ML20134B295
| ML20134B295 | |
| Person / Time | |
|---|---|
| Site: | 07003073 |
| Issue date: | 01/07/1997 |
| From: | Jim Hickey NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20134B291 | List: |
| References | |
| NUDOCS 9701300022 | |
| Download: ML20134B295 (5) | |
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- U.S,. NUCLEAR REGULATORY COMMISSION
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- l WI lj Pariu. int to the Atomic ! nergy Act of 1954, as an ended, the Energy Reorganitation Act of 1974 (Public Law 93-43x). and Title 10. Code of gl lh IeJeralI cgulations Chapter L Parts 20. 31. 32. 33. 34. 35, 4. 39. 40 anJ 70, and in reliance on statements and representations heretofore made {
[I by the licen ce. a license n hereby inued authorving the licensee to recene acquire. posseu and transfer byproduct. source, and special nutlear {l C material designated below. to use suth material ior the purpose (s) and at the placch) designated below; to deliser or transfer such material to O 4
[ persons authoried to recene it m auordant e with the regulations of the applicable Parth). This license shall be deemed to contain the conditions *l "l
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l specified in Section Nuclear Regi latory Commnsion lxnow3orof theterAtomic hereaf in ellect andLocrgy Att of to any conditions 1954,
.pecified below. as amended. nd is subject to all l$ $l l5
- l 3 Licensee ! jl wi M
cl Kerr-McGee Corporation SNM-1999 C' fj l. 3. License Number "l 9,i 3
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~i Kerr-McGee Center D f
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Oklahoma City. OK /3125 4. Expiration Daic J nuary 1. 1997 i
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4 5. Docket or 70-3073 gl l !
Reference No. Ameridgent_he. 5 gj l h 6. liypnsluct. Source, and or 7. Chemical anWor Physical 8. Maximum Amount that Licensee 9l 4 jC Special Nuclear Material Fonn May Possess at Any One Time gl 1 Under This License gi
{l D p i lg A. Uranium Enriched A. Contaminated soil. A. All residual contam- lEl ,
ia in U-235 sludge. sediment. ination which 5 l l
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trash, building rubble, structures and any currently exists at the former Cushing (gj '
other contaminated Refinery Site. 9 l l material. g '
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l gl l B. Thorium B. Contaminated soil. B. All residual contam- pi l ll sludge, sediment. ination which 5 i j trash, building rubble. currently exists at the former Cushing jl
@ structures. and any g; l
other contaminated Refinery Site. c l
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ci l C. Natural Uranium and C. Contaminated soil. C. All residual contam- i"l hj Depleted Uranium sludge, sediment, ination which s
i trash, building rubble. currently exists at gll c structures and any the former Cushing other contaminated Refinery Site. }l sj cl 3 material. l 9 ;h"
% D. U-235 D. Calibration and D. No calibration or j"l 3 reference radioactive sources containing referenceradioactivegll source containing 33 g U-235 U-235. shall exceed cl
% 0.1 microcurie per "
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% 9. Authorized Use: Licensed material shall be possessed and used in remediation $
activities leading to the decommissioning of the Cushing Site.
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h 10. Authorized Place of Use: The existing facilities of Kerr-McGee Corporation. $
' Environmental Operations. Technology and Engineering Division. P.O. Box 89. Cushing. "g *;
k; OK 74023. Location: Two miles North - State Highway 18. 1/2 mile East - Deep Rock
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NR fpRM 374A U.S. NUCLEAR REGULATORY COMMISSION PAGE
{ OF ] PAGES l Lnctne Number SNM-1999 i
-y f MATERI ALS LICENSE tu Lei or Reierence Number SUPPLEMENTARY SHEET g'
3 70-3073 gl 3j Amendment No. 5 $g l h b af $m ji 11. Conditions: 9l g 9l 3 A. Kerr-McGee shall submit by license amendment request. before May 1. 1994. a El 3 Proposed Decommissioning Plan for the Cushing Site meeting the requirements offl 3 10 CFR 70.38(c)(2)(iii). ;
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! ll Kerr-McGeeshallsubmit,byseparatelicenseamendmentrequests,orasapart%l g
3 oftheProposedDecommissioningPlar.,detaileddescriptionsoft performing the following activities, prior to beginning the activities: g 4 O g 1. Prior to transferring contaminated material to any of the three 1 sl y temporary storage areas provide an analysis of the ability of the three 3 temporary storage areas to effectively resist erosion by wind and water. l{l el y anddescribethemeasurementprocedurestobeusedtocontrolthesortinghl g of the contar.;nated material to be transferred to the temporary storage @
g areas.
3 5 y 2. Prior to neutralizing the acidic contaminated sludge in Pit 4. describe Ql y the methods to be used. q g A g
- 3. Prior to demolishing potentially contaminated structures, provide a description of the methods to be used. gll
!g I i 3 C. Both the 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and 2 to 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> Health and Safety indoctrinations described ini !
!5 Item 8 of the application shall include all of the topics described in 10 CFR I l 19.12.
Ql fs D. Deleted.
y 3 E. Notwithstanding statements in the application, the limits listed in 3 ll 3
" Guidelines for Decontamination of Facilities and Equipment Prior to Release gl for Unrestricted Use or Termination of Licenses for Byproduct. Source, or c!
3 Special Nuclear Material." Policy and Guidance Directive 83-23. August 1987. {l 3 slall be used as the criteria for the unrestricted release of equipment. ! l
% material, and personnel. l l E i N F. All radiation protection program procedures shall, at a minimum, be approved $l 3 by the Radiation Safety Officer and either the Vice President. Environmental $l 3l Operations, or the Vice President. Environmental & Health Management. $l
%j G. All work in radioactive materials areas or restricted areas. or work with h
%s i licensed material not located in radioactive materials or restricted areas. hll c
% shall be in accordance with an approved radiation safety procedure. Work may 5l
% be performed in the haul road corridor area.* except in fenced radioactive Fl
, materials areas located within the haul road corridor area. without $l l j implementing a radiation safety procedure.
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- 0 g The haul road corridor area is considered to be defined as the aggregate of 9l g the 33 survey units addressed in Kerr-McGee's letter to the NRC dated May 30. 1996.. L" _ ON'O 2l
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FORM 874A U.S. NUCLEAR REGULAVORY COMMISSION
, PAGE 3 or 3 r^ots Lnense Number jll j
l SNM-1999 9l Wl 3
3 MATERI AI S I.ICENSE SUPPLEMENTARY SHEET auen,r Reference Number 70-3073 Ll ll 3'! Cl d
Amendment No. 5 !!!'
