Cimarron Corp Final Status Survey Plan for Sub-Area 'O ... · letter transmits the Final Status Survey Report£ r Sub-Area "O" Surface. Please find enclosed three (3) copies of the

CIMARRON l10RPORATION P 0 . BOX 25861 • OKLAHOMA CITY, OKLAHOMA 73125

February 9, 1999

Mr. Ken Kalman, Project Manager Facilities Decommissioning Section Low-Level Waste & Decommissioning Projects Branch Division of Waste Management , Office of Nuclear Material Safety_ and Safeguar4s U.S. Nuclear Regulatory Commission I

Washington. D.C. 20555-0001

Re: Docket No. 70-925; License No. SNM-l 28 Cimarron Corporation f Final Status Survey Plan for Sub-Aret "0" Surface

Dear Mr. Kalman: I

Cimarron Corporation has recently completed t e Final Status Survey for Sub-Area "O" Surface in accordance with the previously approved Pha e III Final Status Survey Plan. This submittal letter transmits the Final Status Survey Report£ r Sub-Area "O" Surface.

Please find enclosed three (3) copies of the repo for your review and approval. One (l) copy of this report has been submitted to the NRC Dock t and one (1) copy has been provided to Mr. Louis Carson with NRC Region IV.

Cimarron Corporation requests that Sub-Area" · "be released from License No. SNM-928.

Please feel free to contact me if there are any adbitional questions or concerns.

Sincerely,

~·~ o/fe:: ~arsen Vice President Enclosure

[

A SUBSIDIARY OF KERR·MCGEECORPORA110N

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FINAL STATUS ~URVEY REPORT SUBAREAlo (Surface)

Cimarron Corp ration's Former Nuclear Fuel Fa rication Facility

Crescent, Oklahoma

License Numler: SNM-928

Prepa ed for:

Cimarron orporation Oklahoma C ty, Oklahoma

February 1999

• TABLE OF ONTENTS

1.0 PURPOSE .................................................... J ............................................................................ l

2.0 BACKGROUND ........ .................... ....... .................................................................................. 1

2.1 Phase I Area ........................................................................................................................ 2

2.2 Phase II Area .... ............................................................ .. .......................... .......................... 2

2.3 Phase III Area ......................................................................................................... .. ......... 3

3.0 DECOMMISSIONING ACTIVITIES .................................................................................... 3

3 .1 Identification of Contaminants ..... ..................... .... ...... ...... .... ...... ...... .. .............................. 4

3.2 Site Background Levels ..................................................................................................... 4

3.2.1 Soils ........................................................................................................................... 4

3.2.2 Exposure Rate ............................................................................................................ 4

3 .3 Characterization Data .................................... ...... .... ....................... ........... ......................... 4

3 .4 Environmental Monitoring Data............. . .......................................................................... 4

4.0 FINAL STATUS SURVEY PROCEDURE ................................................... ... ................... .. .4

• 4.1 Survey Method ................................................................................................................... 4

4.1.1 Grid Areas .................................................................................................................. 4

4.1.2 Survey Locations (Open Land Area ) ......................................................................... 4

4.1.3 Soil Sample Locations ....... ............................................ ...... .................................. .. .. 4

4.2 Radiological Guideline Values ......................................... ..... .. ..... ... .................................. 4

4.2.1 Equipment and Materials ........................................................................................... 4

4.2.2 Volumetric Activity of Soil ....................................................................................... 4

4.2.3 Gamma Surface Survey (Open Lan Areas) .............................................................. 4

4.2.4 Exposure Rate Survey (Open Land ~reas) ................................................................. 4

4.3 Equipment Selection ............................... j ........................................................................... 4

4.3.l Equipment and Instrumentation ...... j ........................................................................... 4 I

4.3.1.1 Unshielded 3" x 0.5'' NaI Gamm4 Detector.. .......................................................... 4

4.3.1.2 Shielded 3" x 0.5'' Nal Gamma tjetector. ............. ..... ............................................. 4

4.3.1.3 Micro-R Meters ................... .. ...... ; ............ ............................................................... 4

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4.3.1.4 Soil Counter (Gamma Spectrosctjpy) ..................................................................... 4 I

Procedures/Plan.s ..................................... ! ........................................................................... 4

FSSR SUBAREA O (Surface)

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• 4.4.1 Organization ............................................................................................ ............... ... . 4

4.4.2 Training .............. ............................... ......................................................................... 4

4.4.3 Radiation Protection Program ................................ .................................................... 4

4.4.4 Cimarron Quality Assurance Prog am (QAP) ................................. ........................... 4

5.0 SURVEY FINDINGS ............................... ................................... ....................................... .... 4

5.1 Data Evaluation .................................................................................................................. 4

5.2 Comparison with Guideline Values ...................................................................... ............. 4

5.2.1 U-Pond #1 Data Evaluation ....................................................................................... 4

5.2.2 U-Pond #2 Data Evaluation ....................................................................................... 4

5. 3 QA/QC Procedures ............................................................................................................ 4

6.0 SUMMARY ............................................................................................................................ 4

7.0 APPENDICES ........................................................................................................................ 4

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• FSSR SUBAR£A O (Surface) 11

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• Appendix 1

• Appendix 2

• Appendix 3


Drawing 95 MO$T-RF3

Data Tabulation Sheet, Statistical Analyses and Drawings for UPond #1

Data Tabulation Sheet, Statistical Analyses and Drawings for UPond #2

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RELRENCES I

1. Cimarron Corporation Nuclear Materials Lilense, SNM-928 Docket No. 70-0925, issued for possession only March 31, 1983; Amendme' t No. 14, issued July 7, 1997.

2. Cimarron Corporation Nuclear Materials License, SNM-1174, Docket No. 070-1193, terminated February 5, 1993.

3. Cimarron Corporation letter to USNRC, Au ust 20, 1990.

4. USNRC letter from Mr. Richard E. Cu · ngham, Director, Division of Industrial and I\-1edical Nuclear Safety to Dr. John Staute , Director of Environmental Services, Cimarron Corporation, dated February 5, 1993.

5, Chase Environmental Group, Inc. "Radi logical Characterization Report for Cimarron Corporation's Former Nuclear Fuel Fabricat on Facility, Crescent, Oklahoma", October 1994.

6. Chase Environmental Group, Inc. "Deco missioning Plan for Cimarron Corporation's Former Nuclear Fuel Fabrication Facility, C escent, Oklahoma", April 1995.

7. Chase Environmental Group, Inc. ,,Final Status Survey Plan for Unaffected Areas for Cimarron Corporation's Former Nuclear uel Fabrication Facility, Crescent, Oklahoma", October 1994 .

8. USNRC letter from Mr. Michael F. Weber Chief Low-Level Waste and Decommissioning Project Branch, Division of Waste Manag ment, to Mr. Jess Larsen, Vice President Kerr~ McGee Corporation, dated May 1, 1995.

9. Cimarron Corporation Letter from Mr. Jess Larsen, Vice President, Cimarron Corporation to Mr. Michael F. Weber, Chief Low-Level aste and Decommissioning Branch, Division of Waste Management, USNRC, dated Novem~er 13, 1995.

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I 0. Cimarron Corporation, ''Final Status Survey Report, Phase I Areas at the Cimarron Facility, License No. SNM-928", July 1995. '

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11. USNRC letter from Mr. R. A. Nelson Acting Chief Low-Level Waste and Decommissioning Project Branch, Division of Waste Man~gement, to Mr. Jess Larsen, Vice President, Cimarron Corporation, dated April 23, l 996~

i 12. Chase Environmental Group, Inc., "Final Status Survey Plan for Phase 11 Areas for Cimarron

Corporation's Former Nuclear Fuel Fabricat~on Facility", Crescent, Oklahoma, July 1995.

13. USNRC letter from Mr. Kenneth L. Ka~an, Project Manager, Low-Level Waste and Decommissioning Projects Branch, to Mr. Jess Larsen, Vice President, Cimarron Corporation, dated March 14, 1997.

FSSR SUBAREA O (Surface) IV

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14. USNRC letter from Mr. George M. McCJ, Chief, Materials Licensing Section to D. r. John Stauter, Vice President, Kerr-McGee Cofl)~1ation, dated December 30, 1992. .

! 15. Cimarron Corporation, ""Final Status Su

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ey Report, Phase II-Subarea J for Cimarron Corporation's Former Nuclear Fuel Fabric tion Facility, Crescent, Oklahoma'\ September 1997.

16. USNRC letter from Mr. Kenneth L. Ka man, Project Manager, Low-Level Waste and Decommissioning Project Branch, to Mr. Je s Larsen, Vice President, Cimarron Corporation, dated July 31, 1998.

17. USNRC letter from Mr. Kenneth L. Ka man, Project Manager, Low-Level Waste and Decommissioning Project Branch, to Mr. Je s Larsen, Vice President, Cimarron Corporation, dated December 4, 1998.

18. Cimarron Corporation, "Final Status S rvey Report for Subarea H for Cimarron Corporation's Former Nuclear Fuel Fabric tion Facility, Crescent, Oklahoma", November 1998.

19. Cimarron Corporation, "Final Status Su ey Report for Concrete Rubble in Subarea F, Cimarron Corporation's Former Nuclear uel Fabrication Facility, Crescent, Oklahoma", March 1998 .

20. Chase Environmental Group, Inc. "Fin Cimarron Corporation's Former Nuclear June 1997.

Status Survey Plan for Phase III Areas for uel Fabrication Facility", Crescent, Oklahoma,

21. USNRC letter from Mr. Kenneth L. Kalm n, Project Manager, Facilities Decommissioning Section to Mr. Jess Larsen, Vice President, imarron Corporation, dated September 11, 1998

22. Cimarron Corporation, "Final Status Surv y Report, Phase III-Subarea L (Subsurface) for Cimarron Corporation's Former Nuclear uel Fabrication Facility, Crescent, Oklahoma", May 1996.

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23. USNRC letter from Mr. Kenneth L. Kalm~n, Project Manager, Facilities Decommissioning Section, to Mr. Jess Larsen, Vice President, Fimarron Corporation, dated August 16, 1996.

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24. Cimarron Corporation letter from Mr. Jess ~arsen, Vice President Cimarron Corporation, to Mr. Kenneth L. Kalman, Project Manage~ Facilities Decommissioning Section, USNRC, dated September 9, 1996. ·

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25. Cimarron Corporation letter from Mr. Jess t· arsen, Vice President, Cimarron Corporation, to Mr. Kenneth L. Kalman, Project Manager Facilities Decommissioning Section, USNRC, dated October 17, 1996. !

FSSR SUBAREA O (Surface) V

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26. Cimarron Corporation letter from Mr. Jessj Larsen, Vice President Cimarron Corporation to Mr. Kenneth L. Kalman, Project Manage , Facilities Decommissioning Section, USNRC, dated November 4, 1996.

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27. USNRC letter from Mr. Kenneth L. Kalm , Project Manager, Facilities Decommissioning Section, to Mr. Jess Larsen Vice President, imarron Corporation, dated November 8, 1996.

28. Cimarron Corporation letter from Mr. Jess Larsen, Vice President, Cimarron Corporation to Mr. Kenneth L. Kalman, Project Manage , Facilities Decommissioning Section, USNRC, dated July 27, 1998.

29. Cimarron Corporation, "Final Status Surve ' Report Phase III - Subarea HO" Subsurface for Cimarron Corporation's Former Nuclear uel Fabrication Facility, Crescent, Oklahoma", dated March 1998.

30. Cimarron Corporation, "Final Status Surv y Report Phase III - Subarea "M" for Cimarron Corporation's Former Nuclear Fuel Fa rication Facility, Crescent, Oklahoma", dated December 1998

31. Cimarron Corporation letter from Mr. Jess arsen, Vice President, to Mr. Michael F. Weber, Chief Low-Level Waste and Decom 1ss1on Projects Branch, Division of Waste Management, USNRC, dated June 21, 1995 .

32. ORAU Final Report, "Confirmatory Surve of the Cimarron Corporation Mixed Oxide Fuel Fabrication Plant", January 1991.

33 . Kerr-McGee Corporation, "Decommissio ing Plan - Groundwater Evaluation Report for Cimarron Corporation's Former Nuclear ue] Fabrication Facility, Crescent, Oklahoma," July 1998.

34. USNRC letter from Mr. Kenneth L. K man, Project Manager, LO\v-Level Waste and Decommissioning Projects Branch, to Mr. Jess Larsen, Vice President, Cimarron Corporation, dated January 19, 1999. l

35. J. D. Berger, 11 Manual for Conducting i Radiological Surveys in Support of License Termination"; Draft Report for Comment, Oak Ridge Associated Universities, NUREG/CR-5849, June 1992.

36. USNRC, "Guidelines for Decontaminationi of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of LiceJ)ise for By-Product, Source , or Special Nuclear Material", August 1987.

37. USNRC, "Branch Technical Position on ~isposal or On-site Storage of Residual Thorium and Uranium from Past Operations", FR. Vpl. 46, No. 205, Page 52061, October 23, 1981.

FSSR SUBAREA O (Surface) vi

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i 38. American National Standards Institute, "Radiation Protection Instrumentation Test and

Calibration 11, ANSI N323-l 978, Institute ! of Electrical and Electronic Engineers, Inc.

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September 1977. : i I

39. Cimarron Corporation, "Response to NRC Qomments on Cimarron's Final Status Survey for Phase II, Subarea "J" for Cimarron Corpora ion's Former Nuclear Fuel Fabrication Facility, Crescent, Oklahoma", dated May 13, 1998.

40. USNRC letter from Mr. Ross A. Scarano, Director Division of Nuclear Materials Safety, Region IV, to Mr. S. Jess Larsen, Vice Presi ent, Cimarron Corporation, dated July 31, 1997.

41. E.W. Abelquist, "Confirmatory Survey fo the South Uranium Yard Remediation, KerrMcGee Corporation, Cimarron Facility, rescent, Oklahoma", Oak Ridge Institute for Science and Education, November 1995.

42. USNRC letter from Mr. Michael F. Weber, Chief, Low-Level Waste and Decommissioning Project Branch, Division of Waste Manage ent to Mr. Jess Larsen, Vice President, KerrMcGee Corporation, dated May 31, 1995.

43 . USNRC letter from Mr. Ross A. Scarano, irector, Division of Nuclear Materials Safety, Region IV to Mr. S. Jess Larsen, Vice Presi ent, Cimarron Corporation, dated November 3, 1998 .

44. American Society of Mechanical Engineers "Quality Assurance Requirements for Nuclear Facility Applications" ASME NQA-1, 1994 .

FSSR SUBAREA O (Surface) Vil

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' FINAL STATUS SURVEY REPPRT FOR DECOMMISSIONING

CIMARRON FACILIT~ SUBAREA O (Surface) !

1.0 PURPOSE

This Final Status Survey Report (FSSR) is b ing submitted by Cimarron Corporation to the Nuclear Regulatory Commission (NRC) for t e surface area located on the Cimarron site and designated as Phase III Subarea 0. This Su area is shown on Drawing No. 95MOST-RF3, which is included in Appendix 1, and include only affected areas that have been surveyed as part of the ongoing site decommissioning pr cess. A FSSR for the subsurface soils located within Subarea O was submitted to the NRC i March 1998, and this Report is presently under review by the NRC.

Based upon the Phase III FSSP, the Subarea O FSS was performed for the entire surface area to demonstrate that the established guideline va es for umestricted release had been met. The results of the Subarea O (Surface) FSS are pre ented in this FSSR as justification for release of this Subarea from License SNM-928 for umest icted use.

