ML003685810

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IR070-0925/1999-002 of Kerr-McGee Center, Cimarron Site in Crescent, Oklahoma
ML003685810
Person / Time
Site: 07000925
Issue date: 02/23/2000
From: Chamberlain D
Division of Nuclear Materials Safety IV
To: Larsen S
Kerr-McGee Corp
Carson L
References
-RFPFR 1999002
Download: ML003685810 (14)


Text

February 23, 2000 Mr. S. Jess Larsen, Vice President Kerr-McGee Center P.O. Box 25861 Oklahoma City, Oklahoma 73125

SUBJECT:

NRC INSPECTION REPORT 70-925/99-02

Dear Mr. Larsen:

On December 15, 1999, the NRC concluded the onsite portion of an inspection of the Cimarron site near Crescent, Oklahoma. On February 14, 2000, the NRC held a telephonic exit briefing with you and a member of your staff concerning the results of the inspection and NRC analysis of confirmatory soil samples obtained during the inspection. The enclosed report presents the scope and results of the inspection.

This inspection covered the remediation and verification that soil in Sub-Area L met NRC release criteria. Soil sampling activities conducted by your staff were observed. Forty soil samples were collected from Sub-Area L for analysis by the NRC. Sub-Area L property included Burial Area 2, the Sanitary Lagoon, and the Emergency Plutonium Facility Pond. As part of the NRCs confirmatory sampling program for the Cimarron site, the results of these soil samples were compared with the results of the final status survey data from Sub-Area L soil samples collected at the same locations by Cimarron. The results of the 40 NRC soil samples were found to be consistent with the licensees analyses in that results met the NRCs release criteria. These confirmatory sample results provided additional assurance that residual soil contamination in Sub-Area L met the NRC Branch Technical Position Option 1 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 placed in the NRC Public Document Room. 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

Kerr-McGee Center

Enclosure:

NRC Inspection Report 70-925/99-02 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 Mike Broderick Radiation Management Section Waste Management Division Department of Environmental Quality State of Oklahoma 707 North Robinson Avenue Oklahoma City, Oklahoma 73102-6087 Oklahoma Radiation Control Program Director

Kerr-McGee Center E-Mail report w/enclosure to Document Control Desk (DOCDESK)

E-Mail report w/enclosure to D. Lange (DJL) bcc w/enclosure to DCD (IE-07) bcc w/enclosure distrib. by RIV:

EWMerscoff MCLayton, NMSS (T7J8)

KLKalman, NMSS (T8F37)

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

DOCUMENT NAME: s:\dnms\fcdb\lcc\90092502.wpd To receive copy of document, indicate in box: "C" = Copy without enclosures "E" = Copy with enclosures "N" = No copy RIV:DNMB:FCDB FCDB C:FCDB D:DNMS LCCarsonII DLRice /RA/ DBSpitzberg /RA/ DDChamberlain /RA/

02/ /00 02/17/00 02/17/00 02/17/00 OFFICIAL RECORD COPY

ENCLOSURE U. S. NUCLEAR REGULATORY COMMISSION REGION IV Docket No.: 70-925 License No.: SNM-928 Report No.: 70-925/99-02 Licensee: Cimarron Corporation Kerr-McGee Center Oklahoma City, Oklahoma 73125 Facility: Cimarron Site Location: Crescent, Oklahoma Dates: December 15, 1999 and February 14, 2000 Inspectors: Louis C. Carson II, Health Physicist Fuel Cycle & Decommissioning Branch Danny L. Rice, Health Physicist, CHP Fuel Cycle & Decommissioning Branch Approved By: D. Blair Spitzberg, PhD., Chief Fuel Cycle & Decommissioning Branch

Attachment:

Supplemental Information

EXECUTIVE

SUMMARY

Cimarron Corporation, Cimarron Site NRC Inspection Report 70-925/99-02 Cimarron is conducting site remediation activities in preparation for the termination of License SNM-928. Decommissioning inspections, radiological surveys, and analysis of surface and subsurface soils have been conducted at Cimarron as part of the overall NRC confirmatory survey process. This inspection was a continuation of this process. The licensee is authorized to bury soil contaminated with residual low-enriched uranium at the Cimarron site, if the soil meets the criteria of the NRC branch technical position (BTP) for soil. Sub-Area L property included Burial Area 2, the Sanitary Lagoon, and the Emergency Plutonium Facility Pond. The Sub-Area L subsurface soils had been analyzed and determined to meet the release criteria, as documented in a letter from the NRC to the licensee dated November 8, 1996. This inspection focused on reviewing final status survey records and collecting surface soil samples from Sub-Area L to confirm compliance with the license and BTP soil limits. This inspection also included a review of the sites decommissioning status.