H. Wastes disposed offsite shall be classified and meet waste form requirements l
EI of10CFRPart61.meetapplicabledisposalsitelicenseconditions.andmeetE ls Department of Transportation and 10 CFR Part 71 transportation requirements. g ll l I. The Radiation Safety Officer for this license is Mr. Terence Moore. f5l I
l l J. Licensee is exempt from the physical protection requirements of 10 CFR Part 73 and the criticality accident requirements of 10 CFR 70.24.
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K. Except as specifically provided otherwise in this license, the licensee s'n all !sl 3 conduct its program in accordance with statements, representations. and Cl 3 conditions contained in letter dated September 25. 1992. as supplemented on I$l 3 December 18. 1992. January 14. 1993. February 23. 1993. August 26. 1993 and 9l 3 January 5. 1994 3
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E ul 3 FOR THE U.S. NUCLEAR REGULATURY COMMISSION 2l 3 El 3 ?
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Date: January 7,1997 By. -
Cl a J in W.N. H1ckey. ChieT \ !!l jl cw-Level Waste and Decommissioning) 12l 3 Projects Branch Ql 3
Division of Waste Management 9l 3 Office of Nuclear Material Safety 9l 3 and Safeguards jl 3 sl u! 9l j! 9l a! 9l E! 9l i! l2l
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4 3 3 SNM-1999 70-3073 Amendment No. 5 H. Wastes disposed offsite shall be classified and meet waste form requirements of 10 CFR Part 61 meet applicable disposci site license conditions, and meet Department of Transportation and 10 CFR Part 71 transportation requirements.
I. The Radiation Safety Officer for this license is Mr. Terence Moore.
J. Licensee is exempt from the physical protection requirements of 10 CFR Part 73 and the criticality accident requirements of 10 CFR 70.24. .
K. Except as specifically provided otherwise in this license, the licensee shall conduct its program in accordance with statements, representations, and conditions contained in letter dated Se)tember 25, 1992, as supplemented on December 18. 1992. January 14. 1993. Fe]ruary 23, 1993. August 26, 1993, and January 5, 1994.
FOR THE NUCLEAR REGULATORY COMMISSION
[ Original signed by] ,
Date: January 7,1997 By: [0riginal signed by]-
John W.N. Hickey. Chief Low-Level Waste and Decommissioning' Projects Branch Division of Waste Management Office of' Nu' clear Material Safety and Safeguards l'
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DISTRIBUTION: Central File #70-3073 NMSS r/f LLDP r/f JGreeves MFederline LCarson/RIV BSaitzberg/RIV RNelson ~
Mark Small ~ 30xes'in Concurrente!BlockLto' Define' Distribution Copy' Preference.
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In 'small Box 6n "0FCi"'~lirie' enteri C~ = Cover E = Cover & ~ Enclosure N = No' Copy 0FC LLDP LLDPEL LLDPi OGC%/ LLDL [ '
NAME SBro [ [ JCopNand TCMkn RFbn' neb Jdkey l DATE /2 ///I I& P/96 4/ '8V96 //1/93 / / 7/93 i Path & File Name:S:\dwm\lldp\swb\cush ilc.a5 0FFICIAL RECORD COPY l In small Box on "DATE:" line enter: M = E Mail Distribution Copy H = Hard Copy
! PDR YES X NO Category: Proprietary or CF Only ACNW: YES NO X Delete file after distribution Yes ___ No X IG: YES NO X l
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i ENCLOSURE 2
pn MQu y- *a UNITED STATES j
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's NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20555 4001
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS RELATED TO AMENDMENT NO. 5 TO MATERIALS LICENSE NO. SNM-1999 KERR-McGEE CORPORATION CUSHING REFINERY SITE DOCKET NO. 70-3073
1.0 INTRODUCTION
Kerr-McGee Corporation (the licensee) in its letter dated February 16, 1996.
identified a need to construct an all weather haul road on its Cushing
' Refinery site. Under the terms of license condition 11.G. the licensee would be required to im)lement a radiation safety procedure while work is being performed in the laul road corridor area.
2.0 BACKGROUND
On April 6.1993. U.S. Nuclear Regulatory Commission (NRC) issued Materials License SNM-1999 authorizing Jossession of contaminated soil, sludge.
sediment, trash, building rub)le, and any other contaminated material, at the ;
licensee's Cushing site. Condition 11.G of Materials License SNM-1999. states
~
that "[A]ll work in materials areas or restricted areas, or work with licensed ;
material not located in radioactive materials or restricted areas. shall be in accordance with an approved radiation safety procedure." However. License i Condition 11.6 does not include a radiation limit below which the licensee would not have to implement a radiation safety procedure while either working in materials areas or restricted areas, or working with licensed material.
Thus, the licensee in its February 16, 1996. letter proposed establishing a radiation limit below which a radiation safety procedure would not have to t implemented while working in the haul road corridor area.
3.0 EVALUATION The licensee in its letter dated February 16. 1996, proposed establishing a radiation limit below which a radiation safety procedure would not have to be implemented while either working in a materials areas or restricted areas, or working with licensed material. The licensee by letter dated May 30. 1996, submitted the " Final Radiation Survey of Haul Road Corridor" (Final Survey Peport) to support its proposal. In addition, the licensee requested that NRC release the haul road corridor area for unrestricted use. The licensee's request for release of this area for unrestricted release is still under review. The Final Survey Report provided data that indicated that the haul l road corridor area meets NRC criteria for unrestricted release. The licensee supplemented the Final Survey Report by letter dated August 30. 1996.
9701220236 970107 PDR ADOCK 07003073 C PDR ,
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In that letter, the licensee addressed NRC's concerns related to potential !
subsurface contamination in the haul road corridor area. Subsurface '
contamination could result from either migration of contaminated material from i the surface or buried contaminated material. The licensee's effort to ,
determine if migration of contaminated material had occurred in this area was l to collect soil samples from the three M 3tions of highest concentration of I licensed material on the surface. The samples were taken from depths of 15 centimeters to one meter. The licensee noted that all of the soil samples yielded results indicating only background concentrations of uranium, thorium.
and radium. The licensee in its letter dated November 25, 1996. submitted the results of this subsurface sampling effort. With respect to buried contaminated material, the licensee stated that there is only one location in this haul road corridor area where contaminated material is buried. This on-site burial will be assessed during NRC's evaluation of the licensee's request-to have the haul road corridor area released from its license..
At the request of NRC. its contractor, the Oak Ridge Institute for Science and Education (0 RISE). performed a confirmatory survey of the haul road corridor during the period of August 26 through 29. 1996. The results of that ORISE confirmatory survey were provided to NRC in the " Confirmatory Survey of the Haul Road Corridor at the Oklahoma Refinery site." dated December 1996. ORISE performd scan surveys of between 50 to 100 percent of the surface area of each selected survey unit. In addition. ORISE collected over 60 surface soil samples and three subsurface soil samples. The soil samples yielded results indicating only background or slightly above background concentrations of uranium arid thorium. These results of the subsurface samples provided no definitive indication of subsurface contamination due to surface migration.
