ML003771426

IR07000925/2000-001 Kerr-McGee Center (Cimarron Corporation) 11/24/2000

ML003771426
Person / Time
Site:	07000925
Issue date:	11/24/2000
From:	Chamberlain D Division of Nuclear Materials Safety IV
To:	Larsen S Cimarron Corp
Carson L
References
-RFPFR IR-00-001
Download: ML003771426 (18)

Text

November 24, 2000 Mr. S. Jess Larsen, Vice President Cimarron Corporation Kerr-McGee Center P.O. Box 25861 Oklahoma City, Oklahoma 73125

SUBJECT:

NRC INSPECTION REPORT 70-925/00-01

Dear Mr. Larsen:

On July 11-13 and August 15, 2000, the Nuclear Regulatory Commission (NRC) concluded the onsite portions of an inspection of the Cimarron site near Crescent, Oklahoma. On October 26, 2000, the NRC held a telephonic exit briefing with you and members of your staff concerning the results of the inspection and NRC analysis of confirmatory samples obtained during the inspection. The enclosed report presents the scope and results of the inspection.

The purpose of this inspection was to perform confirmatory surveys and sampling in Sub-Areas H, I, and M to confirm that the NRC Branch Technical Position (BTP) Option 1 release criteria had been met. Exposure-rate measurements and smear and soil samples were collected from various locations for analysis by the NRC. The results of these measurements and samples were compared with the results of your final status survey data and the BTP Option 1 release criteria. The data indicated that the BTP Option 1 release criteria had been met in Sub-Areas H, I, and M.

Soil sampling activities in Pit 3 were also observed. Twenty-four soil samples were collected from Pit 3, Lift 5 for analysis by the NRC. The results of these samples were compared with the results of the soil samples collected at the same locations by your staff. The NRC analysis was consistent with the results obtained by your staff and confirmed that the soil in Pit 3, Lift 5 met the NRC Branch Technical Position Option 2 release criteria.

In accordance with 10 CFR 2.790 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS).

ADAMS is accessible from the NRC Web site at http://www.nrc.gov/NRC/ADAMS/index.html (the Public Electronic Reading Room)."

Cimarron Corporation Should you have any questions concerning this inspection, we will be pleased to discuss them with you.

Sincerely,

/RA/

Dwight D. Chamberlain, Director Division of Nuclear Materials Safety Docket No.: 70-925 License No.: SNM-928

Enclosure:

NRC Inspection Report 70-925/00-01 cc w/enclosure:

Kerr-McGee Corporation Kerr-McGee Center P.O. Box 25861 Oklahoma City, Oklahoma 73125 Karen Morgan, RSO Cimarron Corporation P. O. Box 315 Crescent, Oklahoma 73028 Mr. Earl Hatley Oklahoma Toxics Campaign 3000 United Founders Blvd. #125 Oklahoma City, Oklahoma 73112 P. L. Bishop, Senior Environmental Specialist Radiation Management Section Waste Management Division Department of Environmental Quality State of Oklahoma 707 North Robinson Avenue Oklahoma City, Oklahoma 73102-6087

Cimarron Corporation Mike Broderick Radiation Management Section Waste Management Division Department of Environmental Quality State of Oklahoma 707 North Robinson Avenue Oklahoma City, Oklahoma 73102-6087

Cimarron Corporation E-Mail report to D. Lange (DJL) bcc w/enclosure to DCD (IE-07) bcc w/enclosure (via ADAMS distrib):

EWMerscoff KLKalman JPeckenpaugh DDChamberlain LLHowell DBSpitzberg LCCarson, II RJEvans MIS System Materials Docket File (5th Floor)

DOCUMENT NAME: s:\dnms\fcdb\lcc\007092501-lccrev1.wpd r:\_dnms\

RIV:DNMS:NMIB FCDB C:FCDB D:DNMS RJEvans LCCarsonII DBSpitzberg DDChamberlain

/RA/ /RA/ /RA/ /RA/

11/21/00 11/09/00 11/24/00 11/24/00 OFFICIAL RECORD COPY T=Telephone E=E-Mail F=Fax