2.0 BACKGROUND

Cimarron Corporation, a subsidiary of Kerr McGee Corporation, operated two plants near Crescent, Oklahoma, for the manufacture of miched uranium and mixed oxide reactor fuels . The 840-acre Cimarron Facility site was origi ally licensed under two separate SNM Licenses. License SNM-928 1 was issued in 1965 for the ranium Plant (U-Plant) and License SNM-11742

was issued in 1970 for the Mixed Oxide Fu I Fabrication (MOFF) Facility. Both facilities operated through 1975, at which time they ere shut down and decommissioning work was initiated.

Decommissioning efforts at the MOFF Fa ility were completed in 1990 and Cimarron Corporation applied to the NRC on August 2 , 19903 to terminate License SNM-1174. After confinnatory surveys, the NRC terminated the MOFF Facility License, SNM-1174, on February 5, 19934

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Decommissioning efforts at the Cimarroit U-Plant facility involving characteriz.ation, decontamination and remediation were initiated in 1976 and are nearing completion. The goal of the decommissioning effort is to release the ent~re 840-acre site for unrestricted use.

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Based upon historic knowledge of site operat~ons and the characterization work completed to date, Cimarron Corporation completed anq. submitted the 1994 Cimarron Radiological Characterization Report5 to the NRC. As di~cussed in that report, the site was divided into affected and unaffected areas. The affected ~nd unaffected areas are shown on Drawing No. 95MOST-RF3 which is included in Appendix ~- For the final status survey the entire 840-acre site was divided into three major areas contai¥ng both affected and unaffected areas. Each of these three major areas are shown on DrawingJNo. 95MOST-RF3 and are designated by Roman Numerals I, II, and III (herein referenced as Phases I, II, and III). These three major areas \Vere


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then further subdivided into smaller '"subareas" ke., A, B, C, D, etc.). The FSSP's for the Phase I, II and III areas have been approved by the N~; the three areas are discussed briefly below:

2.1 Phase I Area

2.2

As presented in the Cimarron Decomm·ssioning Plan6, the FSSP's (Phases I, II and III)

were discussed in general terms, with t e understanding that each of these three phases would be submitted to the NRC under s parate cover for approval. The area designated as Phase I on Drawing No. 95MOST- 3 contain only unaffected areas and represents approximately 688-acres. The FSSP £ r the first of these three phases (Phase r7) was approved by the NRC by letter dated M y 1, 19958

. By letter dated November 13, 19959,

Cimarron modified the southern bound of two Phase I areas (i.e., Subareas C and E) and placed these portions of Subareas and E into Phase II Subareas G and H. The Phase I FSSR 10 was submitted to the RC and confirmatory sampling for the Phase I Subarea was completed by the Oak Rid e Institute for Science and Education (ORJSE). Cimarron Corporation received Amend ent # 13 which released all of the Phase I areas from License SNM-928; the amendmen was forwarded to Cimarron by NRC letter dated April 23, I 996 11

• This amendment re uced the licensed facility acreage from 840 to approximately 152 acres.

Phase II Area

The area designated as Phase II on Dr wing No. 95MOSTwRF3 contains both affected and some contiguous unaffected areas d represents approximately 122 of the remaining licensed 152-acres. The Phase II FSS was submitted to the NRC in July 1995 12 and approved on March 14, 199i3

. Phase I includes Subareas F, G, H, I and J. Included within Phase II is Burial Area# 1 whic was released in December 1992 by the NRC 14

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subsequently backfilled with clean soil, and then seeded. Also included in Phase II are the East and West Sanitary Lagoons, the MOFF Plant Building exterior and yard area, the Emergency Building, the Warehouse B ilding (Building #4) and surrounding yard, and numerous drainage areas. Cimarron ha~ essentially completed all remediation in each of the Phase II Subareas and final status sur7eys are currently being completed.

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The FSSR for Subarea J was the first ~base II Subarea to be submitted to the NRC for license release; it was submitted in September 199?15

. Subarea J is West of Highway #74, and represents approximately 7 of the 122 acres in Phase II. The FSSR for Subarea

16 • J has been approved by the NRC , and a confirmatory survey was performed by NRC staff during their site visit of September! 21-23, 1998. By NRC letter dated December 4, 1998 17

, Cimarron was informed that NJtC staff will approve the release of Subarea J as part of the next license amendment incmtporating Cimarron's decommissioning plan.

Subarea His the second subarea includekl within Phase II where final status surveys have been completed. As discussed above, ¢e East and West Sanitary Lagoons are included within Subarea H, which includes approximately 38.5 acres. The FSSR for Subarea H was submitted to the NRC on November 16, 1998 18

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Also included in Phase II is the concretb previously surveyed for release and placed in a drainage way located within Subarea F. ! This concrete has been surveyed, with the results reported in the FSSR 19 for the Concret Rubble located in Subarea F. This FSSR was submitted to the NRC in March 1998. i Final Status Survey Reports for Subareas F, G, and I are pending.

Phase III Area

The area designated as Phase III on D awing No. 95MOST-RF3 contains only affected areas and represents approximately 30 acres of the remaining licensed 152 acres. The FSSP for release ofthis area from the si e license, was submitted to the NRC for approval in June 199720

. Phase III includes th former Uranium Processing buildings and yard area, Burial Areas #2 and #3, New Sa itary Lagoon, the NRC approved BTP Option #2 On-site Disposal Cell (Burial Area 4), and the Five Former Waste Water Ponds, consisting of Uranium Waste Ponds #I and #2, the Plutonium Waste Pond, the Uranium Emergency Pond, and the Plutonium mergency Pond. By letter dated September 11, 199821

, the NRC approved the Phase II Final Status Survey Plan.

The FSSR for Subarea L (Subsurface) as the first Phase III FSS to be submitted to the NRC. The Subarea L FSSR (Subsurfa e) was submitted to the NRC on May 29, 199622

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The NRC, by letter dated August 16, 199623, sent Cimarron comments concerning the

Subarea L FSSR. Cimarron responded to the NRC comments by letters dated September 9, 199624 and October 17, 199625

. dditionally, in order to resolve the NRC staff concerns pertaining to the potential resence of subsurface contamination, additional subsurface soil samples were collected or analysis within Subarea L. Cimarron provided the results for this additional subsurf: ce sampling event to the NRC by letter dated November 4, 199626

• Based upon th NRC staff review of these submittals and the additional subsurface sampling data, Cimarron's request to backfill Subarea L was approved by NRC letter dated Novem er 8, 199627

. Subarea L has been backfilled and contoured. Subsequently, the FSS for e Subarea L surface soils was completed and the FSSR was submitted to the NRC on Ju '27, 199828

. Subarea L represents approximately 5-acres. ·

The FSSR for Subarea O (Subsurfac~) was submitted to the NRC in March 199829.

Subsequent to the submittal of the fSSR for Subarea O (Subsurface), a FSS was perfom1ed on the surface soils with tlhe results presented in this Report. Subarea 0 represents approximately 6.4 acres. ~nother subarea recently addressed by Cimarron personnel was Subarea M, which is shdwn on Drawing No. 95MOST-RF3 and represents approximately 2.5 acres. The Subarea !M FSS has been completed and the results were presented in the December 1998 FSSRro. Final survey reports for Subareas K and N are pending.

3.0 DECOMMISSIONING ACTIVITIES

The purpose of this section is to discuss briefl¥ the status of the site decommissioning activities for Subarea O (Surface) and to present the ~adiological criteria and guideline values utilized throughout the remediation and final status suryey. A discussion of the characterization data and


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remediation performed on the subsurface soil~ can be found in the Subarea O (Subsurface) FSSR.

3.1 Identification of Contaminants

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3.2.2

Based upon the knowledge of pa t site operations, the results of numerous characterization efforts to date, and other independent characterization efforts by regulatory agencies and their respective subcontractors, the radiological contaminants on the Cimarron site have been determine to consist of U-234, U-235 and U-238, with an average enrichment above the naturall occurring level of approximately 2. 7 weight percent. Thorium, although not consid red a significant contaminant of concern for this subarea, has been included in the soil d sediment analyses and reported on the data summary sheets along with the total ur ium sample results.

Site Background Levels

Soils

Natural background levels for uranium in soil have been established through numerous measurements by Cimarron personnel utilizing the on-site soil counter and through independent regulatory review and labo atory analysis. Analytical results from Cimarron Corporation's environmental sampling rrogram are reported to the NRC annually in Environmental Monitoring Reports. hese reports include results for soil samples collected from numerous off-site locat, ons which are representative of background in surrounding soils. ·

Cimarron personnel collected and analy,ted 30 surface soil samples from the perimeter of the Cimarron site during the first quart¢r of 1995 to further validate background levels. Total uranium ranged from 2.3 pCi/g to j 6.6 pCi/g, with the average being 4.0 ± 2.6 (2cr) pCi/g. These values were obtained usirlg the Cimarron on-site soil counter. This on-site soil counter is calibrated to assume an i enrichment of 2.7 weight percent as this is the average uraniwn enrichment found tl{roughout the site. When a correction factor (0.67/1.5) is applied to these results to !convert the values from an assumed 2.7 weight percent enrichment to a natural enrichnient, the converted results ranged from 1. 0 pCi/g to 2.9 pCi/g with an average of 1.8 ± LO (2cr) pCi/g total uranium. This evaluation was submitted to the NRC staff in Cimarrori's June 1995 letter31

• Based upon this sampling event, the average value of 4 pCi/g t~tal uranium for background was adopted and applied when the on-site soil countet sample analytical results were compared to guideline values.

Exposure Rate

Background exposure rates have beeij. established by Cimarron by taking micro-R readings and pressurized ion chamber i (PIC) readings at off-site sample locations in addition to Cimarron site areas which ate unaffected by past operations. Exposure rates of approximately 7 to 10 µR/h have been observed in background areas by Cimarron

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personnel utilizing Ludlum micro-R urvey meters. In addition, site back§round exposure rates were measured by ORA (now ORISE) personnel utilizing a PIC 2

, and were determined to be 9 to 10 µR/h. Based on the PIC measurements performed by ORI SE, the site background was <let nnined to be [lpproximately 10 µR/h. Thus, depending upon instrumentation utilize , the background exposure rate at the Cimarron site ranges from 7 to 10 µR/h .

Cimarron personnel perfonned expos re rate measurements at background locations along the site boundary in 1995 using a Micro-R meter. Confirmatory measurements were obtained at the same locations in 997 using a Reuter-Stokes PIC. These data are tabulated below in Table 3 .1. The ave age background as measured using the micro-R meter was 7.6 µR/h, and is about 15 percent less than the average for the PIC measurements of 9.0 µR/h. Cimarron as used 7 µR/h as representative of the average background exposure rate for micro-R easurements. Recently, Cimarron began sending their micro-R-meters off-site for calibr tion by the manufacturer. With this change in calibration procedure, measurements at ackground locations were taken for comparison to the PIC. This data also is presente in Table 3.1 and illustrates an increase in the average measured background of appro imately 2 µR/h. Based upon this data, Cimarron will now use 9 µRib as representati e of background exposure rates for micro-R measurements taken with the off-site c librated meters. Table 3.1 demonstrates good agreement between the micro-R measurtjments and the PIC measurements .

1JABLE 3.1 Sample ID Grid Micro-R Reading PIC Reading Micro-R Reading

No. Location (JR/h) (µR/h) µR/h* UAF-BKG-1 819W-81N l 9 9.8 10 UAF-BKG-7 1600E-120N \7 7.6 7.5

UAF-BKG-ll 840W-700S i8 9.5 10 UAF-BKG-13 840W-288S l9 9.8 10.5

UAF-BKG-16 808W-282N !8 9.7 9.5 UAF-BKG-19 640W-700S 19 10.5 11 UAF-BKG-23 161 0E-300S !5 7.8 7.5 UAF-BKG-25 1610E-69N 6 7.6 8 UAF-BKG-27 1610E-469N : 7 7.8 8.5 UAF-BKG-28 1610E-634N :8 9.6 9.5

AVERAGE 7.6 ±'2.7 (2cr) 9.0 ± 2.3 (2cr) 9.2 ± 2.8 (2cr)

*Background survey results taken with instruments no~v calibrated off-site by manufacturer.

Characterization Data

Throughout the decommissioning process at the Cimarron site, a survey unit was characterized, remediated (if required), i and then a final status survey was performed. The description of the decommissioning! activities and final status survey data were then submitted to the NRC for review and ~proval (i.e., FSSR). After review of the final status survey report, the NRC either ~leased the unit or contracted with ORlSE to


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perform a confirmatory survey. Bas d upon the ORI SE confirmatory survey (if requested by the NRC), the NRC wou d either release the unit or require additional characterization and/or remediation.

The status of the Subarea O charact rization and decommissioning act1v1ties was discussed in the FSSR for Subarea O (S surface). This document was submitted to the NRC in March 1998, and includes a disc ssion of Uranium Waste Pond #1 (U-Pond #1), and Uranium Waste Pond #2 (U-Pond #2 . Subsequent to the submittal of the Subarea 0 (Subsurface) FSSR, the two U-Pond are s were graded, contoured, and seeded prior to performing the surface FSS.

U-Pond #1 was graded and additional so I from outside the affected area was transported and placed over the former pond area t promote drainage. Top soil was then replaced and the area was seeded.

U-Pond #2 was graded to remove appro imately six inches of topsoil. Four feet of soil from outside the affected area was exca ated, transported and then placed to produce a four foot cap over the former pond area. Additional soil was added to promote drainage; the topsoil was replaced; and then the are was seeded.

Environmental Monitoring Data

As previously discussed with the NRC'J staff, Cimarron Corporation has committed to address groundwater for the site in! a separate report. This report is titled, "Decommissioning Plan - Groundwater! Evaluation Report", and was submitted to the NRC in July 199833

. This Ground{ater Evaluation Report summarizes the site environmental data, presents trending an~lyses and a dose assessment, and commits to a plan for resolving the issues associated with elevated residual groundwater radionuclide concentrations. By letter dated Januaryf I 9, 199934

, the NRC approved a groundwater criteria of 180 pCi/1 for uranium. There ~e five monitoring wells located within Subarea O; the wells are #1311, #1312, #1313,1#1320 and #1321. None of the wells within Subarea O contain total uranium exceeding the proposed criteria as prescribed in NRC's January 1999 letter. ·

4.0 FINAL STATUS SURVEY PROCEDURE

The purpose of this section is to discuss the mettjodology utilized for the collection of the surface survey and soil sampling data presented as FSSi data in this report. The FSS data were used to demonstrate that the applicable radiological parq111eters (i.e., guideline values) were satisfied for release of Subarea 0, once Subarea O (Subsurf!ce) has been released, from License SNM-928. The guideline values utilized for comparison to the FSS data are described in this section.

In general, for Phase III areas, Cimarron Corpo~ation has committed to follow the methodology prescribed in NUREG/CR-584935 and as approv¢d in the Phase III FSSP for performing the FSS . This report includes all necessary data to suppott the FSS for the surface soils contained within Subarea O and the release for unrestricted use oflSubarea O (Surface) from License SNM-928.


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4.1 Survey Method

In general, survey and soil sampling d a were collected utilizing established methods that have been demonstrated through the release of other areas at the Cimarron site. The instrumentation available for use by sit personnel as well as the minimum detectable activity (MDA) and typical efficiency fo those instruments are listed in Table 4.1. The survey methods are discussed further bel

4.1.1 Grid Areas

4.1.2

4.1.3

Subarea O was subdivided into the 100 m x 100 m grid pattern shown on Drawing No 95MOST-RF3. The 100 m x 100 m rids were further subdivided for affected area surveys into IO m x IO m grids. For s stematic surveys the IO m grids were further subdivided into 5 m x 5 m grids. The 5 m x 5 m grids were utilized for locating survey and soil sampling points for this FSS. imarron employs a Global Positioning Survey (OPS) unit to check pre-established g 'd points and to locate sample collection and survey positions in the field. This GPS it is accurate to within less than± 1 m. The 0.0 grid point is located just south and sligl tly west of the main Uranium Building and has been tied into a permanent marker for fu re reference.