There were nine samples that yielded results indicating elevated levels of radium. The elevated levels of radium ranged from 1.1 to 73.7 picocuries per gram. ORISE noted that these levels have been )reviously documented as being l the result of past oil refinery operations whic1 tended to concentrate radium i
within pipe scale. Radium is considered a naturally occurring radioactive material, and thus, regulated by states rather than NRC. ORISE's results support the licensee's position that the haul road corridor area meets NRC's unrestricted use criteria.
Therefore. NRC finds that activities may be conducted in the haul road corridor area without the implementation of a radiation safety procedure based on the licensee's Final Survey Report and ORISE's draft confirmatory survey 1 results. This NRC finding does not include the several radioactive materials i l areas located within the haul road corridor area. l.
I 4.0 STATE CONSUL T ION The Oklahoma State official was notified of the proposed issuance of the l amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
l The amendment deletes an administrative requirement to implement a radiation safety procedure while either working in materials areas or restricted areas.
1 or working with licensed material. Accordingly, the amendment meets the l
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criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10). Pursuant ,
to 10 CFR 51.22(b). no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
6.0 CONCLUSION
NRC has concluded, based on the considerations discussed above, that issuance-of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: S. Brown ,
t Date: January 7, 1997
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ENCLOSURE 3 i
CONFIRMATORY SURVEY OF THE HAUL ROAD CORRIDOR AT '
THE OKLAHOMA REFINERY SITE KERR-McGEE CORPORKfION CUSHING, OKLAHOw1A
[ DOCKET NO. 70-3073]
D. R. QUAYLE AND T. J. VITKUS Prepared for the Division of Waste Management U.S. Nuclear Regulatory Commission ,.-
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f The Oak Ridge lastitute fer Science and Education (ORISE) was established by the U.S. Department of Energy to undertake national and international programs in science and engineering education, training and management systenu, energy and environment systems, and medical sciences. ORISE and its programs are operated by Oak Ridge Associated Nyersities (ORAU) through a management and operating contract with the U.S. Department of Energy. Established
.a 1946, ORAU is a consortium of 89 colleges and universities.
NOTICES The opunons expressed herein do not necessarily reflect the opuuons of the sponsoring institutions of Oak Ridge Associated Universities.
'Ihis report was prepared as an account of work sponsored by the United States Government Neither the United States Govern ==* nor the U.S. Department of Energy, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsioility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use wouki not infringe on privately owned rights.
Reference herein to any specific commercial product, process, or service by trade name, mark, manufacturer, or otherwme, does not -rdy constitute or imply its endorsement or recommendation, or favor by the U.S. Government or any agency thereof. 'Ibe views and opinions of authors expressed herein do not necessarily state or reflect those of the U.S. Government or any agency thereof.
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CONFilOIATORY SURVEY OF TIIE IIAUL ROAD CORRIDOR AT TIIE OKLAIIOMA REFINERY SITE
- KERR-McGEE CORPORATION
- CUSIIING, OKLAIIOMA 1
4
^ 6 Prepared by: Date:
- D. R. Quayle, Assistant Profe'ct Leader i
Environmental Survey and Site Assessment Program Prepared by: Date: b T. J. VitlMs / Survey Projects Manager Environmental Survey and Site Assessment Program Reviewed by: . o Date: /2////96 I R. D. Condra, Technical Resources Manager Environmental Survey and Site Assessment Program Reviewed by: N ) M Date: /d / iia lT/e A. T."Payne, Administratile Services Manager, Quality Assurance / Health & Safety Manager Environmental Survey and Site Assessment Program Reviewed by: - - Date:
E.W. Abelquist, Assistant /rogram Director Environmental Survey and Site Assessment Program Reviewed by: /# Date: /2//7/f4 ,
W. L. Beck, Program Director Environmental Survey and Site Assessment Program KerratcGee Corporahon (631) De: ember 12.1996 h Wsap\reportstushmgwushmg 032
ACKNOWLEDGM ENTS The authors would like to acknowledge the significant contributions of the following staff members:
FIELD STAFF l
J. S. Cox LABORATORY STAFF R. D. Condra M. J. Laudeman S. T. Shipley CLERICAL STAFF D. K. Ash T. S. Fox K. E. Waters ILLUSTIL\ TOR T. D. Herrera l
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Ken-McGee Carpwanon (651) . December 12.1716 h 'essapve;xwts'cushmg .cushmg o02
CONFIRMATORY SURVEY OF TIIE IIAUL ROAD CORRIDOR AT TIIE OKLAIIOMA REFINERY SITE KERR-McGEE CORPORATION CUSIIING, OKLAllOMA Prepared by D. R. Quayle and T. J. Vitkus Environmental Survey and Site Assessment Program Environmental and Health Sciences Division Oak Ridge Institute for Science and Education Oak Ridge, Tennessee 37831-0117 l
l l
Prepared for i
Division of Waste Management '
U.S. Nuclear Regulatory Commission FINAL REPORT DECEMBER 1996 This report is based on work performed under an Interagency Agreement (NRC Fin. No. A-9076) between the U.S. Nuclear Regulatory Commission and the U.S. Department of Energy. Oak Ridge Institute for Science and Education performs complementary work under contract number DE-AC-05-760R00033 with the U.S. Department of Energy.
