millirea/yr to the lung or 60 milli-ren/yr to the bone.
See Table 2.
3 Provide NRC with the results of our final surveys and request NRC confirmatory surveys to independently verify that the spe-cified sites and their environs have been appropriately decon-taminated.
4.
Request 'NRC confirmation (s) that soils surrounding the removed underground radioactive material storage tanks listed above have been decontaminated to acceptable levels for release to unrestricted use.
This confirmation will be used as evidence the locations need not be reconsidered at the time of future decommissioning activity.
5 Request and obtain a license amendment indicating that the several acres which contained and surrounded the waste pond area, incinerator area, waste processing and storage areas and the adjacent canyon areas have been appropriately cleaned up and may be released to unrestricted use.
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TABLE 2 3
Criteria for Soil Decentamination at the GA Site j
Exposure Target other Existing Pathway Criteria Criteria or Ouidance External Radiation 10 pr/hr (whole body)
(35 mrem /yr)(,)
20 gr/hr indoor (b) EPA cleanup standard for Inactive Uranium Processing Site: 500 ares /yr-10 CFR 20; 170 ares /yr-FRC Guidance; 400-900 mrea/yr-Sur-geon General's Guidance for in-door exposure; 25 meem/yr-40 CFR 190.
Inhalation of Partic-1 mead /yr (1 ulates (lung, bone)
(20 arem/yr)g) 1500 ares /yr-10 CFR 20 25 ares /yr-40 CFR 190 3 mrad /yr (bone) 1 mead /yr (lung), 3 mrad (bone)
(60 arem/yr)
EPA Transuranic Guidance
- This value does not include background, the 35 ares /yr (realisti dose) includes shielding factor of 0.5 from building a residential c
home for general population and residence time 80 percent.
40 CFR Part 192 - Federal Register. April 22, 1980.
Based on quality factor of 20 as originally intended for alpha emitted free, the transuranic elements.
Designated in or derived from 10 CFR 20.
cwt 9
1Q } 00-p, i.eh 6
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6 b6 8
s' O
o III. Sites to be Released to Unrestricted Use The portions of GA's roughly 430 acre site to be released to unre-stricted use are several small localized areas plus a relatively large area associated with and surrounding the old waste processing area. Their locations are shown in Figures I, II, III and IV.
l The underground tanks being deactivated range from 750 gallons to 1000 gallons capacity.
These tanks served as holdup for radioactive liquid effluents from licensed fuel facilities and laboratories uti-lizing radioactive materials. Where needed, alternative above ground effluent storage is being provided to eliminate the under-ground tank monitoring and potential soil contamination problems.
Each of the tank sites are being treated as a potential highly lo-calized discrete source area.
(Reference Fig. I)
The Waste Processing Area (WPA) is an approximately six acre complex of discrete areas; an incinerator site, solar evaporation ponds, waste processing facility, associated storage yards, and other stor-age facilities.
Their locations are shown in Figure II.
The canyons below the WPA are a discrete area occupying approxi-mately one acre through which run-off frca the WPA goes.
Figure III shows the specific areas associated with and surrounding the Weste Processing Area. This relatively large portion of the GA site ( 80 acres) is the principal area to be released for unrestrict-l ed use. Figure IV shows this area in more detail and identifies the affected areas.
l A brief description of each of the above is given below:
A.
UNDERGROUND RADIOACTIVE LIQUID WASTE HOLDING TANKS 1.
Building 9 The Building 9 Tank is a 750 gallon poured-in-place rein-forced concrete tank. Ihe tank was placed under ground 28 years ago and is part of the Building 9 loading dock.
The i
tank was originally used to dilute non-radioactive acid wastes from a metal plating operation and was later con-t l
Verted to a radioactive liquid waste holding tank.
Ihe l
liquid collected in the tank was contaminated with thorius and depleted uranium.
At a later time it was used to hold-1 up liquid contaminated with mixed fission and activation l
products.
The tank has no history of leakage.
5
O e
v 2.
Building 2/540 The Building 2/540 Tank is a 1,000 gallon poured-in-place reinforced concrete tank. The tank was placed underground 28 years ago.
The tank was used to hold-up liquid waste contaminated with natural uranita and thorium from metallur-gical labs.
No mixed fission or activation products were used in these laboratories.
The tank has no history of leakage.
3 Building 2/307 The Building 2/307 Tank is a 1,000 gallon, poured-in-place, reinforced concrete tank.
The tank was placed under ground 28 years ago.
The tank was used to hold-up liquid from a shielded research laboratory contaminated with Cs-137, Co-60 and Sr-90.
The tank has a history of leakage.
4.
Building 31 The Building 31 Tank is a 1,000 gallon steel tank. The tank was placed under ground 23 years ago. The tank was used to hold-up hand wash water contaminated with enriched uranitan, thorium, and activation products from the HTGR Critical Facility. The tank has no history of leakage.
5.
Building 21 The Building 21 Tank is a 1000 gallon steel tank housed in a concrete cradle and surrounded by gravel. The tank was placed under ground 28 years ago and originally served the TRIGA Reactor Facility.
Until establishment of the Fuel Development and Research Laboratory (FDRL), the tank saw little use.
After establishment of the FDRL the tank was used to hold-up liquid contaminated with mixed fission and activation products.
The tank has no history of leakage.
6.
Building 37 The Building 37 Tanks are two one-thousand gallon steel tanks. The tanks were placed underground 20 years ago and serve the Building 37 Change Rooms. Only hand wash water contaminated with low levels of enriched uranium and thorium drains to the tanks. The tanks have no history of leakage.
6
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B.
Waste Processing Area:
1.
Solar Evaporation Ponds The Solar Evaporation Ponds consists of four sets of three 20' x 20' concrete ponds.one foot deep designed to contain contaminated liquid which in turn is evaporated by solar energy. Three sets of ponds were used for liquid waste containing enriched uranium and thorium. The fourth pond contained liquid waste contaminated with mixed fission and activation produces.
Through the years there was some cross contamination of the ponds necessitated by one or the other set of ponds being full when there was a need to place additional liquid waste in the ponds.
Sludge was periodically removed, packaged and disposed of to a lic-ensed radioactive waste disposal site.
2.
Radioactive Waste Incinerator Site The incinerator was located on a 20' x 20' concrete pad.
The unit was placed in operation in 1963 and decommissioned and removed in 1980.
Only the pad now csmains. The incin-erator was used to burn solid waste contaminated with en-riched uranium.
The incinerator was equipped with a parti-culate filter system.. The ash was periodically removed from the incinerator and analyzed for U-235.
3 Waste Processing Facility The Waste Processing Facility was constructed to process and package solid waste contaminated with enriched uranium and thorius primarily, and small quantities of mixed fis-sion and activation products, and to process and solidify acid waste contaminated with uranium and thoritan.
The waste processing facility was placed into operation twenty-eight years ago.
The surface of the packaging area was asphalt and the solidification area concrete.
4.
Upper Storage Yards The upper storage yards were constructed fourteen years ago with asphalted surfaces.
Only equipment properly packaged for storage, and solid waste packaged in accordance with appropriate regulations and awaiting disposal was stored in these areas.
i l
7
?
O O
5 Other Storage Areas An undergr,ound storage facility was located at the east end of the Weste ' Processing Facility.
The storage arez was con-structed by placing 10 inch diameter transite pipe under-ground.~ Slightly irradiated TRIGA fuel elements in capped and gasketed steel pipe containers were stored in the facil-ity from 1960 to 1982.
At the time of removal no measur-able contamination was detected on the external surface of the pipe containers nor inside the storage pipes.
The Byproducts Storage Building is a metal " Butler" build-ing located in the Northwest corner of the Weste Processing Facility.
Inside the building are:
a.
4 storage wells 13 feet deep by 3 feet in diameter with removable shield plugs, j
b.
6 alary susans" located behind a shield wall.
The
" lazy susan" can be lowered into individual storage wells 12 feet deep, and c.
two levels of shielded shelf storage. Liquid cesium chloride uma spilled in one of the storage wells several years ago.
A high level storage bunker for 55 gallon drums reading 50 mR/hr or greater at the surface is located in the south east end of the Waste Processing facility. The facility is a three aided open top enclosure constructed of burlap bags filled with a mixture of cement and sand and has an asphalt floor.
The drums contained solid weste contaminated with mixed fission and activation products.
C.
Canyon Area The canyon area is a one acre area adjacent to the solar evap-oration ponds, Weste Processing Facility and incinerator pad.
A spill in 1972 from the evaporation ponds contaminated part of this canyon area directly below the ponds with approximately 100 gas of enriched uranitan along with thorium, Cs-134, Cs-137, co-60 and Sr-90. Water runoff from the Weste Processing Facility also enters the canyon area.
D.
Principal Area to Be Released to Unrestricted Use The principal area to be released is shown on Figure III.
This area includes the Waste Processing Area (Item B above),
l the associated canyon area (Item C above), and areas of raw land (mainly hillsides and canyons) surrounding these areas.
8 i
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v IV.
Survey and Sampling Plan for Each Site A.
Underground Tank Removal Survey and Sampling Plan Prior to removal of any tank, the tank will be pumped and the contents sampled and analyzed. The inlet lines will be capped, placarded as appropriate, and a site map marked to indicate the location of the drain lines.
The flow chart for the removal cf the tank, the surveys to de-termine contamination levels, if any, as well as decontamina-tion and disposition is shown on the decision tree in Figure V.
The isotopic content for any contamination inside or outside of the tank will be determined. The total quantities will be made from dose rate measurements utilizing information from the meas-ured isotopic content.
After removal of the tank, the hole will be surveyed with an ap-propriate instrument and if no measurable activity above back-ground levels is detected, permission will be requested from the USNRC to backfill the hole. The decision tree for the ac-tivity associated with any contamination within the tank pit is also given on Figure V.
If levels above the acceptable crit'eria are detected, soil sam-ples will be collected, analyzed and evaluated.
If the levels are in excess of the release criteria for the identified iso-tope, the soil will be removed, packaged and shipped to a licensed land burial facility for disposal. In the event the quantity is economically not removable, the profile and total quantity of radioactive material will be determined and a dis-position scenario proposed to the USNRC.
B.
Weste Processing Area 1.
Survey Plan In the waste processing area the first part of a survey will be a " walkover" survey.- This will consist of random readings taken in the areas with a calibrated meter. This effort will locate any " hot" spots.
Readings from this survey will be recorded for any area exceeding 10 UR/hr above background at one meter above the surface.
Upon completion.of the " walkover" survey and with " hot" spots removed, the grid survey will be inaugurated.
A grid survey will be accomplished by using a 10' x 10' grid in the designated contaminated areas and a 30' x 30' grid in all other affected areas. Measurements at each grid inter-section at a distance of one meter above the surface will be made using a MicroR meter.