Survey Locations (Open Land Areas)

In general, the Subarea O open land a eas were 100% scanned utilizing a 3" x 1/2" shielded N al detector. The specific ins ents used were selected by the RSO/Health Physics Supervisor.

Each 5 m x 5 m grid was surveyed by te hnicians by traversing back and forth within the grid. Each traverse performed by the te hnician covered an area approximately 2 meters in width. The highest reading found within each grid area was recorded. Survey performance, documentation, and record retention was performed in accordance with the Cimarron Radiation Protection Progr ,· In the event that any of the survey readings exceeded the limits discussed in Sectiod 4.2.3, their location was flagged for additional sunreys and/or soil sampling. The s~rvey procedures followed were specified m Cimarron's Special Work Permit(s) and Work Plan(s) for this subarea.

Additionally, at the intersect of each 5 I!n x 5 m grid location, a systematic survey was completed at ground surface and at I rn ! above the surface for ambient radiation using a micro-R meter. Also, a gamma survey ~t the ground surface, using a shielded 3" x 1/2 11

Nal detector was performed and documeited.

Soil Sample Locations

The soil sampling frequency was specifijed in the Cimarron Special Work Permit(s) and Work Plan(s). Where practicable, syst~matic surface soil samples (0-6" depth) were collected at each 5 m x 5 m grid inte~ect location. All soil samples collected were analyzed for tota1 uraniwn and natural thvrium using the on-site soil counter. Any


• • • TABLE 4.1

RADIATION MONITORING INSTRUMENTS

INSTRUMENT NUMBER RADIATION SCALE TYPICAL TYPICAL MDA 95% TYPE AVAILABLE DETECTED RANGE 8KG EFFICIENCY CONFIDENCE LEVEL

Scintillation (Ludlum 2224) 2 Alpha 0-500,000 cpm < 10 cpm 20% 100 dpm/100 cm2

Scaler/Ratemeter Beta < 300 cpm 19% 500 dpm/1 0Ocm2

Micro-R Meter (Ludlum 12 & 19) 3 Gamma 0 - 5,000 µR/h 7 µR/h- 9 µR/h N/A 2 µR/h

1" x 1" Nal Detector

Ion Chamber (Victoreen) 1 Gamma 0.1 - 300 mR/h <.0 1 mR/h N/A < 0.2 mR/h

3" x 1/2" Nal Scintillation (43-82) 3 Gamma 0 - 500,000 cpm 3,000 cpm avg shielded N/A 250cpm I

Digital Scaler (Ludlum 2220/2221) 9,000 cpm avg unshielded 500 cpm

100 cm2 gas flow (43-68) 2 Alpha 0 - 500,000 cpm <10 cpm 20% 100 dpm/100 cm2

Digital Scaler (Ludlum 2220/2221)

60 cm2 gas flow { 43-4) 1 Alpha 0 - 500,000 cpm <10 cpm 25% 200 dpm/100 cm2 ·-·--.... , .. . - -·--···- ·•·.- ··- - -- --·- -- - -·- - ·-· ........ ... .. ·-· - ·-···-- - -- -- ···- · -- ··-- ·· - · .. -- .... _____ ... .. ··- ·- ·-- ··- ·

Digital Scaler

60 cm 2 Count Rate 7 Alpha 0 - 500,000 cpm <100 cpm 50% 350 dpm/100 cm2

Meter (PRM-6)

50 cm2 Personnel Room 2 Alpha 0 - 500,000 cpm <100 cpm 50% 500 dpm/100 cm2

Monitor (Ludlum 177)

Tennelec LB5100 Computer 1 Alpha 0 - 99,999,999 <0.3 cpm 38% 0.4 dpm

Based Auto Sample Counter Beta cpm 1.5 cpm 42% 1.5 dpm

Soil Counter - Computer Linked 1 Gamma --- 4 pCi/g Total U 4% 5 pCi/g U (5 min. count)

4" x 4" x16" Nal (Tl) Detector 1.5 pCi/g Th (Nat) 15% 0.6 pCi/g Th (Nat) (5 min. count)

3 pCi/g U (15 min. count)

0.3 pCi/g Th (Nat) (15 min. count)

100 cm2 gas flow (43-68) 2 Beta, Gamma 0 - 10,000 cpm <300 cpm 20 600 dpm/100 cm2

Digital Scaler {Ludlum 2220/2221)

*Reuter-Stokes PIC Model RSS-1 12 1 Gamma 0 - 100 mR/h 9-10µR/h NIA 0.5 µR/h (10 min. count)

"(Cushing Instrument available for Cimarron Use)

FSSR SlJBAREA O (Surface) 8

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4.2

i locations found exceeding the soil guid line values for affected areas as discussed in Section 4.2.2 were investigated further.

Radiological Guideline Values

The radiological guideline values disc ssed in this section were utilized for comparison with the FSS data in order to confirm at Subarea O can be released for unrestricted use from License SNM-928.

4.2.1 Equipment and Materials

The unconditional release limits for sur ace contamination on materials and equipment is in compliance with Facility License SNM 928, and is identical to the limits specified in Table 1 of the NRC's "Guidance for Decomm ssioning of Facilities and Equipment Prior to Release for Unrestricted Use"36

. Subar a O contains no buildings or equipment and therefore these types of surveys were n t applicable.

4.2.2 Volumetric Activity of Soil

For Subarea 0, the unrestricted release guideline value for residual concentrations of total uranium, which may remain in the s ii is specified as BTP37 Option #1 material. For enriched uranium, as specified in Tabl 2 of the BTP, the Option #1 limit is 30 pCi/g total uranium above background. In additio , the maximum enriched uranium soil concentration within any 10 m x 10 m grid area may qot exceed three times the BTP Option #1 limit (i.e., 90 pCi/g total uranium) above backtround. The average total uranium background concentration has been established at 4 pCi/g31

·

Systematic soil sampling was perform~d within each 10 m x 10 m grid area to determine the average residual total uranium conc~ntration. This systematic sampling equates to four

2 ' surface samples per 100 m area; wh~ch is the same sample frequency as one sample collected at the intersect of each 5 m xi 5 m grid intersect. Areas of elevated activity were determined based upon discrete sampling within the grid or were assumed to have a constant value (e.g., 25 m2 based upon :5 m x 5 m grid sampling frequency). The average value for the 10 m x 10 m grid then wa$ compared to the BTP Option # 1 guideline value of 30 pCi/g total uranium above background. Remediation or hot spot averaging was performed for each individual location which contained average total uranium concentrations in excess of 30 pCi/g a~ve background as described in NUREG/CR-5849. In addition to the above criteria, areas of elevated activity not remediated between one and three times the guideline value were tested to assure that the average concentration was less than (100/A)112 times the guideline valu¢, where "A" is the area of elevated activity in m2

•

The Option # 1 unconditional release guideline value for residual concentrations of natural thorium, which may remain in soil p¢r Table 2 of the BTP, is up to 10 pCi/g above background. Additional constraints itj.clude the "3 times the limit" and the (100/ A) 112

criteria as defined above. The avdrage background for natural thorium has been I

determined to be 1.5 pCi/g for soil analyzed with the on-site counter.


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4.2.3 Gamma Surface Survey (Open Land !reas) !

Cimarron personnel utilize a shielded o unshielded 311 x 0.5'' sodium iodide (Nal) detector as a final screening device for qualitati :e identification of residual contamination in soil. Prior to the commencement of site-wid remediation, Cimarron evaluated several portable survey instruments for performing scan surveys including the 2" x 2" Nal detector. Based upon recommendations from Ludlum I struments, Inc., Cimarron decided to use the 3" x 0.5'' Nal detector for general area sea . This system is one of the more sensitive field detection instruments available to Cima

Since the inception of Cimarron' s site ecornmissioning, twice background has been used as the guideline for scan surveys wh n utilizing the 3" x 0.5'' NaI detector. Survey readings above this guideline indicate an area requiring additional investigation. This guideline has been a standard in the nu lear industry for many years. With the submittal and approval by the NRC of numero s plans and reports, twice background also has become the accepted standard for the Cmarron Facility as a qualitative screening measure. This qualitative guideline was included in the Phase I Final Status Survey Plan7

, Phase I Final Status Survey Report 10

, and the P ase II Final Status Survey Plan 12 just to name a few of the documents where this guideline as addressed and approved by NRC staff for this site.

Twice background (as noted in Section 6.4.2 of NUREG/CR.5849) is at the lower end of the range discemable for scanning instr mentation. During the scan survey the technician, upon noting a "discemable" difference in the audio output from the mete.r, will stop and attempt to locate the elevated area. It is difficult to discriminate low levels of residual uranium contamination when other natu. ally occurring isotopes are present \Vhich affect the gross count rate of the scan instrument. : The guideline value of twice background provides a sufficient margin for technicians w~en conducting a scan to conclude that residual contamination may be present when a ~ignal exceeds the twice background level (i.e., a discemable audible increase above bac~ground). This discemable audible response alerts the surveyor to momentarily stop moving the probe (i.e., 2 to 3 seconds) and to further investigate the area. The survey instruments utilized at Cimarron indicate changes in radioactivity levels via either a higher olr lower pitch. These changes in pitch are easier to detect rather than simply noting an audi~le change in the count rate.

The shielded detector was utilized to perform the initial 100% surface scan survey for Subarea O to identify regions or areas; of slightly elevated activity. Also, the shielded detector was utilized for systematic su~eys at each grid intersect to identify elevated areas. As stated above, this instrument is only utilized for qualitative measurements. Quantitative measurements of residual contaminatio~ levels in soil are performed with the Cimarron soil counter. Additionally, daily "backgrou~d" surveys are taken prior to performing surveys within a survey unit. These average dapy "'backgrounds" are listed on the data tables and drawings and were used for comparison to the guideline (i.e., twice background) .


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4.2.4 Exposure Rate Survey (Open Land Alj'eas) i

The average exposure rate for S ubarea · 0 areas to be released for unrestricted use is 10 µR/h above background, at 1 meter ab ve the surface. Exposure rates may be averaged over a 100 m2 grid area as described in UREG/CR-5849. The maximum exposure rate at any discrete location within a I 00 s uare meter area cannot exceed 20 µR/h above background. Any area with average exp sure rates greater than IO µR/h above background and any discrete location within a 100 s uare meter area with an exposure rate greater than 20 µR/h above background was deline ted and remediated as required. Cimarron has in the past measured 7 µR/h as the average background exposure rate. However, as discussed in Section 3 .2.2, since sending their micro-R meters off-site for calibration by the manufacturer, Cimarron has demonstr ted that 9 µR/h is representative of the average background exposure rate for micro-R easurements. The tables and drawings included in the Appendices provide the average bac~ground for the micro-R meter used in developing the tabulated survey data. A backgroun of 7 µR/h indicates that the instrument utilized for performing the survey was calibrated on-site; and likewise a background of 9 µR/h indicates calibration off•site.

4.3 Equipment Selection

Special Work Permits (SWP) and Wor, Plans (WP) were written and approved prior to commencement of the field work required for this FSS. The SWP and/or WP for Subarea 0 specified the type of instrumentation tb be utilized in performing the FSS .

4.3.1 Equipment and Instrumentation

The instrumentation utilized to generat~ the FSS data discussed herein was calibrated and maintained by site personnel in acc*!rdance with the Cimarron Radiation Protection Program procedures. These procedures tilize the guidance contained in ANSI N323-l 978, "Radiation Protection Instrumentation est and Calibration38

". Specific requirements, as specified by the Cimarron procedures for instrumentation, include traceability of calibrations to NIST standards, field jchecks for operability, background radioactivity checks, operation of instruments withfn established environmental bounds, training of individuals, scheduled performance che¢ks, calibration with isotopes of energies similar to those to be measured, quality assurance tests, data review, and recordkeeping. An explanation of how Cimarron' s Radiation Protection Program procedures are implemented with respect to instrumentation was discussed in Cimarron's May 13, 199839 responses to the NRC' s comments on Subarea J.

With the exception of the exposure rate instrumentation (ion chamber, PIC and micro-R meter), Cimarron health physics staff performs in-house calibration on each of the instruments listed in Table 4.1 . Portab1e survey instruments are calibrated on a quarterly basis. The exposure rate instruments are sent off-site for vendor calibration on a semiannual basis. Where applicable, activities of sources utilized for on-site calibration are corrected for decay. In addition to the periodic calibration requirements, source response checks are performed on a daily Qasis for all instruments being utilized during characterization, remediation and final status survey work.


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All calibration and source check record~ are completed, reviewed, signed-off and retained in accordance with the Cimarron Qualit Assurance Program. The instrumentation utilized by site personnel is discussed below:

4.3.1.1 Unshielded 3" x 0.5'' NaI Gamma Detec or

The 3" x 0.5' 1 detector is a sodium iodid (Nal) crystal gamma detector which is unshielded around all sides. The NaI detector is utilized with a portable scaler/ratemeter that has single channel analyzer capability. ericium-241, Uranium-235, and Natural Thorium sources are utilized to set the instrum ntation window and threshold to detect gamma energies in the range of 50 to 250 keV. This energy range corresponds to the energies of interest when surveying for uranium an natural thorium contamination. The instrument is normally operated in the window 11out 11 10de, meaning that the instrument response is for the entire range of detectable energies.

4.3 .1.2 Shielded 3" x 0.5'' Nal Gamma Detector

The 3" x 0.5'' detector is a NaI crystal amma detector which is shielded with lead around the top socket and sides to improve th directional sensing capabilities of the equipment. Similar to the unshielded detector, t e shielded detector is utilized with a portable scaler/rate meter that has single chann 1 analyzer capacity. This instrument is normally utilized in areas where background may e elevated.

4.3.1.3 Micro-R Meters

The micro-R meter is a r' x l" Nal crys~al gamma detector which measures exposure rates between O and 5,000 µRlh. Background readings are obtained daily at a defined location prior to placing each instrument into service. This instrument is utilized, in general, for determination of exposure rates at both $ystematic and random locations and at locations of elevated radiation identified by area scads.

Confirmatory measurements are obtainqd routinely to provide information concerning any measurement bias. These comparisons: or confim1atory measurements are made using a pressurized ion chamber. Confirmatory :measurements for Subarea Oare included in Table 4.2 and show results indicative of site background for Micro-R meters calibrated off-site .


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T~LE4.2 CONFIRMATORt MEASUREMENTS

(Readings 1 M, ter Above Grade) Reading Mi ~ro-R PIC Reading Location Readi1 g (µR/h) (µR/h)

460N-290E 10.5 9.9 440N-300E J.5 10.6 440N-280E u 10.3 400N-280E J.5 10.2 400N-300E 10.0 10. l 522N-567E 'J.5 9.5 517N-545E 10.5 10.0 597N-550E 10.0 9.8 463N-543E 10.0 9.6 454N-514E 11.0 10. l

Average ~.9 10.0

4.3.1.4 Soil Count er (Gamma Spectroscopy)

on Soil Counter System consists of a 4" X 4" X l 6 11 S The Cimarr odium iodide crystal

I

housed in a shielded chamber whichl is computer linked to a multi-channel analyzer (MCA). Cimarron's counting systeni is programmed to determine the total uranium present in the soil sample by calculating the U-234 activity based upon the U-235 activity measured in the soil sample . The U-234 and U-235 activities are summed with the

I

detected U-238 activity to obtain the to~al U activity. The counter also adjusts for system background. Calibration of this counti*g system is performed annually and is traceable to NIST standards through contractor ~aboratory evaluations of the on-site standards. Standards used for calibration and quality assurance checks for the soil counter have been analyzed by outside laboratories and are NIST traceable through these analyses. Comparisons have been made between rthe standards as counted using the soil counter and two off-site laboratories. The assigned values for the standards are the average of the results obtained from the off-site labor~tories, when the standards were analyzed by more than one laboratory. The standards range in concentration from 4.5 pCi/g total uranium to 292 pCi/g total uranium.