ENCLOSURE U. S. NUCLEAR REGULATORY COMMISSION REGION IV Docket No.: 70-925 License No.: SNM-928 Report No.: 70-925/00-01 Licensee: Cimarron Corporation Kerr-McGee Center Oklahoma City, Oklahoma 73125 Facility: Cimarron Site Location: Crescent, Oklahoma Dates: July 11-13 and August 15, 2000 Inspectors: Danny L. Rice, Health Physicist, CHP Robert J. Evans, Health Physicist, PE, CHP Louis C. Carson II, Senior Health Physicist Accompanied By: Kenneth M. Kalman, Project Manager, HQ Jon M. Peckenpaugh, Groundwater Hydrologist, HQ Approved By: D. Blair Spitzberg, Ph.D., Chief Fuel Cycle & Decommissioning Branch

Attachment:

Supplemental Information and Data Tables

EXECUTIVE

SUMMARY

Cimarron Corporation, Cimarron Site NRC Inspection Report 70-925/00-01 Cimarron was conducting site remediation activities in preparation for the termination of Special Nuclear Material License SNM-928. Decommissioning inspections and radiological surveys had been conducted by the NRC at Cimarron as part of the overall confirmatory survey process.

This inspection was a continuation of that process. The licensee was authorized to bury soil contaminated with residual low-enriched uranium at the Cimarron site if the soil met the criteria of the NRC branch technical position (BTP) for soil. This inspection included reviewing final status survey records, performing exposure-rate and direct alpha and beta contamination measurements and collecting smear and soil samples from various locations within Sub-Areas H, I, and M to confirm compliance with the BTP Option 1 unrestricted release criteria. This inspection also included reviewing final status survey records and collecting soil samples from Pit 3, Lift 5 to confirm compliance and the buried soil release criteria in BTP Option 2.

Decommissioning, Closeout Survey, and Site Status

Site decommissioning activities were conducted in accordance with applicable license conditions and regulatory requirements. Site fences were in good condition and perimeter postings were appropriate. No health or safety hazards were identified (Section 1).

• Exposure-rate measurements, direct measurements of total alpha and beta contamination, smears and soil samples were collected from various locations within Sub-Areas H, I, and M. NRC confirmatory measurement results confirmed that these areas met the approved release criteria for BTP Option 1(Section 1).

• Soil samples were collected from Pit 3, Lift 5 during this inspection. Samples were collected from the same locations by both the NRC and the licensee. Analysis of the samples confirmed uranium and thorium levels were less than the BTP Option 2 and licensed limits for soil. No significant bias or statistical errors between the licensees soil results and the NRCs results were identified. Licensee soil measurement methods and counting times were found to be acceptable (Section 1).

Ambient gamma exposure rates on Lift 5 were measured and found to be less than the License Condition 27 release limit of 10 µR/hr above background (Section 1).

Report Details 1 Closeout Inspection and Survey (83890) 1.1 Inspection Scope The site status and decommissioning activities were reviewed to determine if activities were being conducted in accordance with the license, regulatory requirements and the Cimarron decommissioning plan. The Cimarron decommissioning plan committed to the recommendations in NUREG/CR-5849, Manual for Conducting Radiological Surveys in Support of License Termination. Confirmatory measurements were conducted during this inspection and included exposure-rate measurements, direct measurements of total alpha and beta contamination, smears and soil samples in Sub-Areas H, I, and M. Soil samples were also collected from Pit 3, Lift 5.

Release criteria approved for the Cimarron site were provided in Options 1 and 2 of the NRC Branch Technical Position (BTP), Disposal or Onsite Storage of Thorium and Uranium Wastes from Past Operations, 46 FR 52061, October 23, 1981. Under the Option 1 soil limits of the BTP, the licensee may dispose of wastes containing natural thorium, depleted and enriched uranium and natural uranium without restrictions for burial method or post-termination land use. Under Option 2, higher concentrations of natural thorium and depleted or enriched uranium are allowed without requiring land use restrictions after license termination when buried under prescribed conditions. Limits for Options 1 and 2 are provided in attachment 2 to this report as Table 1 Release Criteria.

1.2 Observation and Findings

a. Site Status The licensee's decommissioning plan was submitted to the NRC in April 1995 and approved in August 1999. The licensee had completed 99 percent of their remediation activities and was in the process of conducting soil sampling, radiation surveys and groundwater remediation to support license termination.