If the readings do not ex-coed 10 pR/hr above the background at one meter above the surface, the surveyor shall move to the next grid intersec-tion.
If the reading exceeds 20 WR/hr above background at 9
O o
one meter above the surface, a surface reading shall also be taken.
With a reading of 20 uR/hr or greater at one meter above the surface, and the surrounding Il grid area average ex-coeding the 10 pR/hr above background at one meter above the surface, that point shall be considered for soil sam-pling. See section on Soil Sample Plan for. details.
Survey each of the affected areas as noted below; Solar Evaporation Ponds 10' X 10' grid Radioactive Weste Incinerator Site 10' I 10' grid Waste Processing Facility 10' I 10' grid Upper Storage Yards 10' X_10' grid Other Storage Areas 10' X 10' grid C.
Canyon Area 1.
Survey Plan The canyon area is defined as that area adjacent to and below the solar evaporation ponds, Weste Processing facil-ity and incinerator pad. This. area is shown in Figure IV.
Because of the activities previously described for the waste processing areas, it is anticipated that there are several locations at which some contamination is expected.
As was done in Waste Processing Area, the first part of the canyon survey will be a walkover survey.
It will be done in an identical inanner as that described for the Waste Pro-cessing Area.
Upon completion of this n rvey and its asso-ciated decontamination, a grid survey will bee performed.
It will be performed in the same sienner as the Weste Pro-cessing area, except that the grid description is as fol-lows.:
Spill area below ponds 10' x 10' grid Other affected areas 10' x 10' grid Canyon floor 30' lengthwise along central axis 10' lateral, parallel to central axis D.
Land Surrounding Weste Processing and Canyon Areas Land surrounding the affected areas described above in Sections B and C but within the boundaries of the principal area for release to tmrestricted use, shall be surveyed for external radiation by a " walkover" survey at 30 foot intervals.
crids will not be staked out unless readings >10 pR/hr above back-ground at 1 meter above the surface are detected.
If this level is exceeded, the location will be identified as an af-facted area and characterixed.
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E.
Soil Sample Plan 1.
Prior to Clean-up After the centaminated (affected) areas have been ide..ti-fied. soil samples will be taken to characteri:e the site.
Core samples will be obtained in the Solar Evaporation Ponds, the spill area below the ponds,'the canyon floor and the radioactive waste incir. orator site and other specific areas where there is a high potential for contaminatien to migrate downward into the soil strata or transport into the soil by erosion.
o Collection a.
he surface vegetation (brush and weeds) will be removed by cutting off at ground level, not up-rotted.
b ". Surface samples (0-1") will be collected; approxi-mately 2 kilograms of soil sample.
c.
A composite soil sample 1"-6" or 1"-12" will be col-lected based on the area and estimated depth of con-tamination.
d.
If subsurface soil contamination is found, then ad-ditional samples (e.g. corea samples) will be taken at sufficient depths to provide an estimate of the extent of contamination.
o Preparation a.
Me soil samples will be free of vegetation and rocks.
b.
he samples nd.11 be dried to remove moisture.
c.
he sample will be ground to a fine powder with no
" clumping" (clumping would be due to excess mois-ture), or if it can be demonstrated with adequate data that there is no significant difference between the re-sults obtained with samples that have been ground to a fine powder and samples that have not been ground, then subsequent analyses will not require samples to be ground.
Samples that are not ground to a fine powder will be crushed and mixed to elimi-nate clumping and to hcmogenize.
11
O e
o Analysis The samples will be analy:ed by gamma ray spectroscopy, gross alpha, gross beta DNAA or chemical analysez per-formed to written procedures.
The option to log the core hole, identify and quantify the nuclides present in-situ with a gamma spectrometer and NaI detector or equivalent instrianent may be used in lieu of counting the core samples.
j 1
2.
During Clean-up During the decontamination phase (removal of soil with con-tamination above Option 1 target criteria) soil samples will be collected and the locations will be marked and iden-tified on a map. The first foot of soil will be prepared, and analyzed as described above to:
a.
Verify correlation between the microR/hr readings and the soil radionuclide concentrations or b.
Check compliance with the. inhalation criteria in areas where correlation may not exist.
If results indicate contamination levels above the Option 1 criteria, additional decontamination will be conducted in order to meet the target criteria (see Section Y).
t After' Clean-up
\\
3 Upon completion of required decontamination, soil samples will be collected as follows:
a.
Ih areas where the microR/ hour readings are the control-ling criterion (i.e., where a correlation betwesn yR meter readings and the results of soil sample analyses has established that both.the inhalation and direct radiation pathway limits are met when using the direct reading), random sampling of 55 of the 30' x 30' grids will be conducted.
b.
In all other affected areas, samples will be taken as follows:
Representative soil samples shall be collected at each grid (30' x 30') from the first inch (1") of soil.
The samples will be prepared and analyzed as described above.
12
1 O
O V.
Target Criteria for Unrestricted Release A.
facility & Equipment Table 1 is taken from USNRC's criteria for releasing facilities and equipment to unrestricted use.
It has been incorporated into our SNM-696 license.
This table will be used for releas-ing process equipment or buildings to unrestricted use.
Ponds,
tanks, etc. will be treated as process equipment.
The above criteria will not be utilized for scils.
)
B.
Direct Radiation External radiation (gamma dose rate in air one meter above ground level) shall not exceed 10 p R/hr above background for a diffuse source area (a contaminated area greater than 30' x 30') and shall not exceed 20 pivhr above background for a discrete area (a contaminated area smaller than 30' x 30').
C.
Inhalation Pathway Table 3 contains values of soil contamination (pCi/ga) which if residing on the surface and could be inhaled would not lead to an exposure exceeding the Option I acceptability limit.
Soil contaminations above these Table 3 values may be acceptable under unusual circumstances but only if a specifically analyzed intrusion scenario shows that any individual will not be ex-posed to radiation levels greater than those appropriate for NRC/ EPA Option I.
D.
Ingestion Pathway The GA site is located wit})in a semi arid region zoned for light industry and Research and Development.
The area is not, nor will likely be, allowed any residential or agricultural land usage.
There is no potable water on the site or. its en-virons. A brackish water table is approximately 275-300 ft deep at about the same level as the nearby salt water backwater and marshes.
Therefore the pathway for ingestion of any resid-ual contamination via any food or water is highly improbable.
Ho= wever, vegetatior. (brush, weeds, etc) removed from the GA site for unrestricted disposal could possibly enter the in-gestion pathway.
Therefore the contamination levels of such vegetation must satisfy the target criteria for ingestion exposure (as well as the target criteria for direct radiation and inhalation exposure).
The target criteria for food ingestion exposure is 30 mrom/ year to the bone (NRC Policy Issue SECY-81-576).
The dose commit-ment resulting from ingestion (vegetation, beef, milk) of radio-nuclides from centaminated vegetation are shown in Table 4.
These values are based upon a unit concentration of 1 pCi/ gram of each radionuclide in the vegetation.
13
i O
O E.
Summary of Limiting Concentrations for Direct Radiation and Inhalatierr Dose Limits Table 5 summarizes the derived limiting concentrations of various groups of radionuclides for the compliance of the direct radiation and inhalation dose limits. Meeting the target criteria in Table 5 will indicate that the residuals satisfy the Option I acceptability criteria, e
e 14
l2 1-o o
TABLE 3 Individual Concentration in Soil Resulting in an Annual Inhalation Dose of 20 mrem to the Lung (
and 60 mrem to the Bone' !
Solubility Derived Concentration (pCi/g)
Radionuclide Classification Lung (20 mrem)
Ibne (60 mrem) 1.2x10"3 U-238 Y
35 2
U-238 W
3 2x10 3 9x10 g
3 U-238 D
1.9x10 1.2x10 4
U-235 Y
35 1.2x10 2
3 3 9x10 U-235 W
3 2x104 3
U-235 D
1 9x10 1.2x10 U-234 Y
30 1*0*10 2
U-234 W
2.8x10 3.6x10 4
3 U-234 D
1 7x10 1.1xto 2
Th-232 Y
35 2.6x10 2
Th-232 W
3 3x10 1.0x10 3
3 Ra-228 W
3 3x10 2 9x10 33x10l 3
1.8x10 Th-228 Y
20 2
Th-228 W
1 3x10 1.6x10f Co-60*
Y 1.2x10 co-60 W
1.2x10 5.8x10 5
6 Cs-137" D
9 6x10 1.8x10 5
1.8x10l Sr-90" Y
2.6x10 j
Sr-90 D
1.6x10 2.8x10 (I Pulmonary lung (570 gn); consistent with EPA's Transuranics Guidance.
Bone means osseous tissue, (5,000 ga); consistent with EPA's Transuranic Guidance.
3)The daughters of Th-228 and Ac-228 do not contribute significantly to the inhalation dose because of their comparatively short half-lives.
(
Solubility classifications are based on ICRP-30.
15 4
2 O
e 6
TABLE 4 Dose Commitment Resulting from Ingestion (Vegetation, Beef, Milk) of Radio-nuclides from Contaminated Vegetation (brush, weeds, etc.).
Figures Based on a Unit Concentration of 1 pC1/g of Each Nuclide in the Vegetation.
Radionuclides Bone Dose (nren/yr)
U-238 1.9E-0 U-235 1.9E-0 U-234 2.2E-0 Th-232 2.1E-0 Th-230 2.0E-0 Th-228 4.0E-1 i
Ra-228 4.5E-0 Ra-226 8.9E-0 Sr-90 6.1E-0 Cs-137 2 3E-1 Pu-239 5.6E-2
)
(1)
Reference:
NRC's Docket No.70-820 - United Nuclear Corporation Resources Company " Soil Decontamination Criteria for the Decommissioning of the UNC's Facility." Scrap Recovery Junction, Rhode Island.
16 L
1
(
b h
i i..
TABLE 5 l
l Derived Limiting Concentrations For Various Groups of Radionuclides Derived Limiting Concentration (pCi/gm)
Direct II Inhalation Radia~ ion c
Radionuclide Lung (20 meem)
Bone (60 mrem)
(10 pR/hr)
U-238. U-234 (Y) 35 2
U-238. U-234 (W) 3 2x10 2 -
8.0x10 U-238. U-234 (D)
High-enriched uranium
~
U-234. U-235 (Y) 30 2
i U-234. U-235 (W) 2.8x10 2
8.0x10 U-234. U-235 (D)
Natural Thorium 10 Th-232. Th-228 (Y) 10 1h-232. Th-228 (W)
Cobalt 8
Cesium 15 l
Cs-137 (D)
Sr-90 (Y) 1.8x10 Sr-90 (D) 2.8x10 (1) GA prefers to use an instrument (microReeter) to demonstrate compliance of 10 V R/ hour above background at one meter for diffuse areas.
l 17
1 O
o VI.
Compliance With the Target Criteria Given below are the target criteria for direct radiation and inhala-tion pathways. Both criteria must be met prior to release of the i
area for unrestricted use.