Established quality assurance measures for the soil counter include Cesium-13 7 centroid checks, Chi-square tests, background determinations, and the counting of soil standards. All of these quality assurance controls are recorded on control charts and are trended on a continuing basis. Additional information pertaining to soil standards and typical MDA calculations for the counting system were included in Cimarron' s responses to the NRC' s comments on Subarea J39

. •

Cimarron personnel determine uraniwin and thorium activities in soil based upon the evaluation of net counts from the soil counter. Activities are calculated through the use of efficiency and correction factors obtain¢d using appropriate standards. Soil concentrations are calculated by dividing the net activify by the soil mass. Soil masses are determined on


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a laboratory scale which is checked on ' daily basis (when in use) utilizing NIST traceable standards. Corrections for soil moisture content are also made as necessary.

ORISE has been used by the NRC for erification of a majority of the decommissioning work completed to date at the Cimarro site. ORISE has conducted an evaluation of the Cimarron Soil Counting system's ability to measure accurately total uranium concentrations in soil samples. This was done by co aring ORISE sample analysis results obtained by alpha pulse height analysis and gamma pectroscopy with the results obtained from the use of the Cimarron Soil Counter. ORI SE d Cimarron analysis results compared favorably at levels above background as demonstrat d by the confirmatory analysis performed for the On-Site Disposal Cell, Pit #3 (NRC co er letter dated July 31, 1997)40

. NRC inspection Report #70-925/97-02, which accompa ied this letter, states that "no significant bias or statistical errors between the license's s ii results and the NRC's results were identified". Additionally, the confirmatory analysis erformed on selected soil samples collected during ORISE's site visit to investigate the outh U-Yard41

, and DAP-3 stockpile42 verified previously that Cimarron's ter results are statistically identical to ORISE's results.

A more recent inspection by the NRC lso confirmed Cimarron' s Soil Counting system's ability to accurately measure total urani concentrations in soil samples. On September 24, 1998, the NRC collected twelve (12 soils and sediment samples form Subarea J. The samples were first counted on the On-S · e Counter by Cimarron and then shipped by NRC to their Region III laboratory for anal~ses. The November 3, 1998 Inspection Report43

(i.e., Report No. 70-925/98-02) stated the following:

'"Overall, the NRC measurem<bnts confirmed that Subarea J soil and sediment had less than 30 pCi/gi uranium. No significant bias or statistical errors between the licensee's Soil and sediment sample results and the NRC's results were identifie~. Licensee measurement methods and counting times were found to be ~cceptable."

4.4 Procedures/Plans

As discussed in Section 4.3, SWPs ,and WPs were written and approved prior to commencement of fieldwork required for this final status survey. These SWPs and WPs are an integral part of this site's radiation protection and quality assurance program. Project organization and responsibilities, which are a part of the site's quality assurance program, are discussed in this section.

4.4.1 Organization

The Subarea O FSS was performed by a !survey team consisting of qualified personnel from the Cimanon Facility . The FSS team: operated under the general direction of a Project Manager who reports directly to the Site :Manager at the Cimanon Facility.

The selection of field measurement equipment and sample collection techniques was under the direction of the RSO/Health Phys~cs Supervisor. Actual field measurements and


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4.4.2

sample collection were under the direc1ion of the Project Manager. The Project Manager was responsible for developing the SWP and WP for Subarea O with input from the RSO/Health Physics Supervisor. The SWP and WP were reviewed and approved by the Cimarron Site Manager.

Training

Cimarron Corporation provides contin ing training to Cimarron personnel and any other personnel (i.e., contractors, visitors~ etc) who are allowed access to the site. All members of the FSS team attended an in-hous training session on the SWP and WP prior to commencement of work. All FSS pr cedures and quality assurance requirements were reviewed during this training session.

4.4.3 Radiation Protection Program

Cimarron Corporation maintains a radi tion protection program that meets and/or exceeds all of the applicable regulatory requir ments associated with activities conducted under Special Nuclear Materials License SN -928. The Cimarron Radiation Protection Program currently in place for all decommission ng activities is administered through the use of the following documents:

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Cimarron Radiation Prote , tion Procedures Cimarron Site Health and ~afety Plan Cimarron Quality Assuranite Plan and Procedures Cimarron Emergency Plari

It is the policy of Cimarron Corporat~on to perform all work in strict compliance with applicable regulatory and internal : requirements. The goal of the Cimarron decommissioning effort is to conduct ~11 operations at a level of excellence that exceeds regulatory requirements. Cimarron staff will continue to exercise appropriate radiation protection precautions throughout the remaining decommissioning work and final survey process.

Independent Kerr-McGee Corporate audits for regulatory and internal requirements are conducted on a periodic basis and include the review of the Cimarron Radiation Protection Program and associated programs. , Assessments of program effectiveness are also performed periodically by the Cimarron RSO/Health Physics Supervisor. Additionally, the Cimarron Radiation Protection Program is inspected for compliance with applicable rules and regulations by NRC Region IV and NRC Headquarters staff.

4.4.4 Cimarron Quality Assurance Prograijn (QAP)

The Cimarron Corporation QAP is an integral part of the Cimarron Radiation Protection Program. A principal component of the QAP is the confirmation of the quality of project work performed during decommissio~ng by assuring that all tasks are performed in a quality manner by qualified personnel.! The Program ensures that samples are collected, controlled, and analyzed in accordatce with applicable quality controls to provide


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confidence in the resulting data accura: y and validity. Cimarron's QA/QC program is structured to generate data that can be verified through independent review should they desire to perform an audit of the data.

The Cimarron QAP is implemented an maintained in accordance with written policies, procedures, and instructions. This Pr gram is administered under the direction of the Quality Assurance Manager. Periodic urveillance and reviews are conducted to ensure that all aspects of the Program are addr ssed. The Cimarron QAP satisfies the applicable requirements of ASME NQA-1 44

.

Written procedures designated as SWPs d WPs, are prepared, reviewed and approved for activities involved in carrying out the ecommissioning process. The Subarea O Survey SWP and WP were written in accord ce with the Cimarron QAP. These documents designate the type of surveys to be perfo ed, samples to be collected, frequency of sample collection, and the type of field instrume, tation required for the tasks required.

Selection, calibration and use of radiat~on detection instrumentation used for final status survey release at Cimarron are directed ~y the Radiation Safety Officer (RSO). The RSO is responsible for the calibration performed by Cimarron Health Physics staff or by contract services. The RSO maintains a file for! each technician on staff as to their qualifications and training. ·

The facility performs its own radiol~gical soil analysis in accordance with written procedures and QA/QC protocols. Field data are gathered and maintained in logs for all samples in accordance with the Cimarron QAP. Necessary data are transferred to the onsite laboratory sample log when the sample is brought to the on-site laboratory for analysis. The sample logs provide a record of sample collection and transport (chain of custody) and are incorporated into the facility quality assurance records.

In addition, off-site independent radiological analysis of split samples (samples are first counted on site and then sentto an off-site independent laboratory) is an integral part of the Cimarron QAP. Samples sent to an : off-site independent laboratory for analysis are accompanied by a chain of custody fortn in accordance with the Cimarron QAP. These forms provide documentation for all aspects of sample control and are maintained by the Quality Assurance Manager as permanent records.

Sample and survey data are reviewed by the Health Physics Department for accuracy and consistency and to determine if further characterization or remediation is required or if the data is acceptable. Additionally, the data are compared to the guideline values on a regular basis. The data review process verifies that approved QA/QC procedures have been followed. When identified, correctiohs to recognized deficiencies are performed in accordance with the QAP .


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5.0 SURVEY FINDINGS

As discussed in Section 1.0, FSS data were gen~rated for Subarea O (Surface) to justify the release of this subarea from License SNM-928. The survey findings, including the statistical methodology employed to evaluate the data for Subarea 0, a discussed in this section.

5.1 Data Evaluation

5.2

As discussed in NUREG/CR-5849, the uideline values for soil activity concentrations and exposure rates are average values (abov background) established for areas of survey units . In order to compare the analytical and survey data developed for the final status survey with guideline values; data at each ind victual survey grid location were compared to the appropriate guideline values. The guid line value for leaving soil in place for unrestricted release is BTP Option #1 material (i.e. up to and including 30 pCi/g total uranium above background).

As discussed in Section 4.2.2., for an affected area, if an individual soil activity measurement (representing 25m2

) ex eeded the applicable guideline value, then the average was determined for the survey nit ( I 00 m2). Areas of residual activity exceeding the guideline value (known as elevated treas) were accegtable provided they did not exceed the guideline value by greater than a fa~tor of (100/A) 1

, where A was the area of residual activity in m2

, and provided the activity! level at any location did not exceed three times the guideline value. Since all individual sd.il activity measurements were below the applicable guideline value, I 00 m2 averaging was not required .

Comparison with Guideline Values

The FSS data for Subarea O (Surface) were compared to the guideline value criteria and are discussed separately in this section. This section evaluates the data collected from both the I 00% scan and the systematic surveys performed at the grid intersects for Subarea O which is shown on Drawing No. 95MOST-RF3 (Appendix 1).

This subarea includes former U-Ponds #1 and #2. As discussed in Section 3.3, the FSSR for Subarea O (Subsurface)29 discussed survey data and statistical evaluations justifying release of the subsurface soils from the site license. The data discussed in this section represents surface data only.

After final grading and the seeding of the two former U-Pond areas, a 100% scan was performed on the entire Subarea O soil surfaces with the shielded Nal detector for any location exceeding twice backgrouncl. For Subarea 0, daily average NaI detector background was determined for comparing either scan or systematic survey results to the guideline value. The N al detector av~rage background value is listed for the systematic surveys on the data tables and on the drawings.

The soil sampling events for the FSS are addressed separately as either fonner U-Pond #1 or U-Pond #2 data sets.


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5.2.1 U-Pond #1 Data Evaluation

5.2.2

For the U-Pond #1 surface sampling ev 'nt, soil samples were collected at each 5 m x 5 m grid location. The soil sample analytica results are listed in tables included in Appendix 2. The soil sample locations and analytic results for total uranium are shown on Drawing No. 98 POP I SS-O. This drawing also i included in Appendix 2.

A total of 272 FSS soil samples were ollected for analysis; with soil sample analytical results ranging from 2.8 to 13.2 pCi/ total uranium. The mean value for all surface samples was 6.9 pCi/g total uranium, ·th a standard deviation of 1.5 pCi/g. The 95% confidence level value was 7.0 pCi/g, w ich is below the guideline value for total uranium. Also, the soil sample analytical results for this subarea showed natural thorium ranging from 0.3 pCi/g to 1.6 pCi/g. The m an value was 1. 1 pCi/g natural thorium, with a standard deviation of 0.2 pCi/g thoriu . The statistical analyses for the natural thorium soil sample data also are included in Ap endix 2.

Systematic surveys were performed duri g the FSS at the 272 grid intersects with 3" x 0.5'' shielded Na! detectors and the µR me r. The exposure rates at the surface and at one meter above the surface, as measured u ing a µR/h meter, both ranged from 8 to 13 µR/h, with the mean being 10 µR/h. All meas ed exposure rates were below the guideline value of 19 µR/h (i.e., 10 µR/h above the aver~ge background of 9 µR/h). The exposure rates are presented on Drawing Nos. 98 POPl[UR-0 and 98 POPI UR-I. These drawings are included in Appendix 2. The ground leteI shielded Nal detector survey results for the grid intersect sample locations ranged from 3,820 to 5,830 CPM. All survey results were less than twice background which was recorded at 4,150 CPM. The survey results are presented on Drawing No. 98 POP13D-Q included in Appendix 2.

U-Pond #2 Data Evaluation

During the U-Pond #2 surface sampling; soil samples were collected at each 5 m x 5 m grid location. The soil sample analytical results are listed in tables included in Appendix 3. The soil sample locations and analytical results for total uranium is shown on Drawing No. 98 POP2SS-0. This drawing also is included in Appendix 3.

A total of 783 FSS soil samples were 1collected for analysis; with soil sample analytical results ranging from 1.0 to 10.7 pCi/g total uranium. The mean value for all surface samples was 5.3 pCi/g total uranium, with a standard deviation of 1.3 pCi/g. The 95% confidence level value was 5.4 pCi/g, which is below the guideline value for total uranium. Also, the soil sample analytical results for this subarea showed natural thorium ranging from 0.6 pCi/g to 1. 7 pCi/g. The mean value was 1.2 pCi/g natural thorium, with a standard deviation of 0.2 pCi/g thorium. The statistical analyses for the natural thorium soil sample data also are included in Appendix 3.

Systematic surveys were performed during the FSS at the 783 grid intersects with 3" x 0.5'' shielded N al detectors and the µR meter. The exposure rates at the surface and at one meter above the surface, as measured using a µR/h meter, ranged from 9 to 13 µR/h, with


•

•

. I·-

the mean being 11 ~tR/h and from 8 µR/h to 13 µR/h , with a mean of 11 µR/h , respectively. All measured exposure rates were bel ; w the guideline value of 19 µR/h (i.e., IO µR/h above the average background of 9 µ ). The exposure rates are presented on Drawing Nos. 98 POP2UR-0 and 98 POP2UR-1. These drawing~ are included in Appendix 3. The ground level shielded Nal detector su ey results for the grid intersect sample locations ranged from 2,460 to 5,370 CPM. A 1 survey results were less than twice background which was recorded at 3,000 CPM. T e survey results are presented on Drawing No. 98 POP23D-O included in Appendix 3.

5.3 QA/QC Procedures

Cimarron Corporation's Quality Assura ce Plans and Procedures are an integral part of the overall site decommissioning program d include off-site independent isotopic analysis of split samples. For the soil activity ran es that apply to this final status survey and for soil samples collected during the time fram that the survey data was being generated, a total of sixteen soil samples were split and sen off-site for analysis. The soil samples were first analyzed using the on-site counter prio to being packaged and sent off site for analysis at an independent laboratory. The in ependent laboratory for this project was Core Laboratories and they participate in an tional inter-comparison quality assurance program. The results for both off-site and on-site analysis are listed in Table 5.1. These sample results show good agreement. '


• TA;BLE 5.1 Off-Site tab Results

i On-Site Results Core Lab NRC

Cimarron Counter Sample ID No.