A site tour was conducted to verify that activities were being conducted in accordance with applicable regulations and license conditions. During the tour, buildings, fences, gates and operating equipment were observed. Security was maintained by site security personnel to prevent unauthorized access to the site. This included locked gates at entrances to the site property and visitor check-in at the main office. The inspectors determined that licensed material was secure within the site property as required by 10 CFR 20.1801.

b. Sub-Areas H, I & M and Building Confirmatory Surveys Uranium levels in soil for areas released for unrestricted use were required to meet Option 1 limits in the BTP. Option 1 established an acceptable release limit of 30 pCi/gm above background for uranium in soil. In addition to the uranium limits, the licensee was required to meet the release criteria in NMSS Policy and Guidance Directive FC 83-23 for smearable and fixed uranium contamination. These limits are provided in the attached Table 1: Release Criteria. The limits apply to the average alpha, beta and gamma levels. Maximum levels of 3 times these values are allowed for areas not to exceed 100 cm2.

The licensees procedures for collecting and preparing soil samples were reviewed, including observation of the licensee staff during collection and preparation of samples.

Sample techniques were found to be acceptable. Soil samples from Sub-Areas H, I, and M were collected for analysis by the NRC Region III laboratory. The soil samples were analyzed for total uranium content. Sample results are provided in the attached Tables 2 through 4. All soil sample results were below the 30 pCi/g criteria specified under BTP Option 1.

License Condition 27 established the release criteria for the site of 10 microRoentgens per hour (µR/hr) average and 20 µR/hr maximum, both above background at 1 meter.

Background radiation levels around the site averaged 7 µR/hr. Ambient gamma exposure rates were measured at each soil sample location. Ambient radiation levels were slightly above background with the highest reading measured at 10 µR/hr (i.e.

3 µR/hr above background). The confirmatory survey effort did not identify any new areas of contamination and supported the licensees conclusion that Sub-Areas H, I, and M met the approved release criteria.

Alpha and beta contamination and ambient gamma radiation levels were measured by the NRC inspectors in several buildings in Sub-Area I. Direct measurements for total alpha and beta contamination and smears for removable contamination were made at the TiO2 building, the emergency building and the plutonium building. Direct measurements were all below the 5,000 disintegrations per minute/100 centimeters squared (dpm/1002) limit. All smear sample results were below the average release criteria for removable contamination of 1,000 dpm/100 cm2. Results of these measurements are provided in the attached Tables 5 through 12 and were consistent with results obtained by the licensee. Building exposure rates provided with the tables are averages for the building and were below the 10 µR/hr above background limit.

The instruments used for exposure-rate and direct alpha and beta measurements were a Ludlum Model 19, Micro-R Meter, Serial #33541, (calibration due October 12, 2000), a Ludlum Model 2224 scaler with an alpha/beta probe Model 43-89, serial #114606, (calibration due August 30, 2000) and a Ludlum Model 19 MicroRoentgen meter calibrated to radium-226, NRC No. 015540, (calibration due October 12, 2000).

c. Site Status of Pit 3 The licensee was approved by License Condition 23 to bury up to 500,000 cubic feet of soil contaminated with low-enriched uranium in concentrations less than Option 2 of the BTP in an onsite disposal cell. The cell was comprised of three pits. Pits 1 and 2 were filled and capped. Pit 3 was still open. Lift 5 was the most recent and final lift to be installed in Pit 3. This lift was approximately 20 meters wide and 160 meters long.

Adjacent to the Lift 5 soil was a smaller lift of asphalt material that was authorized by the NRC for disposal in Pit 3. Samples of both the soil and the asphalt were collected and ambient gamma exposure rates were measured by the NRC inspectors to confirm compliance with site release criteria prior to the licensee permanently capping Pit 3 with clean soil.

d. Pit 3, Lift 5 Confirmatory Exposure Rate Survey Results Pit 3, Lift 5 exposure rates had been evaluated by the licensee using a portable sodium iodide (NaI) detector. Background radiation levels around the site averaged 7 µR/hr.

The NRC inspectors measured the ambient gamma exposure rates in all grids. The exposure rates were measured using an NRC-issued Ludlum Model 19 MicroRoentgen meter calibrated to radium-226 (NRC No. 015540, calibration due date of October 12, 2000). The inspectors measured an average background level of 8 µR/hr. Ambient exposure rates on Lift 5 varied from 7 to 14 µR/hr at 1 meter above the ground surface with the highest readings obtained near the former hot spot that was previously identified in Grid 510E-405N and remediated by the licensee. The NRC inspectors noted that the licensee measured exposure rates of 11 to 14 µR/hr on Lift 5.