I A.
Direct Radiation The direct radiation level of 10 p R/hr above background is in-tended as a target criterion for open land cleanup.
The dose 10 1 will be measured using cahibrated micro R meters accurate enough to differentiate background.
Upon completion of any required decontamination, a final survey.
will be made of the waste procensing and canyon areas.
The pur-pose of this survey is to verify all significant contamination has been removed and the area meets the target criteria.
To demonstrate compliance with the direct radiation limit, the affected areas will be divided into grids about 30' x 30' for surveying purposes.
In ords to meet the target criterion, the following conditions have to be met:
External radiation (gamma dose rate in air one meter above ground level) shall not exceed 10 WR/hr above background for a diffuse source area (a contaminated area greater than 30' x 30') and shall not exceed 20 p R/hr above background for a discrete area (a contaminated area smaller than 30' x 30').
Land surrounding the affected areas but within the boundaries of the principal area for reles:se to unrestricted use shall be surveyed for external radiation by a " walkover" survey at 30 foot intervals.
B.
Inhalation of Particulates Table 3 summarizes the derived soil contamination limits for each inhaled radionuclide, which results in a committed dose of 20 ares /yr to the lung and 60 m em/yr to the bone.
It is noted that Table 3 noil limits are for individual radionuclides.
If a mixture of these radionuclide.s exists in soil, the following formula will be applied to show compliance:
the sua of Ci/Li < 1 where Ci a the av'erage soil con' entration of radionuclide i, and Li the derived maximum noil limit for radionuclide i (from Table 3).
1 18
M h
To demonstrate compliance with the dose limits establianed for the inhalation pathway, the following has to be met:
Representative soil samples shall be collected at each grid (30' x 30') from the first inch (1") of soil and analyzed for the various isotopes. The concentrations of isotopes can be averaged by any four adjacent grids to demonstrate compliance with the target criteria given in Table 3 The derived concentrations in Table 3 also apply to subsurface soil contamination.
Therefore, subsurface
- soil samples will also be collected.
After decontamination has resulted in the above condition being met for surface soil, compliance with the subsurface requirement will be demonstrated by analyzing a random 55 of the subsurface soil samples.
If a subsurface random sample exceeds the limit, the four ad-jacent 30' x 30' subsurface samples will be analyzed and the results averaged.
If the average is below the limits, the j
inhalation dose target criteria will have been met.
If the i
averaged result is above the limits, further decontamination will be conducted.
l In these affected areas idtere it can be demonstrated with ade-quate data that meeting the 10 pR/hr above background limit will also meet the inhalation dose limit, direct radiation measurements will be used to demonstrate compliance for both pathways.
In this case, soil samples of five (5) percent of the grids will be randomly collected and analyzed to confirm compliance.
C.
Ingestion of Vegetation (Brush, weeds, etc )
i Table 4 summarizes the derived vegetation contamination limits for each ingested radionuclide which results in a committed dose of 30 area / year to the bone. The vegetation contamination limits given in Table 4 are for individual radionuclides.
If a mixture of these radionuclides are present in vegetation, the
~
following formula will be applied to demonstrate compliance:
the sum of C1/Li i 1.0 where Ci : average concentration of radionuclide i in vegetation Li a derived limit for radionuclide i in vegetation (from Table 4)
'" subsurface soil sample" refers to a soil sample taken starting at a depth of 1" and extending to a depth of 6" or l' depending on the area and estimated depth of contamination.
19
s
,/
2 e
f
Disposition of contaminated Soil and Vegetation l
VII.
Soil Soil with contamination levels above.the Option 1 target criteria d
will be appropriately packaged and shipped to an authorize radioactive waste disposal facility.
Vegetation _
Vegetation (brush, weeds, etc.) with contamination levels above th target criteria for external radiation or inhalation ex l
packaged and shipped to an authorized radioactive waste disposa facility.
Vegetation with contanination levels below the target criteria for external radiation, inhalation exposure and ingestion exposure may I
be removed from the Gi site for unrestricted disposal, e.g. sent to
(
a local land fill facility.
l l
l l
l 4
i 1
- 0 20 le l
u
~
,P Letter from NRC dated November 26,1985 signed by W.T. Crow approving GA's y;;
1985 Decommissioning Plan t
w 1
Irlvl7r5o6Jwlt$'h a
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UNITED STATES
[
g NUCLEAR REGULATORY COMMISSION
-r'i h yp a
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WASHING TON, D. C. 20666 g,
gh / g g
- p R Luaflth 91 WV 2 61995 FCUP:NK
' {l T-70-734 eC.
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a GA Technologies, Inc.
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't ATTN: Dr. Keith E. Asmussen C
(
Licensing Administrator P. O. Box 85608 s
San Diego, CA 92138 Gentlemen:
We have reviewed your plan dated October 1,1985, for decontaminating portions of your plant so that they can be deleted from your Special ~ Nuclear Materials License No. SNM-696 and released for unrestricted use.
We find your plan acceptable (see Evaluation Report enclosed).
In order to remove these portions from your license, it will be necessary for you to submit an amendment application which includes your survey results.
Sincerely, W. T. Cr, Ac i ief Uranium Fuel Licensing ranch ivision of Fuel Cycl and Material Safety, NMSS
Enclosure:
Evaluation Report cc w/ encl: Mr. Don Honey State of California Departme..c of Health Services Radiological Health Licensing 744 P Street Sacramento, CA 95814 7 j + () f U-
,;.)l)
/
%j UNITED STATES 8
NUCLEAR REGULATORY COMMISSION o
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wasHWGTON, D. C. 20005 k,*****
NOV 2 61985 FCUP:EYS DOCKET N0: 70-734 LICENSEE:
GA Technologies, Inc. (GA)
FACILITY:
Fuel Fabrication Facility, San Diego, California u h
SUBJECT:
EVALUATION OF.GA's PROPOSED DECONTAMINATION PLAN,'
Background
By letters dated November 16, December 6, December 21, 1984, and October-1,
)
1985, GA Technologies, Inc. (GA), inforined the Nuclear Regulatory Conunission o J
(NRC) that GA had decided to decontaminate a. portion of the plant so that it 1 e can be deleted from the license and released for unrestricted use. The principal' areas to be released include the waste processing area, the associated canyon area, and raw land (mainly hillsides and-canyons) surrounding these areas.
In addition, GA plans to decontaminate the underground radioactive liquid storage tanks to an extent that they can be released for unrestricted use; however, the above areas are still within GA's current licensed operating area. Although these.
.j areas will be cleaned up to the criteria suitable for unrestricted release in the-future, they will not be deleted from the GA license. In connection with the above i
activities, GA by letter dated October 1,1985, submitted a revised decontamination plan reflecting (the updated information,from the original plan. - The revised.
plan contains:
- 1) a description of areas to be decontaminated, (2) identification of areas where levels of radioactivity may exceed the regulatory levels for release to unrestricted use prior to decontamination, (3) criteria for release to unrestricted use, (4) methods to identify the quantity of radioactivity in these areas, and (5) decontamination schedule and procedure for detailed final survey (after decontamination) to demonstrate coupliance with the criteria for unrestricted use.
l Description of Areas to be Decontaminated The following provides a general description on the various locations where decontamination activities are to be conducted. GA's objective is to cleanup these areas to the proposed criteria suitable for unrestricted use.
A.
Underground Radioactive Liquid Waste Holding Tanks 1.
Building 9 The Building 9 Tank is a 750-gallon, poured-in-place reinforced concrete tank. The tank was placed underground 28 years ago and is part of the Building 9 loading dock. The tank was originally used to dilute non-radioactive liquid waste. The liquid collected in
?fl3V/O Y
,. NOV 2 61985 the tank was contaminated with thorium and depleted uranium.
At a later time, it was used to hold liquid contaminated with mixed fission and activation products. According to GA, the tank has no history of leakage.
2.
Building 2/540 The Building 2/540 Tank is a 1,000-gallon, poured-in-place reinforced.
concrete tank. The tank was placed underground 28 years ago.
The tank was used to hold liquid waste contaminated with natural uranium and thorium from metallurgical labs. No mixed fission or activation products were used in these laboratories. According to GA, the tank has no history of leakage.
3.
Building 2/307-The Building 2/307 Tank is a 1,000-gallon, poured-in-place reinforced concrete tank. The tank was placed unrNrground 28 years ago. The tank was used to hold liquid from a shielded research laboratory contaminated with Cs-137, Co-60, and Sr-90.
According to GA, the tank has history of leakage.
4.
Building 31 The Building 31 Tank is a 1,000-gallon steel tank. The tank was placed underground 23 years ago. The tank was used to hold hand wash water contaminated with enriched uranium, thorium, and t-activation products from the HTGR Critical Facility.. According to GA, the tank has no history of leakage.
5.
Building 21 The Building 21 Tank is a 1,000-gallon steel tank housed in a concrete cradle and surrounded by gravel. The tank was placed underground 28 years ago and originally served the TRIGA Reactor Facility.
Until establishment of the Fuel Development and Research Laboratory (FDRL), there was little use for the tank. After establishment of the FDRL, the tank was used to hold liquid contaminated with mixed fission and activation products. According to GA, the tank has no history of leakage.
6.
Building 37 The Building 37 Tanks are two 1,000-ga11on steel tanks. The tanks were placed underground 20 years ago and serve the Building 37 Change Rooms.
Only hand wash water contaminated with low levels of enriched uranium and thorium drains to the tanks. According to GA, the tanks have no history of leakage.
i
~3~
NOV 2 61985 The locations of these underground tanks are shown on the site map in GA's submittal (Appendix A, Figure 1).
B.
Waste Processing Area-y 1.
Solar Evaporation Ponds The Solar Evaporation Ponds consist of four sets of three 20' x 20' i
, concrete ponds, one foot deep, designed to contain contaminated
- 3r liquid which in turn is evaporated by -solar energy. Three sets of._
-ponds were used for liquid waste containing enriched uranium and 3i thorium. The fourth pond contained liquid waste contaminated with.
)
mixed fission and activation products.' Through the years -when.
there was a need to place additional liquid waste in the ponds,.
t there was some cross contamination of.the ponds if other ponds were,
n-
,, full. Sludge was periodically 3 removed, packaged, and shipped to a ilicensed radioactive waste disposal site.
- 2.
Radioactive Waste Incinerator. Site 4
The incinerator was located on a 20' x 20' concrete pad. The unit was placed in operation in 1963 and decommissioned and removed in
. 1980. Only the pad remains. The incinerator was used to burn
~
t solid waste contaminated with enriched uranium and was equipped with a particulate filter system. The ash wat periodically removed from the incinerator and analyzed for U-235.
3.
Waste Processing Facility The Waste Processing Facility was constructed to process and package solid waste contaminated with primarily enriched uranium and thorium, small quantities of mixed fission and activiation products, and to process and solidify acid waste contaminated with uranium and thorium.
j The waste processing facility was placed into operation 28 years ago.