(pCi/g U) (pCi/g U) (pCi/g U) N3-3•136 I 13.69 ± 4.28 15.6 ± 2.47 N3-3-141 15.55 ± 3.68 24.1 ± 2.7 N3-3-149 19.44 ± 4.28 20.7 ± 2.58 N3-3-l 78 48.09 ± 7.14 49.7 ± 2.85

HC-1 2.0± 2.3 6.1 ± 2.0 HC-6 3.1 ± 2.6 3.9 ± 1.9 HC-9 5.1 ± 3.8 6.2± 1.4

MISC-41 1.6 ± 1.7 6.7 ± 1.7 MISC-60 1.4 ± 1.8 5.0 ± 1.6 MISC-88 2.9 ± 2.2 7.6 ± 1.6

HU-70 15.1±5.8 15.2 ± 2.1 HU-73 15.1 ± 6.1 15.9±2.0 KE-210 30.6 ± 9.3 33 .3 ± 2.0 KE-213 66.5 ± 14.5 62.4 ± 2.3 KE-219 19.3 ± 6.3 21.6 ± 2.2 GD-647 7.2 ± 3.6 6.5 ± 1.6

• GD-654 11.5 ± 4.8 12.9 ± 1.6 GA-245 3.0 ± 2.4 I 8.1 ± 1.6 GA-219 24.3 ± 7.0 25.0 ± 1.8 IA-884 27.0±7.1 32.1 ± 2.2 IA-899 32.5 ± 7.8 42.2 ±2.0 IA-900 26.6 ± 7.3 25.8 ± 1.9 IA-906 51.4± 10.8 56.5 ± 2.2

IA-1217 76.5 ± 15.3 ' 79.5 ±2.5 KA-30 55.2 ± 12.3 48.1 ± 2.2 JA-328 3.39 ± 1.79 6.3 ± 2.14 JA-329 46.14 ± 3.23 38.8 ± 2.23 JA-330 30.15 ± 2.96 24.8 ± 2.12 JA-331 15.19 ± 2.77 12.7 ± 1.87 JA-332 3.33±1.17 6.3 ± 1.8 JA-333 6.77 ± 1.46 9.0 ± 1.75 JA-334 18.70 ± 2.60 16.5 ± 2.35 JA-335 21.01 ± 2.88 21.4 ± 2.53 JA-336 16.25 ± 2.61 19.9 ± 2.64 JA-337 1.89 ± 1.16 4.8 ± 1.90 JA-338 2.51 ± 1.32 8.1 ±2.04 JA-339 3.53 ± 2.0 6.0 ± 2.24

• FSSR SUBAREA O (Surface) 20

------------···-- · -··· - .. . ...

•

•

•

6.0 SUMMARY

A FSS was performed in accordance with the N C approved Phase III FSSP and the SWP and WP approved by Cimarron Management for Subare O (Surface). This report in conjunction with the March 1998 FSSR for Subarea O (Subsurface) 9 presents a comparison of the FSS results to the guideline values for affected areas at the Cim on site. The comparisons presented herein and in the March 1998 Report demonstrate that all gui eline values for unrestricted release have been met and thus both the Subarea O surface and subsur ace areas can now be released from License SNM-928. Therefore, this report is being submitted o the NRC in conjunction with a request to release Subarea O from License SNM-928 for unrestric ed use .


• 7.0 APPENDICES

• Appendix 1 • Appendix 2

• Appendix 3

•

• FSSR SUBAREA O (Surface)

I

Drawing 95 MOST1-RF3 Data Tabulation sheets, Statistical Analyses and Drawings for U-Pond #1 l Data Tabulation Speets, Statistical Analyses and Drawings for UPond #2

22

i l i ~ • ~ '"= ~

-· t . ;---· -. _/ __ -==->- -· .: '

;~ , . . ;_ . ;. -\ ~ - -

) . '

- • ~ -~ • · . ·- - ' .. - .. : i

UNAITTCTED AREA (PHASE I) (R.,.._ hm Uc-. 1tM)

UHAfF'ECTtD AREA (PHASE II) _.,, ...... .,

II - .a • ... □ - 12 It • ..

II DI ll " • .. .. .a • .. • et ll II. • ... -....a. It • • .... ,.Mt. It • • ---·· .a • • •

_j .. • " " • .. .a • • It • • .t: • • .t: • • -

□ AFFECTED AREA (PHASE II)

AFFECTED AREA (PHASE HI)

SC.Ul 11 IUUU "'

CD/ARRON CORPORATION

CIMARRON FACILITY flNAL STATUS SURVEY PLAN

PHASES I, II AND Ill

95MOST-RF3 13

01/27/99

CIMARRON CORPORATION CIMARRON FACILITY

• SUB AREA "O" SURFACE WASTE POND# 1 RESULTS IN BACKGROUND MDA

INSTRUMENTS: S/N

LUDLUM MICRO R METER MIN 19 138420 uR/hr 9 2

LUDLUM 2220, LEAD SHIELDED 3" X 1/2" Na! DETECTOR 48395 CPM 4150 NIA pCi/g Total U 4.0 5

CIMMARON SOIL COUNTER 4" X 4" X 16" Nat DETECTOR pCi/g Th (Nat) 1.5 1

REVIEWED BY: 1..Jto.' ~- DATE: )_ -1 -y y r BACKGROUND NOT SUBTRACTED

3" MICRO MICRO pCi/g pCi/g LN GRID LOCATION DETECT R' R• O" - 6'

# C.P.M. SURF 1 METER Total-U Th (Nat)

1 255 E - 440 N 5190 10 10 6.4 1.2

2 255 E - 445 N 5040 11 11 6.5 1.4

3 255 E - 450 N 4660 11 10 5.2 1.6

4 255 E - 455 N 4490 9 10 6.7 1.6

5 255 E - 460 N 4790 9 10 4.9 1.2

6 260 E - 420 N 5310 12 12 8.9 1.2

7 260 E - 425 N 5220 11 12 9.6 1.4

• 8 260 E - 430 N 4370 10 12 6.6 1.3

9 260 E - 435 N 4780 11 11 7.0 1.1

10 260 E - 440 N 4300 10 11 8.3 1.4

11 260 E - 445 N 4530 11 11 6.8 1.3

12 260 E - 450 N 5140 11 11 9.2 1.2

13 260 E - 455 N 4760 11 12 9.6 1.3

14 260 E - 460 N 4920 12 11 8.6 1.2

15 265 E - 405 N 5100 11 11 6.6 1.2

16 265 E - 410 N 4930 12 12 6.6 1.2

17 265 E - 415 N 4970 11 11 10.1 1.2

18 265 E - 420 N 4840 11 11 8.2 1.4

19 265 E - 425 N 4670 10 11 5.2 1.3

20 265 E - 430 N 4930 11 10 8.4 1.5

21 265 E - 435 N 4550 11 10 4.1 1.5 22 265 E - 440 N 4440 10 10 6.3 1.4

23 265 E - 445 N 5190 11 11 7.1 1.4

24 265 E - 450 N 4690 11 10 6.7 1.3

25 265 E - 455 N 4880 11 11 9.7 1.2

26 265 E - 460 N 4310 10 10 6.8 1.3

• 27 265 E - 465 N 4780 11 11 7.3 1.2

28 270 E - 385 N 5510 12 13 5.9 1.1

29 270 E - 390 N 4150 11 10 7.6 1.0

30 270 E . 395 N 5020 12 11 5.1 1.1

FILE:OFFICE\QPW\AREAO\OWP1 SUU

01/27/99



INSTRUMENTS: S/N

LUDLUM MICRO R METER MIN 19 138420 pR/hr 9 2

LUDLUM 2220, LEAD SHIELDED 3" X 1/2" Nal DETECTOR 48395 CPM 4150 N/A pCi/g Total U 4.0 5

ClMMARON SOIL COUNTER 4" X 4" X 16" Nal DETECTOR pCi/g Th (Nat) 1.5 1

REVIEWED BY: V (l, ~--~ t,.- l , ,> r _.- DATE: 2..-1-77 BACKGROUND NOT SUBTRACTED

3" MICRO MICRO pCi/g pCi/g LN GRID LOCATION DETECT RI R' O" - 61


31 270 E - 400 N 5050 12 12 4.4 1.3

32 270 E - 405 N 5160 11 11 8.9 1.2

33 270 E - 410 N 4800 9 11 6.0 1.4

34 270 E - 415 N 4550 10 11 5.4 1.5 35 270 E - 420 N 4970 11 10 5.0 1.4 36 270 E - 425 N 4970 11 12 6.0 1.2 37 270 E - 430 N 4630 9 10 5.7 1.4

38 270 E - 435 N 49301 11 12 6.0 1.3 • 39 270 E - 440 N 4420i 11 10 5.9 1.2

40 270 E - 445 N 50301 12 10 5.9 1.3 41 270 E - 450 N 4340: 12 12 6.5 1.0

42 270 E - 455 N 4740 12 11 4.0 1.4 43 270 E - 460 N 4820 11 10 4.3 1.3

44 270 E - 465 N 4610, 10 11 6.3 1.2

45 275 E - 365 N 4940: 12 10 6.1 1.3

46 275 E - 370 N 5460 10 11 7.0 1.4 47 275 E - 375 N 5650 12 12 7.8 1.3

48 275 E - 380 N 5490 11 12 7.3 1.1

49 275 E - 385 N 5160 12 11 8.2 1.3

50 275 E - 390 N 5170 13 12 6.3 1.3

51 275 E - 395 N 4590 11 13 6.4 1.2

52 275 E - 400 N 4620 10 10 8.3 1.1

53 275 E - 405 N 4740 12 11 7.9 1.3

54 275 E - 410 N 4700 11 11 6.7 1.3

55 275 E - 415 N 4580 11 9 6.0 1.1

56 275 E - 420 N 4640 10 10 4.9 1.1

• 57 275 E - 425 N 4490 11 9 5.2 1.3

58 275 E - 430 N 4210 10 11 6.0 0.8

59 275 E - 435 N 4970 10 10 4.4 1.2

60 275 E - 440 N 5100' 9 8 5.7 1.1

FILE:OFF1CE\QPW\AREAO\OWP1 SUU 2

--------------. ·• - •- .. - ••• -· • - --•- • • - • •• " I

01/27/99



INSTRUMENTS: SIN

LUDLUM MICRO R METER MIN 19 138420 uR/hr 9 2

LUDLUM 2220, LEAD SHIELDED 3" X 1/2" Nal DETECTOR 48395 CPM 4150 N/A DCi/a Total U 4.0 5

CIMMARON SOIL COUNTER 4" X 4" X 16" Nal DETECTOR pCi/a Th (Nat) 1.5 1

REVIEWED BY: w. °'-· /4 - - . - DATE: 2--!-?7 BACKGROUND NOT SUBTltACTED

3" MICRO MICRO pCi/g pCi/g LN GRID LOCATION DETECT R' R' O" - 8'

# C.P.M~ SURF 1 METER Total-U Th (Nat)

61 275 E - 445 N 4600 11 10 7.9 1.0

62 275 E - 450 N 4650 11 11 5.1 1.2 63 275 E - 455 N 4550 : 12 11 7.6 0.9

64 275 E - 460 N 4840 1 10 11 6.7 0.9

65 275 E - 465 N 4730 ; 11 10 7.9 1.3 66 275 E - 470 N 4280 11 10 6.9 1.4

67 280 E - 355 N 4820 ' 11 11 5.4 1.0

• 68 280 E - 360 N 5220 12 11 7.0 0.9 69 280 E - 365 N 5680 11 12 8.3 1.1 70 280 E - 370 N 5830 11 12 4.7 1.2 71 280 E - 375 N 5490 11 10 9.3 0.9 72 280 E - 380 N 5170 11 10 8.6 1.1

73 280 E - 385 N 4930 10 10 7.4 1.0 74 280 E - 390 N 4490 10 10 7.6 0.9

75 280 E - 395 N 4850 10 9 5.3 1.3

76 280 E - 400 N 4530 10 9 7.0 1.1 77 280 E - 405 N 4620 9 10 7.1 1.0 78 280 E - 410 N 4630 12 11 6.4 1.0

79 280 E - 415 N 4640 10 10 6.8 1.1 80 280 E . 420 N 4200 10 9 6.2 1.1 81 280 E - 425 N 4520 11 9 5.7 1.1 82 280 E - 430 N 5000 10 11 5.4 1.1

83 280 E - 435 N 4610 11 10 6.6 1.0

84 280 E - 440 N 4670 10 12 6.7 1.1

85 280 E - 445 N 5240 12 12 8.0 1.1

86 280 E - 450 N 4850 11 10 6.1 1.0

• 87 280 E - 455 N 4880 10 11 5.4 1.1

88 280 E - 460 N 5170: 11 10 6.6 1.3

89 280 E - 465 N 4930 ' 11 11 4.6 1.2

90 280 E - 470 N 5030 11 10 6.1 1.2

FILE:OFFICE\QPW\AREAO\OWP1 SUU 3

01/27/99


• SUB AREA "O" SURFACE WASTE POND # 1 RESULTS IN BACKGROUND MDA

INSTRUMENTS: S/N

LUDLUM MICRO R METER M/N 19 138420 uR/hr 9 2


CIMMARON SOIL COUNTER 4" X 4" X 16" Nal DETECTOR pCi/g Th (Nat) 1.5 1

REVIEWED BY: '1.J.,(1_. ~ DATE: 2-1-97 BACKGROUNDNOTSUBtRACTED

3" MICRO MICRO pCi/g pCi/g LN GRID LOCATION DETECT R' R' O" - 6'

# C.P.M. SURF 1 METER Total-U Th (Nat) I

91 285 E - 360 N 4840 11 9 6.7 1.2

92 285 E - 365 N 551Q 11 12 7.3 1.4 I

93 285 E - 370 N 5120 10 10 8.4 1.1

94 285 E - 375 N 4020 10 10 7.9 1.0

95 285 E - 380 N 4390 11 9 6.0 1.1

96 285 E - 385 N 4690 11 11 11.0 1.2

97 285 E - 390 N 4500 11 11 7.5 1.5

• 98 285 E - 395 N 4620 11 11 7.8 1.0

99 285 E - 400 N 499d 11 10 8.9 1.1

100 285 E - 405 N 4630 10 10 8.5 1.0

101 285 E - 410 N 4740 10 10 7.3 1.2

102 285 E - 415 N 4510 11 11 9.0 1.0

103 285 E - 420 N 4470 10 10 8.2 1.0

104 . 285 E - 425 N 4460 10 10 7.0 1.0

105 285 E - 430 N 4780 10 9 6.5 1.1

106 285 E - 435 N 5110 9 11 8.0 1.0

107 285 E - 440 N 4450 11 10 5.5 1.0

108 285 E - 445 N 4690 11 10 7.3 1.0

109 285 E - 450 N 4330 11 11 8.4 1.0

110 285 E - 455 N 4590 10 10 6.8 1.3

111 285 E - 460 N 4840 10 11 8.2 1.0

112 285 E - 465 N 4710 10 11 6.5 1.1

113 285 E - 470 N 4830 10 10 7.1 1.1

114 285 E - 475 N 4110 11 9 8.7 1.0

115 290 E - 360 N 5220 10 11 8.6 1.2

116 290 E - 365 N 4580 10 12 6.2 1.0

• 117 290 E - 370 N 4710 11 9 8.8 1.2

118 290 E - 375 N 4630 10 11 7.0 1.2 '

119 290 E - 380 N 4770 11 10 8.1 1.2

120 290 E - 385 N 4390 11 11 8.3 1.0


01/27/99



INSTRUMENTS: S/N

LUDLUM MICRO R METER M/N 19 138420 ~R/hr 9 2



REVIEWED BY: 1,J.,Q. - ~ _,,,,...,,, DATE: ;2...-J-?? V

BACKGROUND NOT SUBTRACTED 3" MICRO MICRO pCi/g pCi/g

LN GRID LOCATION DETECT R' R' O" - 61


121 290 E - 390 N 4830 11 11 9.0 1.0

122 290 E - 395 N 4670 10 11 5.8 1.1

123 290 E - 400 N 5020 11 10 6.6 1.1 124 290 E - 405 N 4440 10 11 8.1 1.0

125 290 E - 410 N 49sd 11 12 5.9 1.1

126 290 E - 415 N 4820 11 12 7.2 1.1

127 290 E - 420 N 5070 12 12 6.5 1.2

• 128 290 E - 425 N 4730 10 10 4.2 1.3 129 290 E - 430 N 4580 11 11 8.0 1.0 130 290 E - 435 N 4630 10 11 8.1 1.1 131 290 E - 440 N 4320 9 11 5.8 1.1 132 290 E - 445 N 4460 10 10 7.3 0.8