License Condition 27 lists the release criteria. This condition states in part that the release criteria for soils is 10 µR/hr average and 20 µR/hr maximum both above background at 1 meter. With background subtracted, the exposure rates varied from below background up to 7 µR/hr above background. The inspectors concluded that the ambient gamma exposure rates on Lift 5 were less than the License Condition 27 release limit of 10 µR/hr above background for soils.

e. Pit 3 Lift 5 Confirmatory Surveys The inspector reviewed the licensees compliance with License Condition 23 for soil placed in Pit 3 Lift 5. The inspectors observed the sample storage and preparation area.

A licensee technician collected and prepared 20 soil samples and 4 asphalt samples for split-sample analysis with the NRC as part of the confirmatory survey process. The licensee used a sodium iodide detector to conduct soil analysis for uranium. Radiation Protection Procedure KM-CI-RP-47 was used for soil counter operations including operational and calibration checks, cesium-137 energy and efficiency checks, background determinations and sample counting. Total uranium was determined by using a scaling factor applied to the uranium-235 value. The licensees results concluded that the samples met the BTP Option 2 limit of 100 pCi/g uranium in Pit 3.

Further, the results indicate that the samples met the License Condition 23.b limit of 10 pCi/g for thorium.

The 24 split-samples collected for the NRC were sent to the NRC Region III laboratory for analysis on August 15, 2000. NRC sample results were compared with the licensees results and confirmed that uranium and thorium levels were below the license limits. Table 13 provides a summary of both the licensees results and the NRC results.

The licensees samples averaged 29.4 +/- 11.0 pCi/gm uranium in the soil in Pit 3 Lift 5.

The NRC results were consistent with the licensees results and averaged 28.8 +/- 9 pCi/gm.

The licensee had previously informed the NRC that the total uranium background level in soil was 4 pCi/g while the total thorium background was 1.5 pCi/g.

1.3 Conclusion Site decommissioning activities were conducted in accordance with applicable license conditions and regulatory requirements. Site fences were in good condition and perimeter postings were appropriate. No health or safety hazards were identified.

Exposure-rate measurements, direct measurements of total alpha and beta contamination, smears and soil samples were collected from various locations within Sub-Areas H, I, and M. NRC analysis results were consistent with the results obtained by the licensee and confirmed that these areas met the approved release criteria for BTP Option 1.

Soil samples were collected from Pit 3, Lift 5 during this inspection. Samples were collected from the same locations by both the NRC and the licensee. Analysis of the samples confirmed uranium levels were less than the BTP Option 2 limit for soil. Also, the thorium concentrations were below the licensed limit. No significant bias or statistical errors between the licensees soil results and the NRCs results were identified. Licensee soil measurement methods and counting times were found to be acceptable.

Ambient gamma exposure rates on Lift 5 were measured and found to be less than the License Condition 27 release limit of 10 µR/hr above background.

2 Exit Meeting Summary The NRC inspectors presented the inspection results to the licensee representatives at the conclusion of the onsite inspection on July 14 and August 15, 2000. A telephone exit was conducted on October 26, 2000, to discuss the result of the NRCs analysis of the split samples. Licensee representatives acknowledged the findings as presented.

The licensee did not identify as proprietary any information provided to, or reviewed by, the inspector.

ATTACHMENT 1 PARTIAL LIST OF PERSONS CONTACTED Cimarron Corporation J. Larsen, Site Manager and Vice President, Cimarron K. Morgan, Radiation Safety Officer Contractor Personnel S. Marshall, Nextep Environmental W. Rogers, Technical Consultant L. Smith, Quality Assurance Manager INSPECTION PROCEDURES USED IP 83890 Closeout Inspection and Survey IP 88104 Decommissioning Inspection Procedure for Fuel Cycle Facilities ITEMS OPENED, CLOSED AND DISCUSSED Closed None Opened None Discussed None LIST OF ACRONYMS ALARA As Low As is Reasonably Achievable ANSI American National Standards Institute BTP Branch Technical Position CFR Code of Federal Regulations dpm/100 cm2 disintegrations per minute/100 centimeters squared