)
The surface of the packaging area was asphalt and the solidification j
area concrete.
i 4.
Upper Storage Yards The upper storage yards were constructed 14 years ago with asphalt surfaces.
Only equipment properly packaged for storage and solid waste packaged in accordance with appropriate regulations and awaiting disposal were stored in these areas.
t
_4 NOV 2 61985 5.
Other Storage Areas An underground storage facility was located at the east end of the Waste Processing Facility. The storage area was constructed by placing 10-inch diameter transite pipe underground. Slightly irradiated TRIGA fuel elements in capped, steel pipe containers were stored in the
- facility from 1960 to 1978. According to GA, at the time of removal, no measurable contamination was detected on the external surface of the pipe containers or inside the storage pipes.
The yard was abandoned in 1979.
The Byproducts Storage Building is a metal " Butler" building located o
in the northwest corner of the Waste Processing Facility., Inside the building are:
l a.
Four storage wells 13 feet deep by 3 feet in diameter with removable shield plugs,
-b.
Six " lazy susans" located behind a shield wall. The " lazy susan" can be lowered into individual storage wells 12 feet deep, and; 1
l c.
Two levels of shielded shelf storage. Liquid cesium chloride l
was spilled in one of the storage wells several years-ago.
L A high-level storage bunker for 55-gallon drums reading-50 mr/hr or greater at the surface is located in the southeast end of the Waste Processing l
Facility. The Facility is a three-sided, open top enclosure constructed of burlap bags filled with a mixture of cement and= sand and with an asphalt floor.
The drums contained solid waste contaminated with mixed fission and activation products.
l C.
Canyon Area l
The Canyon Area is a 1 acre area adjacent to the Solar Evaporation Ponds, Waste Processing Facility, and incinerator pad. According to GA, a spill in 1972 from the evaporation ponds contaminated part of this Canyon Area l
directly below the ponds with approximately 100 grams of enriched uranium and thorium. Water runoff from the Waste Processing Facility also enters the Canyon Area.
The locations of the above areas are shown in GA's submittal (Appendix A, i
Figures 1 and 2).
The principal area to be released for unrestricted use is shown on Figure III of Appendix A.
This area includes the Waste Processing Area (Item B above),
the associated Canyon Area (Item C above), and raw land (mainly hillsides and canyons) surrounding these areas.
l
)
. NOV 2 61985 Since the small localized storage tank areas are still within the plant's licensed operation, they will be decontaminated but not released at the present time for unrestricted use.
Evaluation of GA's Decontamination Plan i
A.
Decontamination Criteria for Unrestricted Releases 1.
Facility and Equipment e
The NRC has established guidelines for the decontamination-of
,p 4
facilities and equipment prior to release :for unrestricted use.
<W The guidelines provide acceptable surface contamination levels for t m.m byproduct, source, or special nuclear materials. The guidelines:
which are applicable to GA's ' decontamination activites for facility >-
H and equipment, tre shown in Table 1 Appendix A, of GA's submittal.-
2.
Contaminated Soil 1
The NRC issued a Branch Technical Position. setting forth soil y
decontamination limits for unrestricpive. releases of soil.
g
. contaminated with uranium or thorium. These soil limits shall j
C. - be applied to the GA site.
However, there is other radionuclide ee contamination involving fission product or activated products at the o -o GA site. The staff provided GA with cleanup criteria using the dose a
' s P limits established in Option l'in'the Branch Technical Position for mc w all radionuclides involved. The staff has evaluated the derived soil limits for various radionuclides as suumerized in the Tables of GA's. <
.W submittal (see Appendix A) and found that they are acceptable.
B.
Decontamination Plan In Appendix A, GA has outlined the procedures for the proposed decontam-ination activities. This includes characterization of the decontaminated areas, proposed waste disposal to meet released criteria, decontamination schedule, radiological survey plan during cleanup and after cleanup, method to demonstrate coupliance with the criteria for unrestrictive release, and the quality assurance plan. The staff has evaluated the above procedures and found that they are acceptable.
I W. J. Dircks, Executive Director of Operations, NRC, memorandum to the Commissioners, " Disposal or Onsite Storage of Residual Thorium or Uranium from Past Operations" presented as a Branch Technical Position from the Uranium Fuel Licensing Branch, October 5,1981.
I t'
I NOV 2 6 585 Conclusion For the proposed GA decontamination activities, GA has provided acceptable
.j criteria for the decontamination of some portion of their site such that they can be released for unrestricted use. The staff has evaluated the overall
.J decontamination plan submitted by GA and found it acceptable. Therefore, the
' staff recommends that the GA plan be approved.
ret.
E. Y. Shum Uranium Process Licensing Section Uranium Fuel Licensing Branch Division of Fuel Cycle and Material Safety, NMSS
- Approved by:
fg W. T. Crow, Acting Chief i
f
Enclosure:
Appendix A (GA Technologies ltr dtd 10/01/85) 1 1
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4 I
l k
l NRC Polley Issue SECY-81-576 dated October 5,1981 i
1 SC p ney
%~
- )
3 3
2 g October 5, 1981 SES-al-576 POLICY ISSUE (Information)
For:
The Ccamissioners.
From:
William J. Dircks Executive Director for Operations Suoject:
DISPOSAL OR ONSITE STORAGE OF RESIDUAL THORIUM O URANIUM (EITHER AS NATURAL ORES OR WITHOUT DAUG PRESENT) FROM PAST OPERATIONS Purcose:
To inform the Commission of the adoption of a Branch Technical Position for application by the Uranium Fuel Licensing Branch.
Discussion:
Some of the sites formerly used for processing thorium and uranium are known today to be contaminated with residual radioactive materials.
In many cases, the total amount of contaminated soil is large, but the activity concentrations of radioactive materials present are sufficiently low as to justify their
. disposal on privataly owned lands or storage onsi a rather than transport them offsite to a licensed radioactive materials disposal (commercial) site.
In many instances, packaging and transporting these wasteis to a licensed disposal site would be too costly and not justified from the'stsndpoints of risk to the public health or cost-benefit. Fyrther. core, because of the high volume of 'these wastes, limited commercial waste disposal capacity, and restrictions placed on receipt of long-lived wastes at commercial sites, it is not presently feasible to disease of these wastes at c::mmercial low-level wasta disposal sites.
Effective January 13, 1981, NRC regulations in 10 CFR 20 " Standards for Protection Against Radiation" were amended (45 FR 71761-71762) to delete Section 20.204 which provided general authority for disposal of radioactive matarial by burial in soil..
Under the amended regulations licensees must apply for and cotain soecific NRC approval to dispose of radioactive matarials in tais manner unoer tne provisions of 10 CFR 20.302.
CONTACT:
d R.G. Psge NMSS
.Q-/4f1k2-945V/
42-74309
1 1
The Commissioners Enclosure 4 is a Federal Register notice wnich we plan to have published on tnts matter.
b'x N William J. Dir:ts Executive Direc'Jr for Operations
Enclosures:
1.
Contaminated Site Cases Presently. Pending 2.
Summary of Disposal and Storage Options 3.
Calculation of Allowable Concentrations for Four Disposal Options 4.
Federal Register Notice -
e e
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1
's Contaminated Site Cases Presently Pending Site Disposal or Storage Option that Ma v Aeolv Stepan Chunical Company Maywood, New Jersey Z,2' (Tnorium ore residues)
Kerr-McGee Corporation
~5 West Chicago, Illinois i
(Thorium ore residuas)
McGaan Chanical Company 4
Newburg Heights, Ohio (Depleted uranium)
Amax Corporation a or 5 Parkersburg, West Virginia (Thorium oxide mixed with zirconium) totter Corporation (former owner) 5 Latty Avenue St. Louis, Missouri (Uranium residuas)
Velsical Chemical (formerly Michigan Chemical) a St. Louis, Michigan (Uranium, thorium and radium are wastes Except for a few hot spots that will need to be removed from the site, the contamination on adjoining property west of Highway 17 appears to fall under options 2 or 3.
e Inclosure 1
),.
'i SulWARY OF DISPOSAL AND STORAGE OPTIONS The following is a suissary of the disposal and storage options which staff intends to apply. The maximum concentrations permitted under each discosal option are tabulated on the last page of this enclosure.
1.
Disposal of acceptably low concentrations (which meet EPA cleanup standards) of natural thoHus, depleted or enMehed uranium, and uranium cres with no restMction on buMal method.
The concentrations specified for this option are believed acceptably low without restMeting the method of burial.
It is expected, however,
- tha currently licensed operations will be conducted in such a manner i
as to minimize the possibility of soil contamination and'when such occurs the contamination will be reduced to levels as low as reasonably achievable.
2.
Disposal of certain low concentrations of natural thoHum and depleted or enriched uranium (with no daughters present) when buried under prescribed conditions with no land use restrictions and no continuing
{
NRC 1icensing of the matarial.
Under this option, buMal will be pensitted only if it can be demon-strated that the buMed nataMals will be stabilized in place and not be transported away from the sita. Acceptability of the site for disposal
. will depend on topographical, geological, hydrological and meteorological characteristics of the site. At a minimum, burial depth will be at least four feet below the surface.
3.
Disposal of low concentrations of natural uranium ores with daughters in equilibrium, when buMed under prescribed conditions in areas :oned for industMal use, and the recorded title documents are amended to stata that the specified land contains buMed radioactive materials and are conditioned in the manner acceptable under sata law to impose a covenant running with the land that the specified land may not be used for residential building. (There is no continuing NRC licensing of the mataMal.)
Disposal will be approved if the buMal cMtaMa outlined in option 2 (including buMal at a minimum of four feet) are met.
Under unis option, no residential building would be. permit ad over land where natural uranium are residues have been buried.
0 4
2-4.
Disposal of land-use-limited concentrations of natural thorium, natural uranium and depleted.or enHched uranium wnen buried under prescribed conditions in areas zoned for industrial use and the recorded titl documents are amended to state that the land contains bur materials, and are conditioned in the manner required by state law to impose a covenant running with the land that the land 11) may not be excavated below stated depths in specified areas unless cleared by appropMate health authorities, (2) any not be used. for residential or (There is no continuing NRC licensing of the disposal Criteria for disposal under these conditions is predicated upon the assumption that intentional intrusion.is less likely to occur if a warning.
is given in land documents of record not to excavate below buHal de in specified areas of land without clearance by health' authorities;.pths construct residential or industrial buildings on the sita; and not to use not to specified areas of land for agricultural purposes.
to impose these land use restMetions.the buHal criteria in op 5.
availability of an appropMata disposal sita. Storage of licensed When concentrations exceed those specified in option 4, long term disposal under the provisions of 10 CFR 20.302.other than at a licensed dispo In such cases, the tnorium and uranium may be peneitted to be stored onsite under an NRC license until a suitable method of disposal is found.
radiation doses not exceed those specified in 10 CFR Part 20 and tained as low as reasonbly achievable.