Ken McGee Corporanon(653) December 12. 1996 h vssapveports'cushmgwushmg 002
- . _ .. _ _ _ . . = -
TABLE OF CONTENT S PAGE List of Figures ii List of Tables . iii i
Abbreviations and Acronyms iv Introduction and Site History . 1 Site Description .3 Objectives 3 Document Review 3 Procedures 3 Findings and Results 5 Comparison of Results with Guidelines .6 4
Summary .7 a
References . 26 Appendices:
Appendix A: Major Instrumentation Appendix B: Survey and Analytical Procedures Appendix C: Guidelines for Residual Concentrations of Thorium and Uranium Wastes in Soil Ken.kicGee Corindmn (65.1) . December 12.17#, h 'essapveportss cushing cushing (02
LIST OF FIGURES PAGE FIGURE 1: Location of the Kerr-McGee Corporation Site, Cushing, Oklahoma 8 FIGURE 2: Haul Road Corridor, Kerr McGee Corporation-Survey Unit Locations and Areas Surveyed . 9 FIGURE 3: Survey Unit 34A-Measurement and Sampling Locations 10 FIGURE 4: Survey Unit 56A-Measurement and Sampling Locations !I FIGURE 5: Survey Unit 68A-Measurement and Sampling Locations 12 FIGURE 6: Survey Unit 79A-Measurement and Sampling Locations 13 FIGURE 7: Survey Unit 54A-Measurement and Sarnpling Locations 14 FIGURE 8: Survey Unit 32A-Measurement and Sampling Locations 15 FIGURE 9: Survey Unit 52A-Measurement and Sampling Locations 16 FIGURE 10: Survey Unit 40A-Measurement and Sampling Locations 17 FIGURE 11: Survey Unit 108A-Measurement and Sampling Locations 18 FIGURE 12: Survey Unit 201 A, Part A-Measurement and Sampling Locations 19 FIGURE 13: Survey Unit 201 A, Pan B-Measurement and Sampling Locations 20 l
Kerr McGee Corporaoon (651) . [hember 12.1996 II hs essapveprwisscushmg' cushing r.02 l
LIST OF TABLES PAGE TABLE 1: Exposure Rates and Radionuclide Concentrations in Soil Samples 21 i
i i
Ken-McGee Corp <waison(653) December 12 l'/M $5k h Wsapweportsuhmg<ushmg 002 l
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ABBREVIATIONS AND ACRONYMS pR/h microroentgens per hour prem/h microrem per hour AEC Atomic Energy C mmission ASMC American Society of Mechanical Engineers BKG background cm centimeter cm 2 square centimeter cpm counts per minute BTP Branch Technical Position EML Environmental Measurements Laboratory EPA Environmental Protection Agency ESSAP Environmental Survey and Site Assessment Program kg kilogram KMC Kerr-McGee Corporation m .neter m2 square meter m' cubic meter MDC minimum detectable concentration MeV mega electron volts Nal sodium iodide NIST National Institute of Science and Technology NRC Nuclear Regulatory Commission ORAU Oak Ridge Associated Universities ORISE Oak Ridge Institute for Science and Education pCi/g picocuries per gram RMA radioactive materials area UA unaffected area UF, uranium tetrafluoride UF, uranium hexafluoride Ken 4fcGee Corporauon (653) . December i2,1996 kV hsessapeeports'cushmg'cushms 002
CONFIRMATORY SURVEY OF TIIE IIAUL ROAD CORRIDOR AT TIIE l 4
OKLAllOMA REFINERY SITE !
KERR-McGEE CORPORATION CUSIIING, OKLAIIOMA l INTRODUCTION AND SITE IIISTORY j The Cushing Refinery Site is located two miles north of the City of Cushing in Payne County,
, Oklahoma and was operated from 1915 to 1972. Kerr-McGee Corporation (KMC) purchased the ;
{ Cushing site from General American Oil Company of Texas in 1956 and operated an oil refine y there
- from 1956 to 1972. From 1962 to 1966, KMC used part of the Cushing refinery site to process natural thorium and natural, depleted, and enriched uranium under two Atomic Energy Commission l
(AEC) licenses, SMB-664 and SNM-695.
AEC license SMB-664 was issued to KMC on November 7,1962 and authorized unlimited quantities
! ofuranium and thorium in a variety of chemical forms. The bulk of uranium material received was UF,(uranium hexafluoride). Typical products were oxides, carbides, fluorides, nitrates, metal, etc.
4 Thoriurn material was received in the form of concentrates. Typical products were oxides or carbides j or combinations of uranium and thorium compounds at various ratios of thorium to uranium.
]
, AEC license SNM-695 was issued to KMC on April 23,1963 and authorized possession of any enriched uranium in any form, except metal, including scrap recovery, not to exceed 1000 kilograms
- (kg) ofuranium-235. The uranium was received in the form of UF, and other chemical compounds 4
and was converted to other compounds ofuranium suitable for nuclear fuels. AEC license SNM-695 was amended to permit reduction of high enriched UF,(uranium tetraflouride) to uranium metal t buttons.
Enriched uranium was processed at Cushing from early 1963 until September 1965 and thorium
- processing was performed from December 1964 until February 1966. In April 1966, KMC reported to the AEC that as of April 26,1966, all special nuclear material had been transferred from the j Cushing site to KMC's new Cimarron facility in Crescent, Oklahoma and that all Cushing buildings J in which licensed activities had been performed were cleaned and decontaminated. The AEC conducted a close-out survey of the Cushing facility on July 6,1966. On the basis of this survey, and in response to KMC's request for authorization to release the facility for unrestricted use, licenses SMB-664 and SNM-695 were terminated on July 25,1966.
3 Km-McGee Corporahan (65)} . December 1119M h VuapVeportskushmstushmg 002
During cleanup activities, some radioactively contaminated materials were placed in burial trenches, old petroleum storage tank dike areas, and part of a hydrocarbon waste impoundment (Pit 4) on the site Materials placed in trenches and the waste impoundment were covered with native soil. An October 1989 radiological survey conducted by Oak Ridge Associated Universities (ORAU) l confirmed the presence of general low-level radioactive material in the northeast corner of the site l around and in Pit 4.
The remediation and restoration of the former refinery site by KMC has identified localized areas of contamination from former processing and waste management activities. About 5600 cubic meters (m') ofsoil and other materials contaminated with licensed uranium or thorium in excess of the limits specified in Nuclear Regulatory Commission (NRC) Branch Technical Position (BTP) Option 2 or 4 are estimated to remain on site. About 1375 m' of material at Option I concentrations is buried on-site in trenches. On April 6,1993, the NRC issued license SNM-1999 to KMC for decommissioning the site for release for unrestricted use.
KMC is scheduled to begin acid sludge remediation at the site and intends to construct haul roads for transporting treated sludge to on-site disposal cells. The roads will run through portions of the site that were used for petroleum refming during the years that nuclear material processing was performed. Most of the roads will be within the north tank farm which was used for crude oil and refined oil storage. Thorium-contaminated wastewater was dumped in various tank dikes and also sprayed in the northeast corner of the tank farm. KMC has petitioned the NRC for release for unrestricted use of the corridor where the haul roads will be constructed in order to permit construction activities without the requirements for radiation safety training and monitoring. In support of this petition, KMC performed a radiological survey of the haul road corridor land areas and provided the results in a final status survey report (KMC 1996). The results of that survey indicated that the NRC's guidelines for residual concentrations of uranium and thorium in soil were satisfied, with the exception of two areas that will be maintained as radioactive materials areas (RMA). Portions of the roads also will be established in areas unaffected by radioactive material use that KMC previously surveyed. The Oak Ridge Institute for Science and Education (ORISE) performed a confirmatory survey of those areas in September 1995 (ORISE 1996a). At the request of the NRC's Division of Waste Management, the Environmental Survey and Site Assessment Program (ESSAP) of ORISE performed a confirmatory survey of the affected portions of the haul road corridor. This report describes the procedures and results of this survey.