µR/hr microRoentgen/hour pCi/g picocuries/gram PDR public document room QA quality assurance SNM special nuclear material

ATTACHMENT 2 TABLE 1: RELEASE CRITERIA TYPE OF SAMPLE RELEASE CRITERIA RELEASE CRITERIA ADJUSTED FOR BACKGROUND Exposure-rate (License 10 µR/hr average 17 µR/hr average Condition 27) 20 µR/hr maximum 27 µR/hr maximum Soil Concentration Around 30 pCi/gm Enriched Uranium 34 pCi/gm Buildings (Option 1)

Soil Concentration in the 100 pCi/gm Soluble Uranium 104 pCi/gm Soluble Pit (Option 2) 250 pCi/gm Insoluble Uranium 254 pCi/gm Insoluble Surface Concentration 5000 dpm/100cm2 (fixed) Not Applicable (FC 83-23) 1000 dpm/100cm (removable) 2 Note: Background values used were 7 µR/hr and 4 pCi/gm Uranium (Total)

TABLE 2: SUB-AREA H SOIL SAMPLES Sample Location Sample Depth Licensee Gross NRC Gross NRC Gross Result Results Exposure rate (pCi/gm) (pCi/gm) (µR/hr) 835N-33E 3-4 feet 5.7+0.6 2.0+0.7 7 395N-105E 1-2 feet Remediated to 3.5+0.6 6 Rock 425N-104E 1-2 feet 7.4+3.4 1.7+0.0 8 455N-102E 1-2 feet 6.7+2.9 2.1+0.7 10 290N-140E 0-6 inches 6.8+3.3 3.6+1.0 9 285N-155E 0-6 inches 2.4+2.4 3.4+1.0 10 320N-240E 0-6 inches 5.0+3.6 2.7+0.6 8 365N-108E 0-6 inches 4.5+3.3 2.1+0.8 8 365N-210E 1-2 feet 7.6+3.2 4.0+0.8 8 440N-95E 1-2 feet 10.6+3.4 1.8+0.0 8

TABLE 3: SUB-AREA I SOIL SAMPLES Sample Location Sample Depth Licensee Gross NRC Gross NRC Gross Result Result Exposure rate (pCi/gm) (pCi/gm) (µR/hr) 185N-95E 0-6 inches 13.0+3.0 3.9+0.7 8 220N-5E 0-6 inches 7.6+3.3 4.5+0.6 9 220N-5E 3-4 feet 11.5+2.8 1.8+0.8 9 200N-15E 0-6 inches 10.0+3.1 2.3+0.5 8 200N-15E 3-4 feet 8.6+2.5 0.8+0.4 8 10S-10E 0-6 inches 16.6+3.5 3.4+1.4 8 5N-10E 0-6 inches 14.6+3.7 4.5+0.9 9 220N-460E 0-6 inches 4.6+2.9 8.5+0.0 7 360N-450E 0-6 inches 7.1+3.6 11.2+0.0 10 TABLE 4: SUB-AREA M SOIL SAMPLES Sample Location Sample Depth Licensee Gross NRC Gross NRC Gross Result Result Exposure rate (pCi/gm) (pCi/gm) (µR/hr) 315E-255N 2-3 feet 6.0+3.0 3.4+0.5 8 320E-240N 2-3 feet 3.6+3.0 1.9+0.5 8 335E-270N 0-0.5 foot 9.1+3.2 7.6+3.0 8 305E-265N 2-3 feet 7.5+2.8 2.3+0.6 7 290E-330N 0.5-1 foot 4.1+3.2 2.3+1.0 8 305E-265N 3-4 feet 7.5+3.0 1.4+0.6 7

TABLE 5: SUB-AREA I, TiO2 BUILDING ROOF Sample Licensee Direct NRC Direct Licensee Smear NRC Smear Location (dpm/100cm2) (dpm/100cm2) (dpm/100cm2) (dpm/100cm2)

Alpha Beta Alpha Beta Alpha Beta Alpha Beta 43 1840 4650 22 0 4 16 0 0 82 1310 4270 198 2160 4 12 0 1 103 1270 4120 1309 2190 4 12 8 16 107 1570 4200 869 2985 7 4 12 8 119 2040 5380 495 1545 4 16 9 13 205 1440 5900 308 1590 10 13 10 11 211 810 4060 396 1365 2 14 0 0 224 1150 4010 616 1230 12 13 5 4 229 600 4550 230 1290 2 2 1 1 256 940 4710 297 1650 4 14 1 0 284 290 4090 143 2295 0 2 1 0 290 1600 4890 187 1410 10 13 0 0 319 1610 4060 187 1260 7 9 0 0

Background:

Alpha = 2 cpm; Beta= 92 cpm. All values are corrected for background.