I i
g S
l,
SUMMAAY OF MAXIMUM CONCENTRATIONS PERMITTED UNDEj Discosal Ootions Kind of Material J'
2[pC1/gn)8 d
3 4
Natural Thorium (Th-232 + Th-228) 10 50 500 with daughters present and
, in' equilibria i
Naturall urania (U-238 + U-234) with daughters pressat and 10 40 200 in equ111 brim Depleted Urania o soluble 35 100 1000
- o. Insoluble 35 300 2000 Enriched Uranta o Soluble 30 100 1000 o Insoluble 30 250 2500 1
a Based on EPA cleanup
- standards.
b Concentrations based on Ifmiting individual doses td 170 mram/yr.
Concentration based on limiting equivalent exposure to 0.02 working c
~
level or less.
y d
Concentrations based on limiting individual doses to 500 aren/yr and, in case of natural uranium, limiting exposure to 0.02 working level or less.
i l
=
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7 CALCULATI"4 0F ALLOWA8LE CONCENTRATIONS FOR 40R OISPOSAL OPTICNS I
Introduction The following sections provide dose calculations for esa611shing limi-ing concentrations of thoHun and uranium for disposal under four discosal options. The dose tabulation includes vaMous significant pathways to man resulting from the buHal of radioactive wastes containing natural thorium.
natural uranium, enHched uranium, or depleted uranium. With ' 2ese l
tables. the concentratton listt of a radionuclide or af xture of raaienuclices in vaMous types of wastes to be disposed ~of by these options"can se calculated. Tables 7 and 8 susinaHze the concentration Itaits of sose typical wastes for each option of disposal. Concentration limits involving other mixtures of these radionuclides can be' calculated by the use of these tables.
~
II
. Radioactive Characteristics of the Nuclides A.
ThoH us The natural thoHun decay chain and the characteHstics of each nuclide are susesHzed in Table 1.
The parent Th-232 generally exists in nature with its daughters which are in radioactive equilibrium with the parent. However, in some t;ypes of waste such as from processing of thoHus ore,' the puMfied metal (Th-232 and Th-228) is removed as the
~'
product and the daughter products can be vaMous wastes. Therefore, 1
it is inmortant to understand the history of the operation and how the
?
wastes are generated.
l As shown in Table 1 Th-232 and its daughters consist of alpha, beta.
and gassa emitters. The alpha eritters will constitute a significant pathway for dose to man through inhalation and ingestion. The cMtical organs in the inhalation and ingestion pathways are the lung and the bone depending on the solubility classification of the nuclide. The j
gamma emitters will contMbute external radiation (whole-body) dose to 3
man. Therefore, the pathways for dose to man to be considered for i
natural thoMus are direct radiation inhalation and ingestion.
1 1
O I
I i
i
Table 1 Thorium Chain
. Princioal Radiations fl4eV)a Isotone T1/2 Oaughter M ona" Beta-co - f 10 Th-232 1.405x10 y Ra-228 4.00; i
Ra-228 a 5.75y Ac-228 0.01 0 Ac-228 6.13h
, Th-228 0.376 0.91 5 Th-228 1.9131y Ra-224 5.40 0.002 Ra-224 3.66d An-220 5.67 0.009 Rn-220 55.Es Po-216 6.29 Po-216 -
0.15s Pb-212 6.78 Pb-212 10.64h 51-21 2 0.100 0.117 Bi-212 60.55m T1-208 6.04(35.93%)
0.003 2
l Po-212
-(64.07%)
, 0. 71 7 0.281 T1-208 3.07m Pb-208 0.5 61 2.37 Po-212 3.05x10'I s Pb-208 8.78
~
~~
(stable)
" Branches <1% not included.
b Average enery.
t
- Total Enery estttad per disintegration.
Q l
I
-3 B.
Uranium The uranium chains including U-238 and U-235 are given in Tables 2 and 3.
For uranium that has been processed througn the milling i
operation, the only nuclides of importance in the dose calcu.lations are U-238 ~ and U-234. The buildup of daughters in the separated uranium is not important, i.e., neither the Th-230 nor the~Ra-226 could reach 105 of equilibrium with the separated uraniusuntil greater than 10,000 yea'rs. The U-234 usu' ally stays in equilibrium with the U-238 parent with the equilibrium between U-238 and Pa-234
]
reached in a matter of months.
In normal processing of uranium ore, i
the process separates both the Th-230 and~ Ra-226 to the same stream of waste; then both nuclides are in secular equilibrium.
If in the case of uranium residues Th-230 and Ra-226 are not in equilibrium, particularly if the Th-230 is much higher than Ra-226, a potential source of Ra-226 contamination may exist as radium builds up to equilibrium with the Th-230.
In this case, the primary con-i sideration must be given to exposure from radionuclides other than U-238 and U-234.
In some types of operations, other metals are extracted and uranium I
ore is left in the weste stream as byproducts.
In,these cases all uranium daughter products must be considered.
4 The parent U-235 occurs to the extent of only about 0.7*. in natural uranium and the chain is generally unimportant compared with the U-238 chain. However, in the early years of the Manhattan Project much of the ore was very high grade pitchblende or carnatite ore. Af*ar 'Jw uranium was separated and Ra-226 extracted from the wastes, the Ac-227 and Pa-231 nuclides remained in the waste stream. These constitute a significant source of contamination.
As shown in Tables 2 and 3 radionuclides in the uranium decay chains emit alpha, beta and gamma radiation. The pathways for dose to man are from oirect radiation, inhalation and ingestion. The critical organs are the whole body, the bone and t.'m lung.
9 O
i
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-4 Table 2 Uranitan Chain PHncipal Radiations (MeYla Isotone 1/2 Daughter Alona-3 eta-sanuma -
I U-238
- 4.468x10 Th-23;4 4,.20
.m s
Th-234
'24.10d Pa-234 0.0tL4 0.008 1
Pa-234 1.17e U-234
~
0.82 0.011 5
U-234 2.445x10 y Th-230 4.,76 4
Th-230 7.7x10 y Ra-226 4.66 Ra-226 1600y Rn-222 4.77 0.006 Rn-222 3.8235d Po-218 5.49
~
Po-218 3.05m Pb-214 6.00 Pb-214 26.8m 81-214
- 0. 2'2 0.23 81-214 19.9m Po-214 0.63 2.03 Po-214 1.64x10 s Pb-210 7.69 Pb-210 22.3y 81-210 0.007 0.002 Bf-210 5.012d Po-210 0.39 Po-210 138.378d Pb-206 5.31 (Stable)
"3 ranches <15 not included bhi edne m.
CTotal energy earf tted per disintegration.
)
9.
III Dese Calculation The following Tables 4-6 susanHze the organ doses for vaMous pathways to man based on unit concentration of each nuclide as shown in Tables 1-3.
All internal doses listed in the tables are 50-year dose cosedtzents; that is, the total dose an indivital will receive from one yearf of intake integrated over the next 50 years of his life. For'those mateMais that einer have short radioactive half-lives or are ' eliminated rapid 1y from me bo#, essentially all me dose is received in me same year that the radionuclide entered te body, 'and the annual dose rate is about the same as the 5D-year dose comuttmant. All external doses are given as annual dose rates.
The factors for converting internal exposure to dose (dose conversion factors) were determined using ICRP-2 and other reco implemented by recent models (Task Group Lung Model)gnized values and for the lung and GI tract. The dose conversion factors used for external radiation dose determination are given in ORNL-4992. The dose conversion factor for inhalation of radon and its daughters are derived from the SEIR report.
IV DeMved Maximum Allowable Concentration for Various Discosal Ontions Tables 7 and 8 susuaHze the maximum allowable concentration for the disposal of vaMous types of wastes. Concentrations deMved in opt $en-4 are residues of cleanup conceneations which can be disposed of in ary mannan. The concentra-tions derived in option 2 are such that under the worst modes of exposure including all significant pathways, the maximum individual dose would not exceed 170 ares /yr to any cHtical organ.
In option 3. the most significant pathway is from the inhalation of radon and its daughter products. Wie an average concentration of 20 pCi Ra-226 per gm of wasta. it is estimated that an indivital could be exposed to an average of 0.04 Working Level (WL) from inhalation of radon instde structures built on contaminated land.
This exoosure is judged to be too high for residential use of the buMal site. (Com Guidance.) pare with 0.033 WL-10 CFR 20; 0.005-0.02 WL-EPA Flodda Phosphate Cosmarcial use of the site is allowable because the exposure time to radon is exoected to be less than.505 of continuous exposure and consequently no indivikal will likely be exposed to an average of 0.5 WLM.
The concent: rations of uranium, depleted uranium and natural thoMum deMyed in l
i option 4 are higher by approximately a factor of 10 since a limited exposure from an intruder (assuming about 305 of full exposure used in option 21 is assumed and a maximum individual dose of 500 ares /yr *.o a cMtical organ ts assumed. For the case of natural uranium, the concentration deMved in option 4 is higher by a factor of 5.
The concentration is based on a limited exposure such that no individual will be exoosed to a radon dose in l
excess of 0.5 WLM assuming a maximum exposure time of 2.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> (i.e.105) a day. This is equivalent to continuous exposure to 0.02 WL.
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- Table 5a Dose Cossaitment:(a) From Inhalation of Resusoended Rac1onuciloes'-' From Contaminateo Sol.1 Figuras am based on a unit concentration of 1 pCi/g of each radionuclide in so11.
(Clearance rate class Y; particle size (AMAD) = 1 us)
Rant onuc t ice Dose coas11:nent (erin)(f)
Lune se sone
~
worzino tevei uranium 5eries U-238 6.1E-IICI M.2E-3
.Th-234 (d)
Pa-234a U-234 6.9E-1 5.8E-3 Th-230 6.7E-1 2.4E-1 I
Ra-225 7.2E-2 *I 3.6E-2 Po-218 Pb-214 81-214 Po-214 I
Pb-210 7.9E-3 *I 3 1E-2 81 -210 Po-210 5.9E-Z An-222
.002(h)
(a) Fifty-year dose consitzent for one year of intake.
(b) Assumed resuspension factor 5x10-9's-l; maximum soil densit 80% occupancy. This resuspension factor may be conservative.
These factors should be based on particle size and densities associated with specific sites.
(c) Read as 6.1x10~1 (d) Insignificant ccmpared with other nuclides.
(*) Ra-225 and Pb-210 are classified as W compounds; Po-210 is cla comoound.
if) Based on quality factor of 20 for alpha particles.
(I) Pulsenary lung (h) Tne average Working Level (WL) is calculated on the basis of 25 (continuous exposure) and a dose conversion factor of 5 run per working level This mean level of exoosure derived from radon inside a struct month.
on contaminated was as could be off significantly depending on ne incut parameta used, such as the ventilation rate, type of floor, etc., wnica are cepencent on tne struc~rral design of the building.