133 290 E - 450 N 4790 9 10 5.9 1.2

134 290 E - 455 N 4520 11 10 7.9 1.1

135 290 E - 460 N 4630 10 11 8.0 1.0

136 290 E - 465 N 4500 10 11 11.9 0.9 137 290 E - 470 N 4110 11 10 8.4 1.1 138 290 E - 475 N 4060 10 11 7.8 1.0

139 295 E - 360 N 4530 10 10 7.3 1.3

140 295 E - 365 N 4690 11 10 9.7 1.1 141 295 E - 370 N 4830 11 11 7.9 1.1

142 295 E - 375 N 5180 11 11 9.5 0.9

143 295 E .. 380 N 4950 10 11 7.5 1.1

144 295 E - 385 N 4610 10 10 4.7 1.2

145 295 E - 390 N 4780 11 11 7.0 1.0

146 295 E - 395 N 4330 10 11 6.7 0.9

• 147 295 E - 400 N 4770 9 10 6.6 1.0

148 295 E - 405 N 4750 10 10 5.8 0.8

149 295 E - 410 N 4480 9 10 6.3 0.8

150 295 E - 415 N 4480 10 11 8.7 1.1

FILE:OFFICE\QPW\AREAO\OWP1SUU 5

------ ------ ·· ·· ····· ······ ···-

01/27/99



INSTRUMENTS: SIN




REVIEWED BY: 1,J, Q_. - ~ ~ DATE: .2.-;--99 ,-BACKGROUND NOT SUBTRACTED

3" MICRO MICRO pCi/g pCi/g LN GRID LOCATION DETECT Rt R' O" - 6'


151 295 E - 420 N 409() 10 10 5.3 1.0

152 295 E - 425 N 4190 11 10 8.2 0.8

153 295 E - 430 N 409~ 9 9 6.4 0.9

154 295 E - 435 N 5150 10 10 7.0 0.9

155 295 E - 440 N 445~ 9 10 7.4 1.0

156 295 E - 445 N 4640 10 12 5.5 1.0

157 295 E - 450 N 480¢) 9 10 4.4 1.1

• 158 295 E - 455 N 4750 9 10 6.1 1.1

159 295 E - 460 N 480~ 10 10 9.3 0.9

160 295 E - 465 N 4840 9 10 10.8 1.3 161 295 E - 470 N 4590 11 10 5.3 1.0

162 295 E - 475 N 4420 9 10 7.4 1.0

163 295 E - 480 N 4860 10 11 8.0 1.1

164 300 E - 365 N 4810 11 10 6.9 1.3

165 300 E - 370 N 4470 11 12 5.8 0.9

166 300 E . 375 N 4740 10 10 7.8 1.0

167 300 E - 380 N 4700 10 10 7.3 1.0 168 300 E - 385 N 4600 10 10 6.4 0.8

169 300 E - 390 N 4500 9 10 2.8 1.2

170 300 E - 395 N 4170 11 10 6.8 0.9

171 300 E - 400 N 4760 10 10 6.5 0.9

172 300 E - 405 N 4300 9 9 7.7 0.8

173 300 E - 410 N 4780 9 10 6.1 1.0

174 300 E - 415 N 4170 9 11 5.1 1.1

175 300 E - 420 N 5220 11 9 4.6 1.0

176 300 E - 425 N 4160 11 11 6.4 0.8

• 177 300 E - 430 N 4900 11 10 4.4 1.0

178 300 E - 435 N 4900 11 10 7.7 1.0

179 300 E - 440 N 5030 13 11 7.3 1.0

180 300 E - 445 N 4730 11 10 7.0 0.8


01/27/99



INSTRUMENTS: SIN


LUDLUM 2220, LEAD SHIELDED 3" X 1/2" Nal DETECTOR 48395 CPM 4150 NIA pCi/g Total U 4.0 5

CIMMARON SOIL COUNTER 4" X 4• X 16" Nal DETECTOR pCi/g Th (Nat) 1.5 1

REVIEWED BY: 'h)_.Q, ~ DATE: :L-/-7 9 BACKGROUND NOT SUBT'RACTED

3" MICRO MICRO pCi/g pCi/g LN GRID LOCATION DETECT R' R' 0" -61


181 300 E - 450 N 4470 11 10 6.9 0.9 182 300 E - 455 N 4980 11 10 5.4 1.2

183 300 E - 460 N 4720 11 10 7.1 1.3

184 300 E - 465 N 4860 11 11 11.7 1.1

185 300 E - 470 N 5130 10 9 7.2 1.1

186 305 E - 365 N 4850 11 11 7.5 1.3

187 305 E - 370 N 4830 10 10 7.9 1.0

• 168 305 E - 375 N 4340 10 9 7.1 1.2

189 305 E - 380 N 4790 10 12 8.5 1.0

190 305 E - 385 N 4680 9 9 8.4 1.1

191 305 E - 390 N 4730 10 10 8.9 0.9

192 305 E - 395 N 4370 10 10 7.3 1.0

193 305 E - 400 N 4120 9 9 8.1 1.0

194 305 E - 405 N 4040 10 9 8.2 1.1

195 305 E - 410 N 4740 10 10 4.6 1.3

196 305 E - 415 N 4700 10 10 7.0 1.1

197 305 E - 420 N 4490 10 10 7.6 1.1

198 305 E - 425 N 4780 11 11 8.4 1.0

199 305 E - 430 N 4100 10 10 5.6 1.2

200 305 E - 435 N 4620 10 11 6.5 1.1

201 305 E - 440 N 5040 9 11 10.6 1.4

202 305 E - 445 N 4440 10 10 6.1 1.4

203 305 E - 450 N 4770 9 11 7.6 1.1

204 305 E - 455 N 4600 9 10 5.3 0.9

205 305 E - 460 N 4820 10 10 6.9 1.1

206 310 E - 370 N 4850 12 11 9.0 1.2

• 207 310 E - 375 N 4690 11 10 6.3 1.2

208 310 E - 380 N 468() 10 10 8.9 1.1 I

209 310 E - 385 N 4790 10 10 6.5 1.2

210 310 E - 390 N 5030 9 10 6.7 1.0


01/27/99


• SUB AREA "0 " SURFACE WASTE POND# 1 RESULTS IN BACKGROUND MDA

INSTRUMENTS: S/N


LUDLUM 2220. LEAD SHIELDED 3" X 1/2" Nal DETECTOR 48395 CPM 4150 NIA pCi/g Total U 4.0 5

CIMMARON SOIL COUNTER 4" X 4" X 16" NaJ DETECTOR pCi/g Th (Nat) 1.5 1

REVIEWED BY: 'l-<.J,ct. ~~ DATE: ?--1-?9 BACKGROUND NOT SUBTRACTED

3" MICRO MICRO pCi/g pCi/g LN GRID LOCATION DETECT R' R' O" - 61


211 310 E - 395 N 4820 9 10 8.1 1.0 212 310 E - 400 N 4450 9 9 8.0 0.8

213 310 E - 405 N 4770 10 9 7.6 1.0

214 310 E - 410 N 4410 10 12 7.0 1.0

215 310 E - 415 N 4760 10 10 6.1 1.3

216 310 E - 420 N 5170 10 11 8.3 1.1

217 310 E - 425 N 5040 11 11 6.6 1.0

• 218 310 E - 430 N 4800 9 12 6.7 1.0

219 310 E - 435 N 5080 11 10 5.4 1.2

220 310 E - 440 N 4050 11 10 5.1 1.0

221 310 E - 445 N 5460 10 10 6.7 1.4

222 310 E - 450 N 4960 9 11 8.3 0.8

223 315 E - 370 N 4490 11 10 5.3 1.1

224 315 E - 375 N 4800 10 10 7.2 1.1

225 315 E - 380 N 5020 11 10 6.8 1.2

226 315 E - 385 N 4300 10 10 5.3 1.3

227 315 E - 390 N 4940 10 10 6.4 1.0

228 315 E - 395 N 4380 11 10 7.2 1.1

229 315 E - 400 N 4460 11 10 6.2 1.0 230 315 E - 405 N 4500 10 10 7.9 1.4 231 315 E - 410 N 4840 10 11 6.2 1.1

232 315 E - 415 N 4950 11 11 3.6 1.3

233 315 E - 420 N 4880 10 10 7.6 1.4

234 315 E - 425 N 4600 9 10 3.6 1.1

235 315 E - 430 N 4120 9 9 6.1 1.0

236 315 E - 435 N 5150 9 11 4.4 1.2

• 237 315 E - 440 N 4910 11 10 6.9 1.2

238 320 E - 375 N 4610 12 11 5.5 1.3

239 320 E - 380 N 4970 9 11 3.9 1.4

240 320 E - 385 N 4100 10 10 4.8 0.8

FILE :OFFICE\QPW\AREAO\OWP1 SUU 8

01/27/99



INSTRUMENTS: SIN

LUDLUM MICRO R METER MIN 19 138420 pR/hr 9 2


CIMMARON SOIL COUNTER 4" X 4" X 16" Nat DETECTOR pCi/g Th (Nat) 1.5 1

REVIEWED BY: 1,J. a . M~ ~ DATE: :i...-1-7 r BACKGROUND NOT $UBTRACTED

3" . MICRO MICRO pCi/g pCi/g LN GRID LOCATION DETECT R' R' O" - 6'

# C.P.t.1. SURF 1 METER Total-U Th (Nat)

241 320 E - 390 N 4510 12 10 5.9 1.1 242 320 E - 395 N 460(D 11 11 7.2 1.2

243 320 E - 400 N 4760 10 10 6.4 1.1

244 320 E - 405 N SOOQ 13 11 6.1 1.2 I

245 320 E - 410 N 482~ 11 10 6.3 1.0

246 320 E - 415 N 4630 10 10 7.8 1.0

247 320 E - 420 N 4210 8 9 5.8 1.1

• 248 320 E - 425 N 489~ 10 10 6.7 1.3 249 320 E - 430 N 4520 9 10 6.7 1.2

250 325 E . 375 N 4400 9 9 13.2 1.3

251 325 E - 380 N 4410 9 9 4.7 1.2

252 325 E - 385 N 4870 11 11 8.1 1.1 253 325 E - 390 N 4890 11 10 6.5 1.0 254 325 E - 395 N 4580 10 10 8.1 1.1

255 325 E - 400 N 4690 11 11 7.7 1.2

256 325 E - 405 N 4980 10 12 6.2 1.3

257 325 E - 410 N 4670 11 10 7.2 1.0

258 325 E - 415 N 4570 9 10 4.2 1.1 259 325 E - 420 N 4710 10 10 4.8 1.3

260 330 E - 380 N 5220 10 11 7.2 1.0

261 330 E - 385 N 5090 10 10 4.6 1.1

262 330 E - 390 N 4900 10 11 5.4 1.4

263 330 E - 395 N 4910 10 11 6.5 1.1

264 330 E - 400 N 4640 11 11 6.0 1.2

265 330 E - 405 N 4270 11 11 4.0 1.0

266 330 E - 410 N 4800 10 11 7.2 0.9

• 267 335 E - 380 N 4230 10 9 3.2 1.1

268 335 E - 385 N 4890 10 9 5.4 1.1

269 335 E - 390 N 4440 9 10 5.4 0.6

270 335 E - 395 N 3890 9 10 3.5 0.5


01/27/99


• SUB AREA ''O" SURFACE WASTE POND# 1 RESULTS N BA .... K~ROJ D

INSTRUMENTS: S 1N I

LUDLUM MICRO R METER M/N.19 I

138420 µR/hr 9 2

LUDLUM 2220, LEAD SHIELDED 3" X 1/2" Nal DETECTOR 48395 CPM 4150 N/A pCi•a To u 40 5

CIMMARON SOIL COUNTER 4" X 4" X 16" Nal DETECTOR p 'g ( :) 1 5 1

REVIEWED BY: 1-,J; Q, ~~ DATE: .z.-1 ~ r? R

3" MICRO MICRO pCi/g pCi/g LN GRID LOCATION DETECT R' R' 0"-6'

# C.P.M. SURF 1 METER - ::iii I I (tJcf)

271 335 E . 400 N 5110 ! 11 11 7.0 1.1

272 340 E - 385 N 3820 . 10 8 5.1 0.3

•

• FILE;OFFICE\QPW'AREAO\OWP1 SUU 10

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01/27/99

100

(/) C, 80 z -Cl <{ w 60 0:: LL 0

40 0:: llJ cc ~ 20 :J z

0

PHASE Ill -AREA 110•• WASTE POND# 1-AFFECTED CIMARRON SOIL COUNTER SURFACE SAMPLES TOTAL URANIUM SOIL SAMPLE RESULTS SITE BACKGROUND OF 4 pCi/g NOT SUBTRACTED

DECEMBER, 1998

URANIUM SAMPLE DATA FREQUENCY DISTRIBUTION

3 4 5 6 7 8 9 10 11 12 13 pCi/g

NUMBER OF SAMPLES AVERAGE SAMPLE MINIMUM SAMPLE MAXIMUM SAMPLE STANDARD DEVIATION

272 6.8 2.8

13.2 1.5


•

•

•

CIMARRON CORPORATION - CIMARRON FACILITY TRUE MEAN ACTIVITY VS. GUIDELINE VALUE AT 95% CONFIDENCE AREA "O" WASTE POND # 1 (AFFECTED) SURFACE

n = oCi/11 TOTAL U Number n (IWII) (n-H)"

1 6.4 -0..4 0.2 2 6.5 --0.3 0.1 3 5.2 -1.6 2.7 ,4 6.7 --0.1 0.0 6 4.9 -1.9 3.8 6 8.9 2.1 4.2 7 9.6 2.8 7.6 8 6.6 ,-0,2 0.1 9 7.0 0.2 0.0 10 8.3 1.5 2.1 11 6.8 --0.0 0.0 12 9.2 2.-4 u 13 9.6 2.8 7.6 14 8.6 1.8 3.1 15 6.6 -0.2 0.1 18 6.6 -0.2 0,1 17 10.1 3.3 10.6 18 8.2 u 1.8 19 5.2 -1.8 2.7 20 8,4 1.6 2.4 21 4.1 -2.7 7.6 22 6.3 --0.5 0.3 23 7.1 0.3 0.1 24 6.7 -0.1 0.0 26 9.7 2.9 8.1 26 6.8 --0.0 0.0 27 7.3 0.5 0.2 28 5.9 -0.9 0.9 29 7.6 0,8 0.6 30 5.1 -1.7 3.1 31 4.4 -2.-4 6.0 32 8.9 2.1 4.2 33 6.0 -0.8 0.7 3,4 5.4 -U 2.1 35 5.0 -1.8 3.4 36 6.0 --0.8 0.7 37 5.7 -1.1 1.3 38 6.0 -0.8 0.7 39 5.9 -0.9 o.s 40 5.9 -0.9 0.9 41 6.5 -0,3 0.1 42 4.0 -2.8 8.1 '3 4.3 -2.6 6..6 4"' 6.3 -0.5 0.3 45 6.1 --0.7 0.6 46 7 .0 0.2 0.0 47 7.8 1.0 0.9 48 7.3 0.5 0.2 49 8.2 1.A 1.8 50 6.3 -0.5 0.3