TABLE 6: SUB-AREA I TiO2 BUILDING OUTSIDE WALLS Sample Licensee Direct NRC Direct Licensee Smear NRC Smear Location (dpm/100cm2) (dpm/100cm2) (dpm/100cm2) (dpm/100cm2)

Alpha Beta Alpha Beta Alpha Beta Alpha Beta 5 120 80 44 0 5 4 4 5 15 0 160 0 0 0 2 0 1 16 10 210 11 0 0 0 0 0 26 120 530 99 450 0 7 0 0

Background:

Alpha = 2 cpm; Beta= 86 cpm. All values are corrected for background.

Exposure-rate measurements at locations adjacent to the outside wall ranged from 5 to 9 µR/hr.

TABLE 7: SUB-AREA I TiO2 BUILDING INSIDE WALLS Sample Licensee Direct NRC Direct Licensee Smear NRC Smear Location (dpm/100cm2) (dpm/100cm2) (dpm/100cm2) (dpm/100cm2)

Alpha Beta Alpha Beta Alpha Beta Alpha Beta 6 90 0 0 0 0 0 0 0 19 0 0 0 0 2 0 0 0 23 0 0 0 0 2 0 0 0

Background:

Alpha = 2 cpm; Beta= 86 cpm. All values are corrected for background.

Exposure-rate measurements adjacent to sample locations on inside wall ranged from 5 to 7 µR/hr.

TABLE 8: SUB-AREA I TiO2 BUILDING UNAFFECTED FLOORS Sample Licensee Direct NRC Direct Licensee Smear NRC Smear Location (dpm/100cm2) (dpm/100cm2) (dpm/100cm2) (dpm/100cm2)

Alpha Beta Alpha Beta Alpha Beta Alpha Beta 8 50 792 11 375 0 2 0 0 10 40 198 0 0 0 0 0 0 15 30 1804 22 555 0 4 0 2 20 20 1056 0 570 0 0 0 0 22 60 1056 0 405 2 2 0 0 25 20 561 33 750 0 0 0 0 29 50 869 66 585 0 2 1 0

Background:

Alpha = 2 cpm; Beta= 92 cpm. All values are corrected for background.

Exposure-rate measurements at the sample locations ranged from 6 to 9 µR/hr.

TABLE 9: SUB-AREA I TiO2 BUILDING AFFECTED FLOORS Sample Licensee Direct NRC Direct Licensee Smear NRC Smear Location (dpm/100cm2) (dpm/100cm2) (dpm/100cm2) (dpm/100cm2)

Alpha Beta Alpha Beta Alpha Beta Alpha Beta 1 250 2520 319 2490 0 2 0 0 8 250 1100 11 600 0 0 0 0 12 190 2410 121 2385 0 0 0 0 21 240 3450 176 4185 0 2 1 0 30 190 2670 0 645 0 12 0 0 42 60 2060 44 855 0 2 0 0 54 270 1820 77 795 0 0 0 0 60 270 1950 66 945 2 2 0 0 88 240 1340 297 735 4 6 1 0

Background:

Alpha = 2 cpm; Beta= 92 cpm. All values are corrected for background.

Exposure-rates measurements taken at each sample location ranged from 6 to 9 µR/hr.

TABLE 10: SUB-AREA I EMERGENCY BUILDING INSIDE WALLS Sample Licensee Direct NRC Direct Licensee Smear NRC Smear Location (dpm/100cm2) (dpm/100cm2) (dpm/100cm2) (dpm/100cm2)

Alpha Beta Alpha Beta Alpha Beta Alpha Beta 34 27 170 0 0 0 6 0 0 200 56 127 11 0 0 4 0 0 202 9 236 0 0 2 1 0 0 265 27 306 0 0 0 0 0 0

Background:

Alpha = 2 cpm; Beta= 97 cpm. All values are corrected for background.