Table Sa (cont af Raasonuciice Dose casan taant (ER*GB)
Luno aone Act1 nt us 5eries U-235 6.2E-1 5.3E-3 Th-231 Pa-231 7.5E-1 7.0E-1 Ac-227 1.3E-0 3.9E-1 Th-227 8.8E-2 2.9E-4 Ra-223 5.9E-2 7.0E-4 Rn-219 Po-215 Pb-211 51-111
~~
-~
T1-207 ThoH us SeM es Th-232 5.8E-1
- 2. 6E'-1
~
Ra-228 6.ZE-3 2.1E-2 Ac-228 Th-228 9.2E-1 2.3E-2 Ra-224 An-220 Pb-212 81-212 T1-208
~
O e
9 e S e
-10 Table Ib Dose coeuritments From Innalation of Resusoended
'b from F.causinates sot i 4/ Ff gures are based on a unit concentration of 1 pCi/g of. each ra in soil (clearance rate class 'd; particle size (AMAD) = 1.m)
Raatonucline Dose ccmanunent (ares)
Lune sons worxing Level pran1un series U-238 Th-234 6.3E-2 1.SE-2 Pa-234a U-234 Th-230 7.0E-2 1.7E-2 Ra-226 6.9E-2 6.0E-1 7.2E-2 3.6E-2 Po-218 Pb-214 51-214 Po-214 Pb-210 7.9E-3 3.1E-2 81-210 Po-210 1.3E-3 5.9E-3 An-222
.002 0
l
\\
Table 5b (cont 4)
Aacionuclice cose comentaent (wres)
},.,u,nji, none n
Actintum series u-2.sa 6.4E-2 1.5E-2 Th-231 Pa-231 1.6E-0 Ac-227 7.4E-2 1.1E-0 Th-227 6.8E-2 2.6E-3 Ra-223 E.9E-2 7.0E-4 Rn-219 Po-215 Pb-211 81-211 T1-207 Thorium Series Th-232 6.0E-2 6.2E-1 Ra-228 6.1E-3 1.1E-2 Ac-228 Th-228 1.5E-1 1.3E-1 Ra-224 Rn-220 Pb-212 Bi-212 T1-208 9
0 9
?
1
- Table Sc, Dose Commitments from Inhalation of Resusoended Racionucitces from cortaminateo scii Figures are based on a unit concentration of 1 pCf/g MJ of each radionuclide in so11.
',']
0; particle size (AMAD= 1.um)) (Clearance rate class l
"~ '
Racionucitae pose cosentment (mrum)
Lung sone woriit.? Leves i
uranium series U-238 1.1E-3 5.0E-2 Th-234 Pa.2344 U-234 1.ZE-3 5.6E-2 t
Th-230 6.9E-2 6.0E-1 Ra-226 7.ZE-2 3.6E-2 Po-218 Pb-214 51-214-Po-214 Pb-210 7.9E-3 3.1E-2 81-210 Po-210 1.3E-3 1.9E-3 Rn-222
.002 e
Table 5e <
tcont's) cose coasttaant
_ _. q Aantonucaiae i
(ares)
Luno cone Actinium series U-235 1.1E 5.0E-2 i
Th-231 Pa-231 7.4E-2 1.6E-0 Ac-227 1.1E-1 1.1E-0 Th-227 6.8E-2 2.6E-3 Ra-223 5.9E-2 7.0E-4 l
Rn-219 Po-215 Pb-211
-~
51-211 T1-207
=
Nota: ThoHum compounds are classified as Y and W compounds.
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-16 Table 8 Maximus Allowable concentration in Wasta for Ontions 1, 2. 3 and..L.
Type of Wastas Maximum Allowable Concentration (oCi/q) 9otton i ootton a a 3 cotton 4 1.
- a. Insoluble 35 300 3,000
- h. Soluble 35 100 1,000 2.
Enriched Uranium (U-23s,U-235,u-134)
- a. Insoluble 30 250 2,500
- b. Soluble 30 100.,
1,000.
3.
Natural Ur'anius (Uw238. U-234) l
- 4. Insoluble 10 40 200
- b. Soluble 10 40 200 j
4.
Natural Thorium (Th-232, Th-228)
- a. Insoluble 10 50 500
- b. Soluble 10 50 500 l
0
e
~
NUCLEAR REGULATORY C0tmI55 ION DISPOSAL OR ONSITE STORAGE OF THORIUM OR URANIUM WASTES FROM PAST OPERATIONS AGENCY:
Nuclear Regulatory Consission (NRC)
ACTION:
Discussion of Options for NRC Approval of Applications for Disposal or Onsite Storage of Thorium or Uranium Wastes -
Interim Use and Public Comment SutNARY:
This notice discusses five options for NRC approval of disposal or onsite storage of thorium or uranium wastes frem past nuclear operations'.
The cptions are contained in a Branch Technical Position for administration
> the Uranium Fuel Licensing Branch, Division of Fuel Cycle and Material Safety, Office of Nuclear Material Safety and Safeguards.
DATES:
Comments on the options for disposal or onsite storage of thorium or uranium are encouraged. Such connents will be considered in any subsequent revision of the Branch Technical Position. Comments are due
=
FOR ADDITICMAL INFORMATION CONTACT:
Ralph G. Page, Chief, Uranium Fual Licensing 3ranen, Division of Fuel Cycle and Material Safety Office of Nuclear Material Safety and Safeguards Washington 0.C. 20555, telephone 301 427-4309.
- 50 days after publication Encicsure 4
'c SUPPLEMENTARY INFORMATT.0N:
I.
Introduction Some of the sitas fomerly used for processing thorium and uraniurs are known today to be contaminated with residual radioactive mataM als.
Some are currently covered by NRC licenses.
Others were once licensed. but the licanses to possess and use.mataHal have expired.
In many cases, the i
total amount of contaminated soil is large, but the activity concentrations of radioactive mateHals'are believed sufficiently J
Iow to justify their disposal on privately owned lands or-I storage onsite rather than their transport to a licensed radioactive mataMais disposal (cosmercial) site.
In many instances packaging and tra'nsporting these wastap to.a Itcensed I
disposal site would be too costly and not justified from the standpoints of risk to the public health or cost-benefit.
l Furtherinore, because of the total volume of these wastes, limited ccessercial wasta disposal capacity, and restrictions placed on receipt of long-lived wastes at comercial sites, it is not presently feasible to dispose of these wastas at connercial 4
low-level wasta disposal sites.
Effective January 28. 1981, ilRC regulations in 10 CFR 20
" Standards for Protection Against Radiation", were amended (45 FR 71761-71762) to delete Section 20.304 which provided f
1 general authority for disposal of radioactive materials by buMal in soil. Under the amended regulations, licensees
?
3-must apply for and obtain specific NRC approval to dispose of radioactive materials in this manner under the provisions of 10 CFR 20.302. - A case-by-case review was believed needed to assure that burial of radioactive wastes would not present an unreasonable health hazard at some future date.
The deleted prtWisions of Section 20.304 previously perinitted burial of up to.100 millicuries of thorium or natural uranium at any one time, with a yearly limitation of 12 burials for each type of material at each site. The only disposal standarts specified were (1) burial at a minimum depth of four feet, and (2) successive burials separated by at least six feet. Thus a total of 1.2 curies of these materials were permitted to be
~
disposed of each year by burial in a 12 foot by k8 foot or larger plot of ground.
Under the amended regulations, it is incumbent on an applicant who l
wants to bury radioactive wastes to demonstrate that local land burial is preferable to other disposal alternatives. Tne evaluation of the application takes into account the following infor. nation:
Types and quantities of material to be buried Packaging of waste e
9 e
e e
e
., BuHal location CharacteMstics of burial site Depth of burial Accans restrictions to disposal site Radiation safety procedures during disposal operations Recordkeeping Local burial restMctions. if any For applications involving disposal of soils contaminated with low level concentrations of thorium and uranius (other than concentrations not exceeding DA cleanup standards), the matters of principal importance are:
Co,ncentrations of thoHun and uranium (either in secular equilibHun with.their daughters or wikiout daughters present)
Voltme of contaminated soil Costs for offsita and onsite disposal Availability of offsite buMal space Disposal sita characteristies' Depth of burial and a'ccessibility of boHed wastas Stata and local government views II.
Branch Technical Position Tnere are f'.ve acceptable options for disposal or onsite storage of thoHus and uranium contaminated wastas. Applicatiens for disposal or storage will be approved if the guidelines discussed under any option are met.
Applications for other methods cf
}
disposal may be submitted and these will be evaluated on their own merits.
1.
Disposal of acceptably low concentrations '(which meet EPA cleanup standards) of natural thorium wfth daughters 'in secular equilibrium, depleted or enriched uranium, and uranium ores with daughters in secular equilibrium with no
~
restriction on burial method'.
Under this option, the concentrations of natural thorium and depleted or enriched uranius wastes are set sufficiently 1ow that no member of the public is expected to receive a radiation dose connitment from the disposed materials in
_ excess of 1 millirad per year to the luno or 3 millirads per year to the bona frue inhalation and incestion, under any foreseeable use of the material or property. These radiation dose guidelines were reconnended by the E.nvironmental Protection Agency (EPA) for protection against transuranium elements present in the environment as a result of unplanned contamination (42 FR 60956-60959).
In addition, th_e concentntions are suff4H--tly low so that no individual may receive an external dose in eyx s
of 10 microreentgens per hour shave haeW-1 This is eczepatible with guidelines EPA proposed as cleanup standards for inactive urarrtum pr: cessing sites (t6 :R 2556-2563).
1 1 For natural uranium ores having daughters in equilibrium, the concentratf on limit is equal to that set by the EFA (46 FR 2556-2553) for radium-EZ6 (f.e., 5 pCi/gm, including background) and its decay pbucts.
The concentrations specified below are believed appropriate to apply.
It is expected, however, that currently licensed operations will.be conducted in such a manner as 'a minimize the possibility of soil contamination and when such occurs the contamination will be reduced to levels as low as reasonably achievable.
Kind of' Material Concas.tration (pCf/gm)
Natural thorium (Th-232 plus Th-228) if all daughters are present and in equilibrium 10 Depleted Urania 35
~
Enriched Uranium 30 Natural Urania Ores (U-238 plus U-234) 10 if all daugtreers are p' resent and in i
equilibrium j
Tne analysis upon which.the Branch Technical Position is based is available for inspection at the Conesission's Public Document Room at 1717 H St., N.W., Washington. 0.C.
O l
i
r 9
1 7-The concentrations specified under this option may be compared with naturally oc:urring thorium and uranium are
~ concentrations of 1.3 pct /gm in igneous rock and uranium concentrations of 120 pCi/gm in Florida phospnate r:ck and 50-80 pC1/gm in Tennessee bituminous shale.