341.9 89.6 371.6 107.3 3"'7,6 124.3 334.8 135.0 128.0 68.5 0.0 0.0

total 1862.8 640.0 Sumtnl Sumfn-N)"

file:owp1 cmpu. wb2

No. of Samples (x) : I 272

COUNT TIME: 15 MINUTES

Sample Mea'1 (N) = Sum(n) + (x)

Sample Mu~ (N): j 6.85 !

standard 0.-.,Jation (Sd) "" SQRT ((n-H)" + (x -1 J]

Standard Dtlv. lation: ~ 2 std O.vl,itlons: ~

Degree of Fn;.ed om(,.= (x) -1 Data llsted on Table 8-1 : (df) = 1.653 I

Are.a's Average Leve-I (Ap) = (N) + (di) x I(Sd)ISQRT(x)l

(AJJ) = Effl pCi/gU TOTAL U O®EUNl!:VA.LUE: pCi/gU TOTAL u

Acceptable Level: pCi/gU TOTAL U

TABLE B-1

FactOf'S for Comp.; rlslon of Survey Data with Guidelines

ldll 96% 97.5% lcffl 96% 97.5% 1 6.314 12.706 19 1.729 2.093 2 2.92 4.303 20 1.726 2.086 3 2.353 3.182 21 1.721 2.08 4 2.132 2.776 22 1.717 2.07-4 5 2.015 2.671 23 1.714 2.069 8 1.943 2.447 2-4 1.711 2.064 7 1.896 2.365 25 1.708 2.06 8 1.86 2.306 26 1.706 2.056 9 1.833 2.262 27 1.703 2.062 10 1.812 2.228 28 1.701 2.048 11 1.796 2.201 29 1.699 2.0-45 12 1.782 2.179 30 1.697 2.042 13 1.771 2.16 40 1.684 2.021 14 1.761 2.1"5 60 1.671 2 15 1.753 2.131 120 1.668 1.98 16 1.746 2.12 400 1.649 1.966 17 1.74 2.11 tnnntta 1.645 1.96 18 1.73"' 2.101

For values of Degrees of Freedom not llsted:

lnt.rpolate betw-n th,...e_ll_sted_v_aT"lu_es_. __ -r----r------,

(df) high value(Z) 400 Is 8 1.6-U 95% (df) low valua{Y) 120 Is A 1.658 96"1,,

Desired value(df) (X) 271 is calculated as follow:

EXP[( (Ln(B)-,Ln(A) ) + ~Z•Y) ) (X-? + Ln(Al l The (df) value for (X) I 271 J 1.663 I 96%

PERFORMED ev,J1,hJw,/-V ,#af1\ DATE: / - :Z.. 7- 'i'i

REVIEWED BY: 1J' C( ' ~

PAGE 1 Of 4


Ci/ TOTAL U Ci/ TOTAL U n = p1 I n=p, II~

• Number n (n-N) (n-Nr 51 6.4 ..0.45 0.20

Number n fn-Nl (n-Nr 101 7.3 0.45 0.20

52 8.3 1.45 2.11 102 9.0 2.15 4.63 53 7.9 1.05 1.10 103 8.2 1.35 1.83 54 6.7 --0.15 0.02 : 104 7.0 0.15 0.02 55 6.0 -0.85 0.72 105 6.5 -0.35 0.12 56 4.9 -1.95 3.80 : 106 8.0 1.15 1.33 57 5.2 -1.65 2.72 : 107 5.5 -1.35 1.82 58 8.0 -0.85 0.72 '. 108 7.3 0.45 0.20 59 4.4 -2.45 6.00 ' 109 8.4 1.55 2.41 60 5.7 -1.15 1.32 110 6.8 -0.05 0.00 61 7.9 1.05 1.10 : 111 8.2 1.35 1.83 62 5.1 -1.75 3.06 • 112 6.5 -0.35 0.12 63 7.6 0.75 0.56 113 7.1 0.25 0.06 64 6.7 -0.15 0.02 , 114 8.7 1.85 3.43 65 7.9 1.05 1.10 115 8,6 1.75 3.07 66 6.9 0.05 0.00 . 116 6.2 -0.65 0.42 67 5.4 -1.45 2.10 : 117 8.8 1.95 3.81 68 7.0 0.15 0.02 118 7.0 0.15 0.02 69 8.3 1.45 2.11 119 8.1 1.25 1.57 70 4.7 -2.15 4.62 120 8.3 1.45 2.11 71 9.3 2.45 6.01 121 9.0 2.15 4.63 72 8.6 1.75 3.07 122 5.8 -1.05 1.10 73 7.4 0.55 0.30 123 6.6 -0.25 0.06 74 7.6 0.75 0.56 124 8.1 1.25 1.57

• 75 5.3 -1.55 2.40 76 7.0 0.15 0.02 77 7.1 0.25 0.06

125 5.9 -0.95 0.90 126 7.2 0.35 0.12 127 6.5 -0.35 0.12

78 6.4 -0.45 0.20 128 4.2 -2.65 7.02 79 6.8 -0.05 0.00 129 8.0 1.15 1.33 80 6.2 -0.65 0.42 130 8.1 1.25 1.57 81 5.7 -1.15 1.32 131 5.8 -1.05 1.10 82 5.4 -1.45 2.10 132 7.3 0.45 0.20 83 6.6 --0.25 0.06 133 5.9 -0.95 0.90 84 6.7 --0.15 0.02 134 7.9 1.05 1.10 85 8.0 1.15 1.33 135 8.0 1.15 1.33 86 6.1 -0.75 0.56 136 11.9 5.05 25.51 87 5.4 -1.45 2.10 137 B.4 1.55 2.41 88 6.6 --0.25 0.06 138 7.8 0.95 0.90 89 4.6 -2.25 5.06 139 7.3 0.45 0.20 90 6.1 -0.75 0.56 140 9.7 2.85 8.13 91 6.7 -0.15 0.02 141 7.9 1.05 1.10 92 7.3 0.45 0.20 142 9.5 2.65 7.03 93 8.4 1.55 2.41 143 7.5 0.65 0.42 94 7.9 1.05 1.10 144 4.7 -2.15 4.62 95 6.0 -0.85 0.72 145 7.0 0.15 0.02 96 11.0 4.15 17.23 146 6.7 -0.15 0.02 97 7.5 0.65 0.42 147 6.6 -0.25 0.06 98 7.8 0.95 0.90 148 5.8 -1.05 1.10 99 8.9 2.05 4.21 149 6.3 -0.55 0.30

• 100 8.5 1.65 2.73

341.9 89.6

150 8.7 1.85 3.43

371.6 107.3 Sum(n) Sumln-Nr Sum(n) S1.m(n-N)2

PAGE20F4

file:owp1 cmpu.wb2


C"/ TOTAL U Ci/ TOTAL U n = p1 1r11 n=p r4J

• Number n fn-N) (n-N)I 151 5.3 -1.55 2.40

Nl.fflber n (n-Nl (n-Ntz 201 10.6 3.75 14.07

152 8.2 1.35 1.83 202 6.1 -0.75 0.56 153 6.4 -0.45 0.20 203 7.6 0.75 0.56 154 7.0 0.15 0.02 204 5.3 -1.55 2.40 155 7.4 0.55 0.30 205 6.9 0.05 0.00 15& 5.5 -1.35 1.82 206 9.0 2.15 4.63 157 4.4 -2.45 6.00 207 6.3 -0.55 0.30 158 6.1 -0.75 0.56 208 8.9 2.05 4.21 159 9.3 2.45 6.01 209 6.5 -0.35 0,12 160 10.8 3.95 15.61 210 6.7 -0.15 0.02 161 5.3 -1.55 2.40 : 211 8.1 1.25 1.57 162 7.4 0.55 0.30 212 8.0 1.15 1.33 163 8.0 1.15 1.33 213 7.6 0.75 0.56 164 6.9 0.05 0.00 . 214 7.0 0.15 0.02 165 5.8 -1.05 1.10 : 215 6.1 --0.75 0.56 166 7.8 0.95 0.90 : 216 8.3 1.45 2.11 167 7.3 0.45 0.20 ; 217 6.6 --0.25 0.06 168 6.4 -0.45 0.20 . 218 6.7 --0.15 0.02 169 2.8 -4.05 16.39 219 5.4 -1.45 2.10 170 6.8 -0.05 o.oo 220 5.1 -1.75 3.06 171 6.5 -0.35 0.12 · 221 6.7 -0.15 0.02 172 7.7 0.85 0.72 222 8.3 1.45 2.11 173 6.1 -0.75 0.56 223 5.3 -1.55 2.40 174 5.1 -1.75 3.06 224 7.2 0.35 0.12

• 175 4.6 -2.25 5.06 176 6.4 -0.45 0.20 177 4.4 -2.45 6.00

225 6.6 -0.05 0.00 226 5.3 -1.55 2.40 227 6.4 -0.45 0.20

178 7.7 0.85 0.72 228 7.2 0.35 0.12 179 7.3 0.45 0.20 229 6.2 -0.65 0.42 180 7.0 0.15 0.02 . 230 7.9 1.05 1.10 181 6.9 0.05 0.00 231 6.2 -0.65 0.42 182 5.4 -1.45 2.10 232 3.6 --3.25 10.56 183 7.1 0.25 0.06 233 7.6 0.75 0.56 184 11.7 4.85 23.53 234 3.6 -3.25 10.56 185 7.2 0.35 0.12 235 6.1 -0.75 0.56 186 7.5 0.65 0.42 236 4.4 -2.45 6.00 187 7.9 1.05 1.10 237 6.9 0.05 o.oo 188 7.1 0.25 0.06 238 5.5 -1.35 1.82 189 8 .5 1.65 2.73 239 3.9 -2.95 8.70 190 8.4 1.55 2.41 240 4.8 -2.05 4.20 191 8.9 2.05 4.21 241 5.9 -0.95 0.90 192 7.3 0.45 0.20 242 7.2 0.35 0.12 193 8.1 1.25 1.57 243 6.4 -0.45 0.20 194 8.2 1.35 1.83 244 6.1 -0.75 0.56 195 4.6 -2.25 5.06 245 6.3 -0.55 0.30 196 7.0 0.15 0.02 246 7.8 0.95 0.90 197 7.6 0.75 0.56 247 5.8 -1.05 1.10 198 8.4 1.55 2.41 248 6.7 -0.15 0.02 199 5.6 -1.25 1.56 249 6.7 -0.15 0.02

• 200 6.5 -0.35 0.12

347.6 124.3

250 13.2 6.35 40.34

334.8 135.0 Sum(n) Sum(n-Nr Sum(n) Sa.n(n-Nr

PAGE30F4

file:owp1 cmpu.wb2


c·1 TOTAL U Ci/ TOTAL U n= p 1rq n=p rq

• Number n (n-N) fn-Nf 251 4.7 -2.15 4.62

Number n (n-N) fn-N)S

301 0.00 0.00 252 8.1 1.25 1.57 302 0.00 0.00 253 6.5 -0.35 0.12 303 0.00 0.00 254 8.1 1.25 1.57 , 304 0.00 0.00 255 7.7 0.85 0.72 : 305 0.00 0.00 256 6.2 -0.65 0.42 : 306 o.oo 0.00 257 7.2 0.35 0.12 ; 307 0.00 0.00 258 4.2 -2.65 7.02 ; 308 0.00 0.00 259 4.8 -2.05 4.20 : 309 0.00 0.00 260 7.2 0.35 0.12 : 310 0.00 0.00 261 4.6 -2.25 5.06 311 o.oo 0.00 262 5.4 -1.45 2.10 312 0.00 0.00 263 6.5 -0.35 0.12 '. 313 o.oo 0.00 264 6.0 -0.85 0.72 : 314 0.00 0.00 265 4.0 -2.85 8.12 I 315 0.00 0.00 266 7.2 0.35 0.12 : 316 0.00 0.00 267 3.2 -3.65 13.31 · 317 0.00 0.00 268 5.4 -1.45 2.10 : 318 0.00 0.00 269 5.4 -1.45 2.10 319 0.00 0.00 270 3.5 -3.35 11.22 320 0.00 0.00 271 7.0 0.15 0.02 321 0.00 0.00 272 5.1 -1.75 3.06 322 0.00 0.00 273 0.00 0.00 323 0.00 0.00 274 0.00 0.00 324 0.00 0.00

• 275 0.00 0.00 276 0.00 0.00 2n 0.00 0.00

325 0.00 0.00 326 0.00 0.00 327 0.00 0.00

278 0.00 0.00 328 0.00 0.00 279 0.00 0.00 329 0.00 0.00 280 0.00 0.00 330 0.00 0.00 281 0.00 0.00 331 0.00 0.00 282 0.00 0.00 332 o.oo 0.00 283 0.00 0.00 333 0.00 0.00 284 0.00 0.00 334 0.00 0.00 285 0.00 0.00 335 0.00 0.00 286 0.00 0.00 336 0.00 0.00 287 0.00 0.00 337 0.00 0.00 288 0.00 0.00 338 0.00 0.00 289 0.00 0.00 339 0.00 0.00 290 0.00 0.00 340 0.00 0.00 291 0.00 0.00 341 0.00 0.00 292 0.00 0.00 342 0.00 0.00 293 0.00 0.00 343 0.00 0.00 294 0.00 o.oo 344 0.00 0.00 295 0.00 0.00 345 0.00 0.00 296 0.00 0.00 346 0.00 0.00 297 0.00 0.00 347 0.00 0.00 298 0.00 0.00 348 0.00 0.00 299 0.00 0.00 349 0.00 0.00

• 300 0.00 0.00

128.0 68.5

350 0.00 0.00

0.0 0.0 Sum(n) Sumfn-Nr Sum(n) Sum(n-Nr

PAGE4 OF4

file:owp1 cmpu.wb2

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01/27/99

PHASE Ill - AREA "O" WASTE POND # 1- AFFECTED CIMARRON SOIL COUNTER SURFACE SAMPLES Th (NAT) SOIL SAMPLE RESULTS SITE BACKGROUND OF 1.5 pCi/g NOT SUBTRACTED

DECEMBER, 1998

THORIUM SAMPLE RESULTS FREQUENCY DISTRIBUTION

70

C/) 60 w _J

~ 50

c5§ 40 LL

o 30 0::: LlJ

~ 20

~ 10

0 0.3 0.5 0.7 0.9 1.1 1.3 1.5

pCi/g

NUMBER OF SAMPLES AVERAGE SAMPLE MINIMUM SAMPLE MAXIMUM SAMPLE STANDARD DEVIATION

272 1.1 0.3 1.6 0.2

FILE:OFFJCE\QPW\AREAO\OWP1SUU 1

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•

•


n .. nCi/2 Th (NAn Number n (n-N) (n-N)2

1 1.2 0.08 0.01 l 1.-4 0.18 0.08 3 1.6 0.48 0.23 4 1.6 0.48 0.23 5 1.2 0.08 0.01 6 1.2 0.08 0.01 7 1.4 0.18 0.68 8 1.3 0.18 0.03 9 1.1 -G.Ol 0.00