Exposure-rate measurements taken inside the emergency building ranged from 5 to 9 µR/hr.

TABLE 11: SUB-AREA I EMERGENCY BUILDING FLOORS Sample Licensee Direct NRC Direct Licensee Smear NRC Smear Location Alpha Beta Alpha Beta Alpha Beta Alpha Beta 2 36 414 0 360 0 0 0 0 31 18 420 0 0 0 1 0 0 45 45 400 0 75 0 4 0 0 57 18 450 22 30 0 0 0 0 79 18 370 0 15 0 1 0 0 117 27 306 22 240 0 0 1 0 159 18 702 0 570 2 0 0 3 163 36 729 11 270 0 2 0 0

Background:

Alpha = 2 cpm; Beta= 97 cpm. All values are corrected for background.

Exposure-rate measurements taken inside the emergency building ranged from 5 to 9 µR/hr.

TABLE 12: SUB-AREA I PLUTONIUM BUILDING FLOORS NRC Direct NRC Smear Sample Location Alpha Beta Alpha Beta On floor just inside front Door of Guard Shack 0 0 0 0 On floor just inside of 1st Door after entering Guard Shack 0 60 0 0 going into main building On floor in doorway to Room 105 (bare concrete) 33 1500 0 0 On floor in Room 129 0 375 0 0 On floor in Room 116 33 285 0 0 On floor in Room 124 22 645 0 0 On floor in rear (opposite of loading dock) of Rm121 22 540 0 0 On floor inside of loading dock roll up door 33 60 0 0

Background:

Alpha = 2 cpm; Beta= 100 cpm. All values are corrected for background.

TABLE 13: CONFIRMATORY SOIL SAMPLE RESULTS FOR PIT 3, LIFT 5 Grid Location NRC Results Licensee Results NRC Results Licensee Results Total Uranium Total Uranium Total Thorium Natural Thorium (pCi/g) (pCi/g) (pCi/g) (pCi/g) 510E-290N 17.1+1.0 12.3+3.4 1.6+0.0 2.5 +0.2 510E-310N 24.7+4.8 21.7+3.6 2.4+0.2 2.6 +0.2 510E-320N 24.4+3.7 27.6+3.3 1.4+0.1 1.8 +0.2 510E-335N 49.1+6.0 40.3+3.4 1.7+0.1 2.1 +0.2 510E-350N 22.9+4.1 19.6 +4.0 1.8+0.1 1.9 +0.2 510E-365N 22.7+1.9 18.9 +3.7 2.1+0.1 3.1+0.2 510E-380N 23.4+4.1 34.2+3.7 2.1+0.1 1.8 +0.2 510E-390N 28.5+1.2 36.1 +3.7 1.9+0.0 2.4 +0.2 510E-405N 48.6+2.0 42.4 +3.9 2.0+0.1 2.7+0.2 510E-415N 23.1+2.0 24.6 +3.6 1.7+0.1 2.2+0.2 515E-295N 21.3+4.5 23.6 +3.3 1.9+0.1 2.0 +0.2 515E-305N 29.9+3.7 29.8 +3.4 1.7+0.1 1.9+0.2 515E-315N 43.7+1.9 42.8 +3.6 1.5+0.1 2.0 +0.2 515E-325N 24.3+3.7 32.9 +3.4 1.7+0.1 2.0+0.1 515E-340N 45.1+6.5 31.9 +3.7 1.8+0.1 2.6+0.2 515E-350N 44.6+0.8 35.0 +3.5 1.8+0.1 1.9 +0.2 515E-365N 25.4+1.3 26.8 +3.6 1.9+0.0 2.9+0.2 515E-385N 33.6+4.0 29.4 +3.8 1.9+0.0 2.4+0.2 515E-400N 40.4+1.4 39.1+3.9 1.7+0.0 2.2+0.2 515E-415N 20.3+4.2 25.9 +3.6 2.1+0.1 1.7 +0.2 520E-290N 26.8+2.9 29.7+ 3.4 0.6+0.1 0.9+ 0.2 520E-315N 26.9+4.2 27.6+ 3.5 0.6+0.1 0.7+ 0.2 520E-340N 28.7+3.2 23.0+ 3.5 0.5+0.1 1.6+ 0.2 520E-360N 28.7+2.2 27.1+ 3.5 0.6+0.0 1.3+ 0.2