Concentration limits for natural thoHun and natural uranium ore wastes containing daughters not at secular equilibrium can be calculated on a case-by-case basis using the applicable isotopic activities data.
2.
Disposal of certain low concentrations of natural -hoHun with daughters in secular equilibrium and depleted or enriched uranium with no daughters present when buried under prescribed conditions with no subsequent land use restMetions and no continuing MRC licensing of the material.
Under this option the concentrations of natural thorium and uranium are sat sufficiently low so that no member of the public will receive a radiation dose exceeding those discussed under option 1 when the ' wastes are buMed in an appr ved manner absent intrusion into the burial grounds. Tnis option will recuire establishing prescHbed c:nditions f:r dis =osal in the license, such as depth and distMbution of mataMal, to minimize the likelihood of intrusion.
BuMal will be pemitted only if it can be demonstrated that the buMed materials will be stabilized in p. lace and not be t-anspor ed away from the sita.
4
r.
Acceptability of the site for disposal will depend on topographical, geological, hydrological and meteorological characteristics of the site. At a minimum, buMal depth will be at least four feet below the surface.
In the event that there is an intrusion into the burial ground, no member of l
the pubite will Itkaly receive a doseln excess of 170 at111rmas to a critical organ.. An average dose not exceeding 170 mi111 rums to the whole body for all memoers of a general population 1s recommended by international and national radiation expert bodies to limit population dosas. iltth respect to limiting dosas to individual body organs, the conenntrations are sufficiently low that no individual will receive a dosa in excess of 170 millirems to any organ from exposure to natural thorium, depleted uranium or enriched uranium.
4 The average activity concentration of radioactivo material that may be buHed under this option in the case of natural thoHus (Th-232.plus Th-228) is 50 pCf/ge, if all daughters are present.and in equ11tbMus; for enriched uranium it is 100 pCi/gm if the uranium is soluble and 250 pCi/gm if insoluble; for depleted uranitor it is 100 pCf/gm if the uranium is soluble and 300 pCi/gm if insoluble. Natural uranium ores containing radium 225 and its daughters are hot included under this option, because of possible radon 222 emanations and resultant higher than acceptable exposure of individuals in private residences if heures wars built.mver buMed matertals.
A 3.
Disposal of low concentrations of natural uranium cras, with all daughters in equ11thrium, when buried under presc-ibed conditions in areas zoned for industrial use and the recorded title documents are amended to state that the specified land contains buried radioactive materials'and are u
conditioned in a manner acceptable unoer stata law 'to impose a covenant running with the land that the specifi.ed land may not be used for residential building.
(There is no continuing
.9C licensing of the material.)
Disposal will be approved if the burial criteria outlined in option 2 (including burial at a minimum of 4 feet) are met.
Depending upon local soil characteristics, burials at depths
[
greater than 4 feet may be required. ~ In order to assure protection against radon 222 releases (daughter in decay chain of uranium 238 and uranium 234), it is necessary that the recorded title documents be amended to state in the permanent land records that no residential, building should be permitted over specified areas of land where nawral uranium are residues (U-238 plus U-234) in concentrations exceeding 10 pCf/gm has been buried.
Industrial butiding is accapuble so long as.he concentration of buried mnteriai does not exceed 40 pCf/gm of uranium (i.e., Ra-226 shall not exceed 20 PCi/ge).
4 Disposal of land-use-limited c:ncentrations of natural thorium or natural uranium, with daughters in secular equilibrium and depleted or enriched uranium without daughters present when
F
' i t
buMed under prescMbed conditions in areas zoned for industrial use and the recorded title documents are amend state that the land contains buMed radioactive mateMal and are conditioned in a manner acceptable under state law to impose a covenant running with land that the land (1) may not be excavated below stated depths in specified areas 'of land j
unless cleared by appropMate health authorities, (2) may l
not be used for residential or industrial structures over specified areas where radioactive mateHals in concentrations higher than specified in options 2 and 3 are buried, and (3) may i
not be used for agricultural purposes in the specified areas.
(There is no continuing NRC licensing of the disposal site.)
Under this option, conditions of burial wi.11',be such' that no member of the public will receive radiation dosas in excess of those discussed under option 1 absent intrusion into the burial ground.
Criteria for disposal under these conditions is predicated upon the assumption that intentional int:asion is less likely to occur if a warning is given in land documents of record not to ' excavate below buMal depthe in
~
specified areas of land without clearance by health authoMties; not to construct residential or industMal building on the site; and not to use specified areas of land for agricultural purposes.
Because of this, we believe it aporopMate to apply a maximum critical organ exposure limit of 500 millirens per year to thoMum i
~
a s.
and uranium buried unoer this restriction instead o as used in options 2 and 3.
In addition, any exposure to such 3
materials is likely to be more transient than assumed (essentially continual exposure) under those cptions. These tw fa'ctors combine to increase the activity concentration limits calculated under option 2 by about 10. Tm$s'," the average concentration that may be buried under this option for thorium
~
(Th-232 plus Th-228) is 500 pC1/gm if all daughters are present and in equilibrium; for enriched uranium it is 1000 pC1/gm if the uranium is soluble and 2500 pct /gm if insoluble; and for depleted uranium it is 1000 pC1/gm if the uranium is soluble and 3000 pCi/gm if insoluble.
With respect to natural uranium with daughters present and in equilibrium, the concentration that may be buried under this option is 200 pC1/gm of U-238 plus U-234, i.e.,100 pCi/gm Ra-226.
This concentration is based on a limited exposure of 2.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per day to limit the radon dose to less than 0.5 working level month (WUi) which is equivalent *J continuous exposure to O.02 working level (WL).
Depending upon local soil characteristics.' burials at depths greater than 4 feet may be required.
5.
Storage of licensed concentrations of thorium and uranium onsite pending the availability of an appropriata disposal site.
e e
- When concentrations exceso those specified in option 4, long tem disposal other than at a license disposal site will not normally be a viable option under the provisions of I
{
In such cases, the thorium and uranium may be pemitted to be stored onsite under an NRC license until "
a suitable method of disposal is found. 1.icense conditions '
will require that redfation doses not exc'eed those specified in 10 CFR Part 20 and be maintained as low as reasonably achievable.
Before approving an application to dispose of thorium or uranium under options 2, 3, or 4. NRC will solicit the view of appropriate State health officals within the State in which the disposal would be made.
Dated:
Richard E. Cunningham Director, Division of Fuel Cycle and Ma arial Safety
. Office of Nuclear Material Safety and Safeguards e
7. r
.s s
d i
Letter dated February II,1999 Nom Timothy Vitkus'to Rod Cummings with the enclosed
" Proposed Verification Survey Plan for the Hot Cell Facility, General Atomics, San Diego, California"
.)
, f
.e FEB.23.1999 St33PM DOE /CRUERD NO.059 P.2 l
g ORISE DAK 18044 INAffruTE PCHt ecWNce ANO pouCATION
\\
\\
W February 11,1999 Mr. Rod @== hgs U.S. Departrnent of raergy EM4 CloverleafBuilding Washington, DC20585 0002 PROPOSED VERIFICATION SURVEh PLAN FOR THE HOT CELL FACILITY,
SUBJECT:
GENERAL ATOMICS, SAN DIEGO, CALIFORNIA Dear Mr. oinnming=-
The Enviremnental Survey and Site Assessment Program (BSSAP) ofIbe Oak Ridge Institute for Science and Education (ORISB) has prepared and enclosed the mbdect survey plan fbr your myiew and comment. Conunchts you may have will be incorporated into tbc final survey plan.
Please contact me at (423) 576-5073 or Eric Abelquist at (423)'576 3740 should you have any questions.
Sincerely,
\\
Tiroothy. V tkus Survey Projects Manager EnvirurunentalSurvey and Site AssessmentProgram i
TJV/dkh Enclosure l
cc:
,J. Dayis,N i
W. Beck, ORISP/BSSAP B. Abelquist, ORISE/ESSAP Pile /406 r, O. BQ( l 17, QAK RIDGE. TENNESSEE 37831 0117 Managed and operoW by Ook Ridge Amonknad unherdpes Int lhe U.S. Depenmeed of Enery R=07%
Sid 637 2078 02-23-99 02:58PM P002 #27
't fEB.23.1999 3:33PM DOE / OAK / ERD NO.059 P.3
~.
PROPOSED VERIFICATION SURVEYPLAN OFTHE HQT CELL FACILITYSITE GENERAL ATOlWICS SAN DIEGO,CAIRORNIA INTRODUCTION AND SITE HISTORY
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General Atomics (GA) has maintainal a fully-operational Hot Cell Facility (HCF) ainoe 1958 in I
support ofprimarily govermnent fbnded nuclear research and devalemmant (R&D). The heavily-1 shielded remote-handling laboratory was used fbr a variety of radiologically hazardous and toxic anarimant=1 operations.
l i
The HCF housed three shielded celle-4he High Level Cell (HLC), the Low Level Cell (LLC), and the Metallography Cell. The HLC was used to p.u'orm post hradiation avaminations on fbols and struotamt materials while tbs LLC was used as a staging area for samples being transarred in and i
i i
out of the HLC. The Metallography Cell was utilized to prepare fbel and metal samples for the ma*=nagraph. Most ofthe projects served in the ar==8a A ofimdiated fuel and graphite forHigh Temperature Gas-Cooled Reactors (HMR). Earlier enminnflons involved examinaties of Hastelloy X-clad uranium oxide berylliinn oxide fuel for the Bxperimatal BerylHum Oxide Reactor (BBOR) and its A =, the Marine Gas-Cooled Reactor (MOCR). The UO -BeO fuel for the 3
HBOR was manufhotured in the area ofthe GA Hot Cell Building that later sesved as the manhine shop. Recently, the HCF was utilized for the namin=Han of thermionic fhel elaments (TFE) for space power application and fuel for GA's
- mining. rad, and isotope reactor (TRIGA).
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In addition to activities c*2d in the building's test cells, areas such as the Physical Test Lab, Hot Col 1 Yard, and the service gallery were used during re.. dor,. Since 1980, the Physical Test Lab was used fbe the Rnei=aarlag Scale Tritiu:n Extraction System project for the New MiJ by the Envimnmental Survey and Site Assessment Program, Radiation Safety, Assessment, and Training, Oak Ridge Institute fbr Science and Education, Oak Ridge, TN, under contract with the U.S. Department ofEnergy.
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4 Production Rametor program while the Hot Cell ynd and service gallery was used for osak h*ad*=
and maintananaa activities, waste consoMatlan and packaging.
i Deceasnissioning actMties have omnpletely Ainmentled the HCF and a substantial portion of the building was disposed of as radioactive waste. Included in the waste disposal was the Cella ManipalatorRepair Room and the mv ina shop All support equipment associated with the MCF, e
A such as wre
.od tanks, wells, and piping systems wese excavated and disposed of accordingly.