KerrafeGee Corporahon (633) Decernber 12, M6 2 h euapweporu'asshmg'cushmg 002
]
- SITE DESCRIPTION j -
i i
j The KMC Cushing site is located in Payne County, Oklahoma, two miles north of the City of Cushing 1
! (Figure 1). Cushing lies about midway between Tulsa and Oklahoma City. The terrain of the region j is rolling, oil-producing pasture land. Several oil fields were developed in the imrrediate area. The i
- ' elevation of the refinery site ranges from 250 to 280 meters above sea level. The entire Cushing site ,
encompasses approximately 178 hectares. The haul road corridor is located in the north-central i
- portion of the plant. KMC has sivided the corridor into 33 survey units, with each survey unit containing approximately 10,000 square meters (1 hectare) ofland area (Figure 2).
j OBJECTIVES The objectives of the confirmatory survey were to provide independent document reviews and
- radiological data for use by the NRC in evaluating the adequacy and accuracy of the licensee's fmal I j status survey report relative to established NRC guidelines.
l
- i l
DOCUMENT REVIEW ;
1 l
}
.1 1
ESSAP reviewed the licensee's documentation associated with the final status survey of the haul road corridors and analytical procedures and methods used by the licensee were reviewed for adequacy j and appropriateness. The data were reviewed for accuracy, completeness, and compliance with j applicable NRC guidelines.
i PROCEDURES l ESSAP performed a confirmatory survey of the proposed haul road corridors at the Cushing Refinery i Site during the period August 26 through August 29,1996. The survey was in accordance with a
- site-specific survey plan dated August 15,1996 which was submitted to and approved by NRC and in accordance with the ORISE/ESSAP Survey Procedures and Quality Assurance Manuals (ORISE 1996b,1995a and b). A total of ten survey units were selected, investigating eight that were l adjoining established RMA's and two that were randomly selected (Figure 2).
f Ken.McGee Corporsuon (6531. December 11 iM 3 m w pveport.wu.sm wu.sm 00:
1
i REFERENCE GRID 1
ESSAP used the existing 100 meter 100 meter survey unit established by KMC for survey data reference.
.1 SURFACE SCANS Surface scans for gamma activity were performed over approximately 50 to 100 percent of each selected survey unit using Nal scintillation detectors coupled to portable ratemeters and ratemeter-scalers with audible indicators. Areas of elevated direct radiation identified by scans were marked for further investigation.
EXPOSURE RATE MEASUREMENTS Exposure rate measurements were performed at a minimum of five systematic locations within each survey unit and at locations of elevated direct gamma radiation detected by surface scans. Exposure rates were measured at 1 meter above the surface using a microrem meter. Measurement locations are shown in Figures 3 through 13. Background exposure rate measurements were obtained during a previous survey at the Cushing Refinery Site (ORISE 1996a). j SOIL SAMPLING The analytical results of background soil samples, collected during a previous ORISE survey at the Cushing Refinery Site were used for comparison (ORISE 1996a). A total of sixty-three surface soil samples were collected from the selected survey units, in which six were composite samples and three were borehole samples. Sampling locations are shown in Figures 3 through 13.
Kerr-McGee Corporation (653 ) . December 12.1996 4 h 'essapveporticushmg'cushmg 002
SAMPLE
- ANALYSIS AND DATA INTERPRETATION Samples and survey data were returned to the ORISE/ESSAP laboratory in Oak Ridge, TN for analyses and interpretation Sample analysis was in accordance with the ORISE/ESSAP Laborator Procedures Manual (ORISE 1995c). Soil samples were analyzed by solid-state gamma spectromet and the spectra were reviewed for radionuclides ofinterest; U-235, U-238, Th-232, Th-228 and any other identifiable photopeaks. Soil samples results were reported in units of picoeuries per gram (pCi/g). Exposure rate measurements were reported in microroentgens per hour (pR/h). Results were compared with the licensee's documentation and NRC guidelines for release for unrestricted use. Additional information concerning major instrumentation, sampling equipment, and analytical procedures are provided in Appendices A and B.
FINDINGS AND RESULTS SURFACE SCANS Surface scans for gamma activity within the haul road corridor identified seven locations of elevated I
l direct gamma radiation in survey unit 40A, one location ofelevated direct gamma radiation in survey '
unit 32A, and one location of elevated direct gamma radiation in survey unit 54A. Surface scans for gamma activity within the remaining surveyed areas did not identify any locations of elevated direct radiation.
4 EXPOSURE RATES Exposure rates at 1 meter above the surface ranged from 9 to 15 pR/h (Table 1). Background exposure rates ranged from 4 to S pR/h (ORISE 1996a).
Kerr4fcGee Corporatum (653) . December 12. t u 5 w wop ,eror1.wussm,'cussm,00:
RADIONUCLlDE CONCENTRATIONS IN SOIL SAMPLES 1
1 Radionuclide concentrations in background soil samples were less than 0.1 pCi/g for U-235,1.0 to 1.6 pCi/g for U-238,0.5 to 1.0 pCi/g for Th-228,0.6 to 0.9 pCi/g for Th-232, and 0.6 to 0.9 pCi/g for Ra-226 (ORISE 1996a)
Concentratinns of radionuclides in confirmatory soil samples from the selected haul road corridor survey units are summarized in Table 1. Concentration ranges were as follows: U-235, less than 0.8 l pCi/g; U-238, less than 2.9 pCi/g; Th-228, 0.5 to 2.9 pCi/g; Th-232, less than 0.4 to 2.8 pCi/g.
Elevated levels ofRa-226, ranging from 1.1 to 73.7 pCi/g, were detected in nine soil samples which corresponded to the locations of elevated direct radiation previously discussed. These levels have been previously documented as being the result of past oil refmery operations which tend to concentrate Ra-226 within pipe scale (ORISE 1996a). Ra-226 concentrations in all remaining soil samples ranged from 0.5 to 1.0 pCi/g.
1 COMPARISON OF RESULTS WITH GUIDELINES The primary contaminants of concern for this site are enriched uranium and natural thorium. The generic guidelines for residual concentrations of uranium in soil are provided in the NRC Branch Technical Position on " Disposal or Onsite Storage of Thorium and Uranium Wastes from Past Operations"(NRC 1981). Specifically, the Option 1 average soil guidelines for enriched uranium and thorium are 30 pCi/g and 10 pCi/g, respectively.