Decommissioning, Closeout Survey, and Site Status C 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).

  • Forty soil samples were collected from Sub-Area L during this inspection. The samples were collected from the same locations by both the NRC and the licensee as part of the NRC confirmatory survey program (Section 1).

C NRC measurements of 40 soil samples from Sub-Area L showed that the samples met the concentration guidelines values required to meet BTP Option 1 criteria (Section 1).

C Radiation exposure rate levels at Sub-Area L were less than 10 µR/hr above background levels (Section 1).

Report Details 1 Decommissioning Inspection Procedure for Fuel Cycle Facilities, Closeout Inspection and Survey, Site Status (83890/88104) 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 commits the licensee to follow the recommendations in NUREG/CR-5849, Manual for Conducting Radiological Surveys in Support of License Termination.

As part of the NRC confirmatory surveys process, 40 soil samples from Sub-Area L were collected for analysis by the NRC. The samples were analyzed for total uranium in soil to determine if the samples met the requirements of the license, BTP, and NUREG/CR-5849 for uranium in soil samples.

1.2 Observation and Findings

a. Site Status Cimarron is in the final stages of site remediation in preparation for termination of its nuclear materials license. The licensee's decommissioning plan was submitted to the NRC in April 1995 and approved in August 1999. The licensees activities have been coordinated with the cognizant project manager in the Office of Nuclear Materials Safety and Safeguards. The licensee's current activities included soil sampling, radiation surveying, groundwater remediation, and facility maintenance. Remediation at the Cimarron site was more than 99 percent complete. Sub-Area L final soil remediation efforts had been underway by Cimarron since 1978. Sub-Area L property included Burial Area 2, the Sanitary Lagoon, and the Emergency Plutonium Facility Pond. Final survey activities for the site were in progress. This inspection was a continuation of the NRCs confirmatory survey program for the Cimarron site.
b. Site Tour A site tour was performed to verify that activities were being conducted in accordance with applicable regulations and license conditions to ensure that controls were adequate to protect the health and safety of the workers and the public. During the tour, buildings, fences, gates, and operating equipment were observed. The inspector noted that security was maintained by site security personnel who prevented unauthorized access to the site. The licensee maintained locked gates at entrances to site property, and visitors were required to check in at the main office when accessing the site property.

The inspector determined that licensed material was secure within the site property as required by 10 CFR 20.1801. Additionally, fences were posted with radioactive material signs as required by 10 CFR 20.1902.

c. Confirmatory Radiation Soil and Sediment Sampling Forty surface soil samples from Sub-Area L were collected for analysis by the NRC.

The samples were analyzed for total uranium to determine if the samples met approved concentration values. All samples were obtained at a depth of 0-0.5 ft. from the surface.

Sub-Area L subsurface contamination had been previously determined to meet the BTP Option 1 average residual uranium concentration of 30 picocuries/gram (pCi/g) total uranium. This was documented in the NRC letter dated November 8, 1996. The inspector reviewed the licensees procedures for collecting and preparing soil and sediment samples and observed licensee staff collect and prepare the samples for analysis by the NRC.

The NRC soil samples were sent to the NRC Region III laboratory for analysis on December 15, 1999. All 40 of the Sub-Area L samples were determined to have concentrations below the 30 pCi/g criteria specified under BTP Option 1. The results of the NRC confirmatory surveys did not identify any new areas of contamination.

Additionally, the confirmatory survey results supported the licensees conclusion the soil in Sub-Area L met the approved criteria specified in the BTP and averaging criteria. The following table shows the results of the confirmatory soil and sediment samples at and around Sub-Area L.