Portions of the building that wese not directly involved with the handling of radioactive materials such as ofHee,s, change rooms, and rest rooms have been dienantlert, surveyed, and released for unrestricted use through confianatory surveys p hmed by the U.S. Nuclear Reguhtory fornmlamlnn (NRC).
DOB's OfBee of Envirnmaar*a1 Restoration, Northwest Area Pmaraens is responshie for oversight of a number of remedial actions hat have been or will be conducted at GA. It is the policy of the DOB to perbrm yT =-Ni (third party) vminaatian of ravnadial action actMties conducted within Oftion of Enviromnantal Restoration prognons. The purpose of these independent verifications is to aanAnn that remedial actions have been eSective in madlag eselimhed and aW%
guidelines and that the documentation accurately and adagadaly describes the radiological cor ians at the site. The Environmanta1 Survey and Site Assessment Pmanun (BSSAP) of the Oak Ridge Insdtate fbr Science and Educadon has been designated by the DOE as the orama68an fbr this task at General AhW and has been requested to verify the cuuent radiological status of the HCF.
SITE DESCRIPTION GA is a 120 acre (48 hectares [ha]) facility located in the extreme western portion of San Diego County.yy.4 ;=*=5y 21 km (13 miles) fhnn downtown San Diego and 1.6 kilometers east of the Pacific Ocean (Figore 1). The fboilityis anam4a=4 of two contiguous sites referred to as the Main site andthe Sorrento Valleysite.
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'Ibe Hot Call Pacility site la located within the Main site, at the former location of Building 23 (Figsre 2). The sits is molosed by a security fbnoe and once included the radiologically-controlled yard area, as N as Building 23. The satire fbuced aren is sppmei==+aly 5000 m.
2 OBJECTIVES I
"' 'Ibe objectives of the verification suney are to condon that remedia1 actions have been effective in i
uneeling estabHahed gnMelines and that doonrnantatinn a,- ---ty-descrioes the post-remedial action j
radiological conditions of the property.
i i
RESPONgntn.rly Waric described in this survey plan will be perfonned under the direction of W.L (Jack) Beck, Program Director, and Tim Vitkus, Survey Projects Manager, of tbs Enviromnental Survey and Site Assessment Program. The cognient ESSAP site supervisor has the antharity to rnake.ypopiate changes to the survey procedures as daarnM necessary. After consultation with the DOB site repramentadve, the scope of the survey plan may be altered. Devindnna to the survey plan or
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procedures will be d&W in the site logbook.
DOCUMENT REVIEW ESSAP will review GA's final survey reentes and supporting docmnantatian me=4ag site decornmissioning activities. Infbrmation will be evaluated to assure that areas Idan*Med as
. aug the site giMahnap have undergone daaantaminadan and that :=ht activity levels satisfythe established==idaH=
PROCEDURES A survey team from ESSAP will visit the General Atomics Hot Cell Facility to p=a m visual innt-dana and ladW rnessuruinants and sampling. The verification survey activities will be e
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No.059' P.6 l i conducted in accordance with the ORISB/BSSAP Survey Procedmes and Quality Assurance Mangala (ORISE 199sa and b). The pencedures applicable to this survey are listed on pass 6 of this surveyplan.
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REFIUDF,NCE SYBHM
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i The 10 m x 10 m grid establiabad by GA will be used for referencing massarament and sampling location. If a grid has not been established, BSSAP willinstall a nimilar aference grid system.
l SURPACE SCANS 1
c4mmnu scans will be mmhr*ad at 1-2 m intervals over 100% of tbs HCP site using NaI arenmissan detootars and ratemeters with audible indiaahws.- LWa of elevsted radistion, suggesting the presence of surface or near surfbee contamina%. will be marked and identified fbr fluther Weah l-EzrosenE RATE MEASUREMENTS 1.i:
l Osama exposure rates will be measured 1 m above the surfhoe at each soll sample location.
Exposure rate measurements will be p.- L. - -i using a microrern meter.
I j
Background exposure rates were determined during a previous she survey (ORAU 1986).
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1 1
A f. L, of 30 sur&ce soil samples (015 cm) willbe collected from 1he HCF. Samples will be collected from the centers and four points equidistant ftom the center sud grid block cornem of 5ve l
grid blocks. Additional soil samples will be coucoted at locations of elevated radiation identified by surfsoe samma scans. Subsurfbee soil samples may be collected if elevated radiation is suspected l
l Osneel Assulas(Oste -Fdnery 11.1998 4
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to be present below 15 cm. Additionally, BSSAP sequested and received Ryo soil samples, co1%d by GA, for -M==*ry analysis.
Background sail samphs collected during a pnwious site survey will be used for comparison purposes (ORAU 1986).
3 i
SAMPLE ANALYSIS AND DATADITERPRETATION l
n.
1 Samples and data will be retumed to ORISE's BSSAP lebui&=y in Oak Ridge, TN for analysis and icEywkilon. Sampleanalyseswillbeperfomed in accordance with the ORISE/ESSAP T mhnratory Procedures Manual (ORISE 1998c). Soil sainples will be analyzed by gamma spectrometry apd
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results reportedin piWas per gram (pCilg), Tbs radionuclides ofinterest are uranium and mixed fissico products; however, spectra willbe reviewedforotheridantinablephvioysiks, Exposurerates 1
will bereported in units ofmicromentgens perhour(pr/h).
The data generated will be s,h.yered with tbs DOE guidelines establiabed for General Atomics, Results will be ycz 2+1in a daft report and provided to the DOB for review and comment. Data and samples collected as part of this survey aillbearchived byBSSAP.
GUpBLINES The applicable site specide guidelinas arepmided in Table 1 and have been.yymwid by both the NRC and State of OmWfamin (GAT 1998). Ibe DOE's exposure rate pdaha is 20 R/h above background (DOE 1990).
TENTATIVE SCHEDULE Measurement and Sampling March 1999 i
SampleAnalysis i
March 1999 Draft SurveyReport May 1999 l
General Amales(6404.Pubrusy !!. IM S
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g LIST OF CUIUtENT PROCEDURES Applicabis procedures from ORISII/BSSAP Survey Pmoedures Manual (Revision 10, January 7, 1998) include:
i Section 5.0 INSTRUMENT CALIBRATION AND CHECK OUT 5.1 Generallafbernation
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5.2 Electionio Calibration ofB atameters 1
5.3 Genuna Sunh Detector and Check-Out and Cross Cahhation 5.9 BicionMicro-RamMeterChecke
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Section 6.0 SITE PREPARATION 6.1 Clearingto Pmvide Access 6.2 Rafennce Grid Systen Section 7.0 SCANNING AND MEASUREMENT TBCHNIQUES s
t 7.1 Surface S-r--
'ng I
7.5 Genuna Radiation (Bxposure Rate) Measumment i
Section 8.0 SAMPLINGPROCEDURBS 8.1 Surfboe Soil S=,ah 8.2 Subsurface Soll A-=hs 8.15 Sampleidantifinatlan and Labeling 8.16 Sample Chain-of-Custody Section 9.0 DfrBGRATED SURVEYPROCEDURES 9.1 Bookground Measurements and Sampling 9.2 General Survey Approaches and Strategies Section 10.0 SAFBTY AND CONTAMINATION CONIROL Omust Adamles(0404.Fahnsey 11. topp 6
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FIGURE 1: Location of General Atomics Facility San Diego, Colifomia w m yoe. penny:,ww 7
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SECTION A 57.
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U NOT TO SCALE FIGURE 2: General Atomics Focliity Indicating Location of Hot cell Facility o
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l TABLE 1 SOILREEASE CRITERIA 8 HOT CELL FACILITYSFIE GENERAL ATOMICS SAN DIEGO, CALIFORNIA I
nala==a Critarla Based on Release CriteriaBased on Radiennelide EirearnalEspasare Llanita, Interna 1 Exposure 1.s-h.
t la PCl/g inpCl/g Co.60 88 Cs-137 158 Cs-134 10 i
Bu-152 11 Bu-154 10 Ba-155 635 Nb-94 7.5 h125 37 Sr-90 18008 Naten1 Uranium 355 hih Uranium 3 08 (U-235 & U-234)
Thorium 1 08' (Th-232 & Th-228)
'The solosse crientia shown in this tends without annotation by fbotnotes 2 er 3 wue osiculated by the licenses using RBSRAD venian 5.18 adbaring to the sans assumplicas that ween providsdin the Waaaa 11ssedia note 2 below.11ds corresponds to censorysdve calculaties of the t------;---
aaan==*H of an footoos in Ibe soE that by itself would give appseximately 10 pR/hr exseenal exposes sees above background As the =p% year of esposues.
%ese inleese orkeria are based span procedent through NRC and Stees at anfa=la spyroved release ihnits fbr iba GA sim. See A.z, =" = K.1L Asumaman to W,T. Crow, dated October 1,1985, certespondence Manhead-696-8023, Sutdoet " Docket 70-734; Plan ihr Obtaining Release of Certain Atees to Unastricted Use."
%sse sensese crimris are based on past precedent established by NRC throtighNRC Policy Issus SECY-81 576, deted October 5,1981, Sutiect " Disposal or onreits seorage ofresidual tWum or umaima (either as naturat ores or webout daughbra pseemeQ Dom past operations."
- stadem=ai nucadse em enematwed during ihe Final sarvey nativities, vahme identiflod in the previously approved GA Hot OmE PaciHty E- --- * '
- Planandthe GA Bitsn====iasiming Plan wm be used.
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REFERENCE 8 i
General Atrein (GAT). Fina1 Survey Plan fbr Gmeral Atontics Hot CellPacility Area. San Diego '
Califbmia; October 30,1998.
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Oak Ridge Associated Universities (ORAU). C=MW Surysy ofPhase I M-ihn Fonner Waste Processing Facility, GA Tech =^!@. San Diego cauw. OakRidge,TN; July 1986.
Oak Ridge Institute jbr Science and Education (ORISE). Survey P==-h+ Manual ihr the
{
P.avironmantal Survey and Site Aamame Program, Revision 10. Oak Ridge, TN; January 7, 1998a.
j i
l Oak Ridge Institute for Science and Ednadan Quality Assu:ance Manual for the Environmental l
Survey and Site Ass-mW Program, Revision N Oak Ridge, TN; May 1,1998b.
Oak Ridge Institute for Science and Wadou. Laboratory Procedures Manual for the Environmel Survey and Site A amaannant Program, Revistas 11. Oak Rkige, TN; February 17, 1998o.
U.S. Department bf Energy (DOB). F#ignan Pr*+ of the Public and the Enviran==*
Washington, DC: DOB Order 5400.s; February 1990.
k amend Aassiles(a406).pshn,'y II.1980 D'M
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