Soil samples collected from the haul road corridors were generally consistent witti natural background levels ofuranium and thorium and therefore all soil samples were within the Option I soil guideline for enriched uranium and natural thorium.
l i
The exposure rate guideline, measured at 1 m from the surface, is 10 pR/h above background (NRC 1981). Exposure rates measured in the haul road corridors were all within this guideline.
i I
Ken 4AcGee Corporation (651) . December 12, im b h usapVeport:1cushmg <cushmg (U3 i
SUMMARY
ESSAP performed confirmatory swvey activities of the haul road corridors located at the Kerr-McGee Cushing Refmery Site in Cushing, Oklahoma during the period of August 26 through 29,1996. Survey activities included surface scans, exposure rate measurements, and soil sampling.
The ESSAP confirmatory measurements support the licensee's conclusion that residual radioactivity within the specified haul road corridors at the Cushing Refinery Site satisfies NRC guidelines for release for unrestricted use.
I i
I l
i Kerr-McGee Corporanon (643) . December 12. IW 7 h iessapveportsicushing'<ushing uG2
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Survey Unit 79A - Measurement and Sampling Locations KenMGee Coqxwaiio.1(653) December 12.19%
h unapveportsbashmg<ushmg 002
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EXPOSURE RATES FEET 0 60 0 20 I METERS FIGURE 12: Survey Unit 201 A, Port A - Measurement and Sampling Locations Ken-McGee Corporation (653) December 12. Im 19 h wsup'reportshhmstushmg 002
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METERS FIGURE 13: Survey Unit 201 A, Part B - Measurement and Sampling Locations Kerv4tcGee Corporation (653) . December 12,1M 20 $w gvepo,1,wo,6,n, s.n 00:
N r
TABLE 1
{ . .
I EXPOSURE RATES AND RADIONUCLIDE CONCENTRATIONS IN SOIL SAMPLES
{ :-
OKLAIIOMA REFINERV SITE _
8 KERR-McGEE CORPORATION i CUSIIING, OKLAllOMA F
E ~-
I ESSAP Sample Exposure Rates Radionuclide Concentration (pCi/g)
Sun'ey Unit.
fs ID (pR/h) U-238 U-235 Ra-226 Th-232 Th-228 1 34A 9 0.8 i 0.6 6 0.2 + 0.2 0.8 0.I 1.I i 0.2 1.2
- 1.I 2 34A 10 0.7 0.4 <0.1 0.6 i 0.1 0.8
- 0.1 0.7 t 0.1 3 34A 12 1.4 06 0.1 0.1 1.0 0.1 1.1 1 0.2 1.1 i 0.1 3
, 4 34A 10 1.3 i 0.6 <0.2 1.0 0.1 1.l
- 0.2 1.1 0.1 5 34A 11 1.2 i 0.5 <0. 2 0.8
- 0.I 1.0 0.2 1.1 0.!
6 56A 10 0.8 0.6 <0.2 0.9
- 0.1 0.9 i 0.2 0.9 i 0.I 7 56A 10 0.9 t 0.7 <0.2 0.7 0.1 1.0 0.2 0.9 0.1 8 56A 10 0.8 0.7 <0.2 0.7 0.1 0.9 0.2 0.9 1 0.1 9 56A 11 1.2
- 0.7 <0.2 0.8 0.I 1.0
- 0.2 0.9 0.I 10 56A 13 1.1
- 0.6 <0. 2 0.8
- 0.1 1.0 0.2 1.0
- 0.1
,, 11 68A 9 1.1
- 0.5 <0. 2 0.7
- 0.1 0.9 0.1 x 1.0 0.1 f4 12 68A 10 1.1 0.6 <0.2 0.7
- 0.I 1.0 0.2 1.0
- 0.1 j 13 68A i1 0.8 0.6 <0.2 0.8 + 0.1 0.9
- 0.2 1.0
- 0.I a 68A 0.8 i 0.6 14 11 <0.2 0.7 0.1 0.9 0.2 1.0 0.1 15 68A 10 0.7
- 0.5 <0. 2 0.8 0.I 1.0
- 0.2 1.I + 0.1
L
~
r c TAllLE I (Continued) - -
?
r E
EXPOSURE RATES AND RADIONUCLIDE CONCFNTRATIONS IN SOIL SAMPLES . -i
{ OKLAIIOMA REFINERY SITE
$g KERR-McGEE CORPORATION CUSilING, OKLAllOM A t
7 t
ESSAP Sample Exposure Rates Radionuclide Concentration (pCi/g)
Survey Unit. ,
$ [i 16 79A 11 0.6 0.5 <0.2 0.9 + 0.1 1.0 + 0.2 1.1 i 0.1 17 79A 11 1.7 0.6 <0.2 0.8 i 0.1 0.9 i 0.2 1.0 i 0.I l8 79A 10 1.1
- 0.7 <0.2 0.8 i 0.1 0.8 + 0.2 1.0
- 0.I 19 79A i1 1.0 0.5 <0. 2 1.0
- 0.1 1.0 0.2 1.1 0.I O
20 79A I2 2.0 0.8 <0.2 0.9 i 0.I 1.0 1 0.2 1.0
- 0.I 21 54A 9 0.9
- 0.6 <0.2 0.9 0.I 1.0 0.2 1.0 t O.I 22 54A 14 1.4 0.6 <0.2 1.0 0.I 1.0 + 0.2 1.0-+ 0.1 23 54A 13 <2.9 <0. 8 73.7 0.7 1.6
- 0.7 1.1
- 0.2 I 24 54A 11 1.4
- 0.6 <0. 3 0.9
- 0.I 1.1
- 0.2 1.1 i O.I 25 54A 9 1.0 + 0.5 <0.2 0.9 i 0.I 1.1 0.2 1.0
- 0.1 l z
j s
26* 54A ---d 1.4
- 0.6 <0.2 0.9
- 0.1 0.9 0.2 1.0 0.1
] 27 32A i1 0.6
- 0.5 <0.2 0.8 0.I 1.0 0.2 1.0 + 0.1 5
{ 28 32A 12 1.1 0.7 (u.2 0.9 0.1 1.1 0.2 1.2 0.1 s
i 99 32A 12 1.2 i 0.6 <0.3 1.1 t o.1 1.3 0.2 1.3 0.1
.b 30 32A 12 1.I
- 0.6 <0. 2 1.0
- 0.1 <0.4 1.2 0.I !
TABLE I (Continued) - -
i:
[' EXPOSURE RATES AND RADIONUCLIDE CONCENTRATIONS IN SOIL SAMPLES , .