Confirmatory Soil and Sediment Sample Results For Sub-Area L Location Sample Depth Sample Mass NRC Results (Sample #) (feet) (grams) U (pCi/g) 1 0-0.5 816 15.3 215N\35E 2 0-0.5 762.2 14.0 215N\75E 3 0-0.5 827.2 16.1 220N\85E 4 0-0.5 761.3 15.9 220N\100E 5 0-0.5 738.2 19.7 210N\100E 6 0-0.5 726.4 16.1 230N\100E 7 0-0.5 804.6 15.9 230N\75E 8 0-0.5 800.2 13.4 235N\60E 9 0-0.5 826.2 14 250N\45E 10 0-0.5 877.5 12.3 255N\60E 11 0-0.5 798.4 14.3 260N\95E 12 0-0.5 714.8 15.4 280N\100E

Confirmatory Soil and Sediment Sample Results For Sub-Area L Location Sample Depth Sample Mass NRC Results (Sample #) (feet) (grams) U (pCi/g) 13 0-0.5 866.8 11.1 295N\70E 14 0-0.5 678.2 16 275N\30E 15 0-0.5 771.9 17 310N\25E 16 0-0.5 783.7 6.1 315N\50E 17 0-0.5 761.7 11.7 325N\95E 18 0-0.5 742.7 11.0 310N\105E 19 0-0.5 822.6 13.7 235N\115E 20 0-0.5 742.2 19.9 225N\110E 21 0-0.5 775.2 14.7 205N\120E 22 0-0.5 834.7 14.1 205N\140E 23 0-0.5 787.6 14.1 220N\140E 24 0-0.5 746 10.8 205N\150E

Confirmatory Soil and Sediment Sample Results For Sub-Area L Location Sample Depth Sample Mass NRC Results (Sample #) feet U (grams) U (pCi/g) 25 0-0.5 769.3 14.9 195N\145E 26 0-0.5 784.8 23.2 185N\160E 27 0-0.5 748 29.6 195N\180E 28 0-0.5 755.7 13.2 185N\190E 29 0-0.5 778.7 14.5 195N\165E 30 0-0.5 694.5 19.2 155N\210E 31 0-0.5 749.5 11.6 150N\225E 32 0-0.5 696.4 20.5 140N\230E 33 0-0.5 714.8 13.5 175N\230E 34 0-0.5 755.5 13.9 160N\245E 35 0-0.5 831 13.0 215N\255E 36 0-0.5 840.7 3.75 195N\260E

Confirmatory Soil and Sediment Sample Results For Sub-Area L Location Sample Depth Sample Mass NRC Results (Sample #) feet (grams) U (pCi/g) 37 0-0.5 748 15.6 145N\260E 38 0-0.5 797.9 13.7 135N\270E 39 0-0.5 719.2 9.1 150N\295E 40 0-0.5 734.9 17.2 115N\275E

d. Confirmatory Exposure Rate Survey Results Sub-Area L exposure rates had been evaluated by the licensee using a portable sodium iodide (NaI) detector. Background radiation levels around the site averaged 7 microRoentgen per hour (µR/hr). Sub-Area L radiation levels measured by the licensee averaged 8 µR/hr. Confirmatory exposure rate surveys were performed by the inspector using a portable NaI detector (Ludlum Model 19, NRC#015546, calibrated 10/12/99) at the Sub-Area L sample locations. Site background readings measured by the inspector averaged 11 µR/hr. The inspectors Sub-Area L measurements were 8-15 µR/hr, and no hot-spots were found during the inspectors survey. The inspectors concluded that radiation exposure levels at Sub-Area L were less than the release limit of 10 µR/hr above background.

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

NRC measurements of 40 soil samples from Sub-Area L showed that the samples met the release criteria. Radiation exposure levels at Sub-Area L were less than 10 µR/hr above background levels.

2 Exit Meeting Summary The inspector presented the inspection results to the licensees representatives at the conclusion of the onsite inspection on December 15, 1999, and during telephone conversations on February 14, 2000. 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 SUPPLEMENTAL INFORMATION 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 83822 Radiation Protection 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 PDR public document room QA quality assurance SNM special nuclear material