10 1.4 0.18 0.08 11 1.3 0.18 0.03 ll 1.2 0.08 0.01 13 1.3 0.18 0.03 14 1.2 0.08 0.01 IS 1.2 0.08 0.01 16 1.2 0.08 0.01 17 1.2 0.08 0.01 18 1.4 0.28 0.08 19 1.3 0.18 0.03 20 1.5 0.38 0.15 21 1.5 0.38 0.15 22 1.4 0.28 0.08 23 1.4 0.28 0.08 :24 1.3 0.18 0.03 :25 1.2 0.08 0.01 26 1.3 0.18 0.03 27 1.2 0.68 0.01 18 1.1 ..0.02 0.00 29 1.0 ..0.12 0.01 30 1.1 -0.02 0.00 31 1.3 0.]8 0.03 32 1.2 0.68 0.01 33 1.4 0.18 0.08 34 1.5 0.38 0.15 35 1.4 0.28 0.08 36 1.2 0.68 0.01 37 1.4 0.28 0.08 38 1.3 0.18 0.03 39 1.2 0.08 0.01 40 1.3 0.18 0.03 41 1.0 -0.12 0.01 42 u 0.18 0.08 43 1.3 0.18 0.03 44 1.2 0.08 0.01 45 1.3 0.18 0.03 46 1.4 0.28 0.08 47 1.3 0.18 0.03 48 u -0.02 0.00 49 1.3 0.18 0.03 so 1.3 0.18 0.03

55..7 1.041 53.1 0.859 51.6 J.3:25 56.7 1.164 21.7 1.594

304.3 8.434 Sum(n) Sum(n-M2

FILE:OWP1 CMTH

No. of Samples (:1) : I 272

COUNT TIME: 15 MJM.ITES

Sam pl~ Mean (N) = Sum(n) + (x) Sampl~ Mean (N): ! 1.12 I

Standarf Deviation (Sd) • SQRT [(n-Nf + (J: • l)J

Standard ~vi•lion: I 0.18 2 Std Oeviations: 0.35 Degree!ofFreedom(df),• (i:)- I Data listed on Table B-1

(di)-- I 1.653 ! Area's ~,·erage Level (Aµ)., (N) + (df) x [(Sd)/sqrt(1)}

, (Aµ)• rn-14 pCi/gTh (NAT) GUJDl\:LINE VALUE: JO pCi/gTh (NAT)

Accept1tble Level: 4.0 pCi/gTh (NAT) (15% or GUIDELINE PLUS BACKGROUND)

! TABLE B-1 Fadtors for Compamion of Sui -vev Data with Guidelines (dO! 95•1. 97.So/e (dO 95•;. 97.s•;. 1 6.314 12.706 19 I. 7.29 l.093 l 2.92 4.303 10 1.725 l.086 3 2.353 3.18l 11 1.721 l.08 4 2.131 2.776 ll 1.717 l.074 5 2.0)5 1.571 l3 1.714 l.069 6 1.943 :2.447 24 1.711 l.064 7 1.895 1.365 15 1.708 2.06 8 1.86 2.306 26 1.706 l.056 9 1.833 2.162 27 1.703 l.051 10 J.812 l.118 18 1.701 l.048 11 1.796 2.101 l9 1.699 l.045 12 1.782 2.179 30 J.697 l .041 13 1.771 1.16 40 1.684 1.021 14 J.761 l.145 60 1.671 2 15 1.753 l.131 120 1.658 1.98 16 1.746 2.12 400 1.649 1.966 17 1.74 1.11 Infinite 1.645 1.96 18 l.734 2,101

For values of Degrees of Freedom DOt listed:

Interpolate between the;::..l:;;is:.:..:fed:.:....:v=aJ;-=;ues.;:::::.. __ -,------r----,

(di) hiih value(Z) 400 is 1.649 95•;. (di) low value(Y) 120 is A 1.658 95•;•

Desired vaJue(dO (X) 271 is calculated as follow: EXPI( (Ln(B) - Ln(A) ) + (Z - Y) ) (X - Y) + Ln(A) ]

Tile (df) value for (X) l 171 I 1.653 I 95•;.

PFJ<FORMEDBY,ri:!17/,J' ~ REVIEWED BY: "t.J LU, r ~

DATE:

DATE:

Page 1 of4

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n ... nCiltr Th (NA n I"•-= nO/" Th (NATI Number n (n-N) (n-~ Number n (n-N) (n--NY

51 1.2 0.08 0.01 101 1.2 0.08 0.01 52 1.1 -0.02 0.00 102 1.0 -0.12 0.01 53 1.3 0.18 0.03 103 1.0 -0.ll 0.01 54 1.3 0.18 0.03 104 1.0 -0.11 0.01 55 1.1 -0.02 0.00 105 1.1 -0.02 0.00 56 1.1 -0.02 0.00 106 1.0 -0.12 0.01 57 1.3 0.18 0.03 107 1.0 -0.11 0.01 58 0.8 ..0.32 0.10 108 1.0 -0.12 0.01 59 1.2 0.08 0.01 : 109 1.0 -0.12 0.01 60 1.1 -0.02 0.00 HO 1.3 0.18 0.03 61 1.0 -0.12 0.01 111 1.0 -0.12 0.01 62 1.2 0.08 0.01 111 1.1 -0.02 0.00 63 0.9 -0.22 0.05 113 1.1 -0.02 0.00 64 0.9 --0.22 0.05 114 1.0 -0.ll 0.01 65 , .3 0.18 0.03 115 1.2 0.08 0.01 66 1.4 0.28 0.08

I

116 1.0 --0.12 0.01 67 1.0 -0.12 0.01 117 1.2 0.08 0.01 68 0.9 -0.22 0.05 118 1.2 0.08 0.01 69 1.1 -0.02 0.00 119 1.2 0.08 0.01 70 1.2 0.08 0.01 120 1.0 -0.12 0.01 71 0.9 -0.22 0.05 121 1.0 ..0.12 0.01 72 1.1 -0.02 0.00 122 1.1 -0.02 0.00 73 1.0 -0.12 0.01 123 1.1 --0.02 0.00 74 0.9 -0.22 o.~ 124 1.0 -0.12 0.01 75 1.3 0.]8 0.03 125 1.1 -0.02 0.00 76 1.1 -0.02 0.00 126 1.1 -0.02 0.00 77 1.0 -0.11 0.01 127 1.2 0.08 0.01 78 1.0 -0.12 0.01 128 1.3 0.18 0.03 79 1.1 -0.02 0.00 129 1.0 --0.12 0.01 80 1.1 -0.02 0.00 130 1.1 -0.02 0.00 81 1.1 -0.02 0.00 131 1.1 --0.02 0.00 82 1.1 -0.0l 0.00 132 0.8 --0.32 0.10 83 1.0 -0.12 0.01 133 1.2 0.08 0.01 84 1.1 -0.02 0.00 134 1.1 -0.02 0.00 85 1.1 -0.0l 0.00 135 1.0 ..0.12 0.01 86 1.0 -0.12 0.01 136 0.9 -0.22 0.05 87 u -0.0l 0.00 137 1.1 -0.02 0.00 88 1.3 0.18 0.03 138 1.0 -0.12 0.01 89 1.2 0.08 0.01 139 1.3 0.18 0.03 90 1.2 0.08 O.Ol 140 1.1 -0.02 0.00 91 1.2 0.08 0.01 141 1.1 -0.02 0.00 92 u 0.28 0.08 142 0.9 -0.22 0.05 93 1.1 -0.02 0.00 143 1.1 -0.02 0.00 94 1.0 -0.12 0.01 144 1.2 0.08 0.01 95 1.1 -0.02 0.00 145 1.0 -0.12 0.01 96 1.2 0.08 0.01 146 0.9 -0.22 0.05 97 1.5 0.38 0.15 147 1.0 -0.12 0.01 98 1.0 -0.12 0.01 148 0.8 -0.32 0.10 99 1.1 ..0.02 0.00 149 0.8 -0.32 0.10

100 1.0 -0.12 0.01 150 1.1 -0.02 0.00

55.7 1.041 53.1 0.859

Swn(n) Sum(n-N)1 Surn(n) Sum(n-N)2

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n • nCi/~ Th (NA TI n - nCl/v Th <NA TI Number n (n-M {n,.N),Z Nwnber n (n-N) (n-N)l

151 1.0 -0.12 0.01 201 1.4 0.28 0.08 152 0.8 -0.32 0.)0 202 1.4 0.28 0.08 153 0.9 -0.22 0.05 203 1.1 -0.02 0.00 154 0.9 -0.22 0.05 204 0.9 ..0.22 0.05 155 1.0 -0.12 0.01 205 1.1 ..0.02 0.00 156 1.0 -0.12 0.01 206 1.2 0.08 0.01 157 1.1 -0.0l 0.00 207 1.2 0.08 0.01 158 1.1 -0.02 0.00 208 1.1 ..0.02 0.00 159 0.9 -0.22 0.05 ; 209 1.2 0.08 0.01 160 1.3 0.18 0.03 210 1.0 -0.ll 0.01 161 1.0 -0.11 0.0) ; 211 1.0 --0.ll 0.01 162 1.0 -0.ll 0.01 212 0.8 --0.32 0.10 163 1.1 -0.0l 0.00 213 1.0 --0.12 0.01 164 1.3 0.18 0.03 214 1.0 --0.12 0.01 165 0.9 --0.22 0.05 215 1.3 0.18 0.03 166 1.0 --0.12 0.01 216 1.1 --0.02 0.00 167 1.0 --0.12 0.0) 217 1.0 -0.12 0.01 168 0.8 --0.32 0.10 218 1.0 -0.12 0.01 169 1.2 0.08 0.01 219 1.2 0.08 0.01 170 0.9 --0.22 0.05 220 1.0 --0.12 0.01 171 0.9 --0.22 0.05 221 1.4 0.28 0.08 172 0.8 --0.32 0.10 222 0.8 -0.32 0.10 173 1.0 -0.ll 0.01 223 1.1 -0.02 o.oo 174 1.1 -0.02 0.00 224 1.1 -0.02 0.00 175 1.0 ..0.12 0.01 225 1.2 0.08 0.01 176 0.8 --0.32 0.10 226 1.3 0.18 0.03 177 1.0 -0.12 0.01 227 1.0 --0.12 0.01 17H 1.0 -0.12 0.01 228 1.1 -0.02 0.00 179 1.0 -0.12 0.01 229 1.0 ..0.12 0.01 180 0.8 -0.32 0.10 230 1.4 0.28 0.08 181 0.9 -0.22 0.05 231 1.1 --0.02 0.00 182 1.2 0.08 0.01 232 1.3 0.18 0.03 183 1.3 0.)8 0.03 233 1.4 0.28 0.08 184 1.1 --0.02 0.00 234 1.1 ..O.o2 0.00 185 1.1 -0.02 0.00 235 1.0 --0.12 0.01 186 1.3 0.18 0.03 236 1.2 0.08 0.01 187 1.0 -0.12 0.01 237 1.2 0.08 0.0) 188 1.2 0.08 0.01 238 1.3 0.18 0.03 189 1.0 -0.12 0.01 239 1.4 0.28 0.08 190 1.1 -0.0l 0.00 240 0.8 -0.32 O.IO 191 0.9 -0.22 0.05 241 1.1 -0.02 0.00 192 1.0 ...0.12 0.01 242 1.2 0.08 0.01 193 1.0 ...0.12 0.01 243 1.1 ..0.02 0.00 194 1.1 -0.02 0.00 244 1.2 0.08 0.01 195 1.3 0.18 0.03 245 1.0 --0.12 0.01 196 1.1 --0.02 0.00 246 1.0 -0.12 0.01 197 1.1 -0.02 0.00 247 1.1 -0.0l 0.00 198 1.0 -0.12 0.01 248 1.3 0.18 0.03 199 1.2 0.08 0.01 249 1,2 0.08 0.01 200 1.1 --0.02 0.00 250 1.3 0.18 0.03

51.6 1.325 56.7 1.264

Sum(n) Sumtn-N)Z Sum(n) Swn(n-NY

Pagel of4

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n - oC1/e: Th (NAT) 11 ... pCl/J! Th (NA TI Number n (n-N) (n-NY Nwnber n (n-N) (n-N)l

251 1.2 0.08 0.01 301 0.00 0.00 252 1.1 --0.0l 0.00 302 0.00 0.00 253 1.0 --0.12 0.01 303 0.00 0.00 254 1.1 -0.02 0.00 304 0.00 0.00 255 1.2 0.08 0.01 305 0.00 0.00 2S6 1.3 0.18 0.03 : 306 0.00 0.00 257 1.0 -0.tz 0.01 : 307 0.00 0.00 258 1.1 -0.02 0.00 308 o.oo 0.00 259 1.3 0.18 0.03 309 0.00 0.00 260 1.0 -0.ll 0.01 310 0.00 0.00 261 1.1 -0.02 0.00 311 0.00 0.00 262 1.4 0.28 0.08 312 0.00 0.00 263 1.1 -0.02 0.00 313 0.00 0.00 264 1.2 0.08 0.01 314 0.00 0.00 265 1.0 -0.1l 0.01 315 0.00 0.00 266 0.9 -0.22 0.05 316 0.00 0.00 267 1.1 -0.02 0.00 317 0.00 0.00 268 1.1 -0.02 0.00 318 0.00 0.00 269 0.6 -0.52 0.27 319 0.00 0.00 270 0.5 -0.62 0.38 320 0.00 0.00 271 1.1 -0.02 0.00 321 0.00 0.00 272 0.3 -0.82 0.67 322 0.00 0.00 273 0.00 0.00 323 0.00 0.00 274 0.00 0.00 324 0.00 0.00 275 0.00 0.00 325 0.00 0.00 276 0.00 0.00 326 0.00 0.00 277 0.00 0.00 327 0.00 0.00 278 0.00 o.oo 328 0.00 0.00 279 0.00 0.00 329 0.00 0.00 280 0.00 0.00 330 0.00 0.00 281 0.00 0.00 331 0.00 0.00 282 0.00 0.00 332 0.00 0.00 283 0.00 0.00 333 0.00 0.00 284 0.00 0.00 334 0.00 0.00 285 0.00 0.00 335 0.00 0.00 286 0.00 0.00 336 0.00 0.00 287 0.00 0.00 337 0.00 0.00 288 0.00 0.00 338 0.00 0.00 289 0.00 0.00 339 0.00 0.00 290 0.00 0.00 340 0.00 0.00 291 0.00 0.00 341 0.00 0.00 292 0.00 0,00 342 0.00 0.00 293 0.00 0.00 343 0.00 0.00 294 0.00 0.00 344 0.00 0.00 295 0.00 0.00 345 0.00 0.00 2% 0.00 0.00 346 0.00 0.00 297 0.00 0.00 347 0.00 0.00 298 0.00 0.00 348 0.00 0.00 299 0.00 0.00 349 0.00 0.00 300 0.00 0.00 350 0.00 0.00

22.7 1.594 0 0.000

Sum(n) Sum(n-NY Sum(n) Swn(n-NY

Page4 of4

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01/27/99

120

~ 100 z -0 80 <{ w c:: LL 60 0 c:: w 40 cc ~ :::, 20 z

0 8

PHASE Ill -AREA 91Q" WASTE POND# 1-AFFECTED LUDLUM 19 MICRO-R METER READINGS AT SURFACE SITE BACKGROUND OF 9 JJR/hr NOT SUBTRACTED

RES UL TS IN µR/hr DECEMB~R, 1998

MICRO "R" READINGS @ SURFACE

FREQUENCY DISTRIBUTION

9 10 11 µR/hr

NUMBER OF READINGS AVERAGE READING MINIMUM READING MAXIMUM READING STANDARD DEVIATION

272 10

8 13

0.9

12


13

Documents

Cimarron Corp Final Status Survey Plan for Sub-Area 'O ... · letter transmits the Final Status Survey Report£ r Sub-Area "O" Surface. Please find enclosed three (3) copies of the