OKLAllOMA REFINERY SITE KERR-McGEE CORPORATION
$ CUSIIING, OKLAIIOMA 7
Exposure Rates Radionuclide Concentration (pCi/g) i ESSAP Sample Survey Unit. ,
2 ID (PR/h) U-238 U-235 Ra-226 Th-232 Th-223 31 32A 12 0.9 0.6 <0. 2 1.0 0.1 1.2
- 0.2 1.1 0.1 32 52A 13 1.4 0.6 <0.2 1.0 i 0.I 1.2 0.2 1.2 0.1 33 52A 12 0.9 0.5 <0.1 0.8 0.1 0.9 0.1 0.9 0.1 34 52A 13 1.0 0.5 <0.2 0.9 0.1 1.8 0.2 1.9 0.1 35 52A 12 1.1 0.6 0.1 0.1 1.0 0.1 1.3 0.2 1.1 0.1 36 52A 12 1.3
- 0.7 <0. 2 1.0 0.I 1.0 0.2 1.1
- 0.1 37' 52A --d 0.7
- 0.6 <0.2 0.9 0.I 1.8
- 0.2 1.8 0.1 38' 52A 15 0.9
- 0.6 <0.3 0.9 0.1 . 2.5 0.2 2.5 0.1 39 40A 12 0.9
- 0.5 <0.2 1.0 0.I 1.2 0.2 1.2
- 0.1 40 40A 13 1.2 0.7 <0.2 1.1
- 0.1 1.1 i 0.2 1.3 0.1 41 40A 12 1.6 0.8 <0.2 0.9 0.1 1.2
- 0.2 1.1
- 0.1 1
42 40A 10 1.1 0.6 <0.2 1.0
- 0.I 1.2
- 0.2 1.0 0.I 43 40A 12 0.9
- 0.6 0.1 0.I 1.0
- 0.I 1.2
- 0.2 1.2 0.I a
N j 44 40A 15 1.0
- 0.7 <0.2 2.3 0.I 1.3 0.2 1.4 0.I a
45c 40A 15 1.4 0.6 <0.3 1.1 0.1 1.3
- 0.2 1.2 0.1
[
t TABLE I (Continued) - -
k EXPOSURE RATES AND RADIONUCLIDE CONCENTRATIONS IN SOIL SAMPLES j OKLAIIOMA REFINERY SITE g KERR-McGEE CORPORATION g CUSIIING, OKLAllOMA f
f ESSAP Sample Survey Unit.
Exposure Rates Radionuclide Concentration (pCi/g)
ID (pR/h) -
U-238 U-235 Ra-226 Th-23 ' Th-228 d
46' 40A ---
< l .9 <0. 5 9.0 * .04 1.4
- 0.3 1.3 0.1 47 40A 14 0.8
- 0.6 <0.3 5.6
- 0.2 1.4 t 0.2 1.4 + 0.1 48' 40A ---d <l .7 <0.4 9.1
- 0.3 1.3
- 0.3 1.7 i 0.I 49' 40A 12 1.1
- 0.6 <0.3 2.0 0.1 1.1 i 0.2 1.1 0.1 50 40A 11 <l .7 <0.4 1.0
- 0.2 2.3
- 0.5 2.5
- 0.2 5I= 40A Ii 1.5
- 0.8 <0.3 1.0 i 0.1 1.7 0.2 1.7 i 0.1 52 40A 11 0.9 0.6 <0.2 1.0 0.I 2.8 i 0.2 2.9 0.1 53' 40A 11 1.2 0.7 <0.2 1.0 0.1 1.4 0.2 1.7 0.1 54 108A 9 0.7
- 0.5 <0.1 0.5
- 0.1 0.5
- 0.1 0.5 0.1 55 108A 10 0.7
- 0.6 <0. 2 0.6 0.1 l 0.5 0.1 0.6
- 0.I i 4' 56 108A 9 0.4
- 0.4 <0.1 0.8
- 0.1
- l 0.8 0.1 0.7 i 0.1 57 108A 12 0.6 i 0.5 <0.2 0.7 0.1 2 0.8 0.2 1.0 0.1 i 58 108A 10 1.3 0.6 <0.2 0.9 0.1 0.8
- 0.2 0.9
- 0.1 59 201A 10 0.7 0.6 <0.2 0.9
- 0.I 8 1.0
- 0.2 1.0 0.1 60 201A 9 0.7 0.4 <0.2 0.7 0.1 0.9 0.2 0.9
- 0.I
?
TABLE I (Continued) . -
r -
@ EXPOSURE RATES AND RADIONUCLIDE CONCENTRATIONS IN SOIL SAMPLES f OKLAHOMA REFINERY SITE ',
i KERR-McGEE CORPORATION
$ CUSIIING, OKLAllOM A F
7
} ESSAP Sample Exposure Rates Radionuclide Concentration (pCi/g)
Survey Unit,
- ID (pR/h) U-238 U-235 Ra-226 Th-232 Th-228 61 201A 10 1.1 0.5 <0.2 0.8
- 0.1 1.0 0.2 1.0 0.1 62 201A 9 1.2 0.6 <0.1 0.9
- 0.1 0.8 0.1 0.8 0.1 63 201A 11 0.9
- 0.4 <0.2 0.8 0.1 0.9
- 0.2 0.7 i 0.I d ' Refer to Figures 3 through 13.
6 Uncertainties represent the 95% confidence level, based only on counting statistics.
' Composite sample.
- Exposure rate not taken.
- Borehole sample.
I k
I l
a
.. < r REFERENCES Kerr-McGee Corporation. Final Radiation Survey of Haul Road Corridor. Cushing, OK; May 1996.
Oak Ridge Institute for Science and Education (ORISE). Survey Procedures Manual for the Energy / Environment Systems Division, Environmental Survey and Site Assessment Program, Revision 9. Oak Ridge, TN; April 30,1995a.
Oak Ridge Institute for Science and Education. Quality Assurance Manual for the Energy / Environment Systems Division, Environmental Survey and Site Assessment Program, Revision 7. Oak Ridge, TN; January 31,1995b.
Oak Ridge Institute for Science and Education. Laboratory Procedures Manual for the Energy / Environment Systems Division, Environmental Survey and Site Assessment Program, Revision 9. Oak Ridge, TN; January 31,1995c.
Oak Ridge Institute for Science and Education. Confirmatory survey for the four unaffected areas of the Cushing Refinery Site, Kerr-McGee Corporation, Cushing, OK (Docket No. 70-3073). Oak Ridge, TN; May 1996a.
Oak Ridge Institute for Science and Education. Proposed confirmatory survey plan for the haul road corridor of the Cushing Refinery Site, Kerr-McGee Corporation, Cushing, OK. Oak Ridge, TN; August 1996b.
U.S. Nuclear Regulatory Commission (NRC). Disposal or onsite storage of thorium and uranium wastes from past operations. Washington, DC: Federal Register 46 (205):52061-52063; October 1981.
Ken McGee Corporanon(653). December 12.1996 2b h 'essapVeportswushmgwushmg D02
. t APPENDIX A SI AJOR INSTRUM ENTATION w
Len McGee Corprum(641) Ikcember 12. IPAi h wssapfeporu eushmgwushmg ind
j I
~
j APPENDIX A i
M A.JOR INSTRUMENTATION i The display of a specific product is not to be construed as an endorsement of the product or its manufacturer by the authors or their employers. l DIRECT RADIATION M EASUREMENT Instrninents i
Bicron Micro-Rem Meter
- (Bicron Corporation, Newburg, OH) l l Eberline Pulse Ratemeter i Model PRM-6 (Eberline, Santa Fe, NM) l l 1
1 Ludlum Ratemeter-Scaler Model 12
! (Ludlum Measurements. Inc.,
- Sweetwater, TX)
! Detectors I 1 :
1 I
Victoreen & '- :tillation Detector !
i hiodel489-5.
! 3.2 cm x 3.8 cm Crystal i
(Victoreen, Cleveland, OH) l j I nhorntory Annlytical Instrumentation a
,1 High Purity Extended Range Intrinsic Detectors l
- Model No
- ERVDS30-25195
. (Tennelec, Oak Ridge, TN)
- Used in conjunction with:
Lead Shield Model G-11 (Nuclear Lead, Oak Ridge, TN) and Multichannel Analyzer 3100 Vax Workstation (Canberra, Meriden, CT)
I 1
Ken-McGee Corporaten (65) p . Decen.her12,1996 A-I h w...pwepo,s.<.hme<m.hmeno2
. . I
? . ,' N
- High-Purity Germanium Detector Model GMX-23195-S,23% Eff.
(EG&G ORTEC, Oak Iddge, TN) l Used in conjunction with: i Lead Shield Model G-16 )
(Gamma Products, Palos Hills, IL) and Multichannel Analyzer 3100 Vax Workstation
)
(Canberra, Meriden, CT) l Ken-McGee Corporation (633) December 12,1996 A-2 h vssapveportswushmg'cushmg (02
APPENDIX 11 SURVEY AND ANALYTICAL PROCEDURES Ren4kGee Corpcutum(631F December 10.19% h 'essap<seemswushmgtmhms (112
'A
!, l '.
.i i
l APPENDIX B l SURVEY AND ANALYTICAL PROCEDURES SURVEY PROCEDURES Surface Senns Surface scans for gamma activity were performed by passing the detector slowly over the surface maintaining the distance between the detector and the surface at a minimum. Identification of elevated levels was based on increases in the audible signal from the recording and/or indicating instrument. Combinations of detectors and instnaments used for the scans were:
Gamma - Nal scintillation detector with ratemeter and/or ratemeter-scaler Ernosure Rnte Mensurements Measurements of dose equivalent rates (prem/h) were performed at.1 m above the surface using a Bicron microrem meter. Although the instrument displays data in prem/h, the prem/h to pIUh ,
conversion is essentially unity.
l Soil Sam nline i
Approximately I kg ofsoil was collected at each sample location. Collected samples were placed in I a double plastic bags, sealed, and labeled in accordance with ESSAP survey procedures. Surface soil samples were collected at a depth of0-15 cm, while subsurface soil samples were collected at a depth of 15-30 cm.
ANALYTICAL PROCEDURES Gamma Snectroscony Samples ofsoil were dried, mixed, crushed, and/or homogenized as necessary, and a portion sealed in 0.5-liter Marinelli beaker or other appropriate container. The quantity placed in the beaker was
, chosen to reproduce the calibrated counting geometry. Net material weights were determined and i
Kerr.McGee Corporauon (653) December 12. Im O*I h icuapveports\cushmgwushmg 002 8g 4
i , ,' .
I the-samples counted using intrinsic germanium detectors coupled to a pulse height analyzer system.
Background and Compton stripping, peak search, peak identification, and concentration calculations were performed using the computer capabilities inherent in the analyzer system. All photopeaks associated with the radionuclides of concern were reviewed for consistency of activity. Energy peaks ,
used for determHing the activiA of radionuclides of concerns were: l U-238 0.063 MeV from Th-234*
U-235 0.143 MeV Th-232 0 911 MeV from Ac-228*
Th-228 0.239 MeV from Pb-212*
Ra-226 0.352 MeV from Pb-214*
- Secular equilibrium assumed.
Spectra were also reviewed for other identifiable total absorption peaks.
UNCERTAINTIES AND DETECTION LIMITS The uncertainties associated with the analytical data presented in the tables of this report represent the 95% confidence level for that data. These uncertainties were calculated based on both the gross sample count levels and the associated background count levels. Additional uncertainties, associated with sampling and measurement procedures, have not been propagated into the data presented in this l l
report. .
Detection limits, referred to as minimum detectable concentration (MDC), were based on 2.71 plus 4.65 times the standard desiation of the background count [2.71 + (4.65/BKG)]. When the actisity was determined to be less than the MDC of the measurement procedure, the result was reported as less than MDC. Because of variations in background levels, measurement efliciencies, and contributions from other radionuclides in samples, the detection limits differ from sample to sample and instmment to instrument.
CALIBRATION AND QUALITY ASSURANCE Calibration of all field and laboratory instrumentation was based on standards / sources, traceable to National Institute of Science and Technology (NIST), when such standards / sources were available.
In cases where they were not available, standards of an industry recognized organization were used.
Ken AlcGee Cceporanon (651) . thember 10. IM B-2 h iewapweports'cushmg1cushmg 002 W
p ,. -
9 l Analytical and field survey activities were conducted in accordance with procedures from the
! following documents of the Environmental Survey and Site Assessment Prograin: i Survey Procedures Manual, Revision 9 (April 1995)
Laboratory Procedures Manual, Revision 9 (January 1995) l Quality Assurance Manual, Revision 7 (January 1995) i l The procedures contained in these manuals were developed to meet the requirements of DOE Order l 5700.6C and American Society ofMechanical Engineers (ASME) NQA-1 for Quality Assurance and contain measures to assess processes during their performance. !
l l Quality control procedures include:
l l -
Daily instrument background and check-source measurements to confirm that equipment operation is within acceptable statistical fluctuations.
Participation in Environmental Protection Agency (EPA) and Environmental
\
' l Measurements Laboratory (EML) Quality Assurance Programs. '
Training and certification of all individuals performing procedures.
Periodic internal and external audits.
I l
?
Kerr McGee Corporanon (653) December 12.1996 B-3 h ,o.gvepe,1,<ussm,sco,vn, m: