ML20211G041
| ML20211G041 | |
| Person / Time | |
|---|---|
| Site: | 07003073 |
| Issue date: | 09/08/1997 |
| From: | Lux J KERR-MCGEE CORP. |
| To: | Brown S NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| NUDOCS 9710010414 | |
| Download: ML20211G041 (22) | |
Text
'/ n-30 73 KERRMcGEECORPORAHON Atten WCQlt C lldith 6 CAL AHOW4 CIT Y, ORL AHOWA F3176 September 8,1997 Mr. Stewart Brown Low Level Waste & Decommissioning Projects liranch Division of Waste Management Ornce of Nuclear Materials Safety & Safeguards U. S. Nuclear Regulatory Commission Washington, DC 20555 Re:
Revision to License Amendment Request dated Sept. 4,1996 Docket No. 70,7p73 License No. SRM 1999
Dear Mr. Brown:
In accordance with telephone conversations and meetings conducted over the past several months, Kerr McGee Corporation (KMC) is submitting this revision to the above referenced license amendment request.
This revision clarifies issues raised by the U.S. Nuclear Regulatory Commission (NRC) in its review of that request, and proposes the deletion or
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modincation of several current license conditions to " clean up" the license to decommission the Cushing refinery site.
Review of the licuise conditions, based on work accomplished since the license was issued,-
3 makes it clear that several existing license conditions are outdated and no longer reflect jvP conditions and operations at the site. KMC proposes deletion or modification of several existing license conditions to reflect the current status of the Cushing site. License conditions and proposed revisions are discussed below.
Condition A This license condition requires the submittal of a Proposed Decommissioning Plan. Since the deconunissioning plan was submitted over three years ago, there is no need for this lice...se condition. KMC requests that this condition be deleted. KMC's comments on Condition K incorporate the requirement that decommissioning be performed in accordance with an approved decommissioning plan.
Condition B This condition requires the submittal of action plans prior to the perfonnance of certain activities. All plans referenced in the condition have been submitted to NRC. KMC requests that this condition be deleted. KMC's comments on Condition K incorporate the requirement that activities such as those addressed in Condnbn B be performed in accordance with approved plans.
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' CMidillMLC KMC has submitted a revision of item 8 of the license application, entitled " Radiation Safety Training" Itcm 8 complies with regulatory requirements, and renders Condition C unnecessary. KMC therefore proposes that NRC delete Condition C.
CWi@llMLU Condition D was initially included in the license because the Cushing site had no dedicated radiation safety program at the time. Since that time, KMC has developed and implemented a radiation safety program for the Cushing site, managed by on-site personnel. This program is inspectable, and complies with regulatory standards for radiation protection. KMC believes this license condition is no longer necessary, and should be deleted. NRC has maintained that identified limits must be stipulated in the license; however, all lleensees must comply with radiation protection stanoards promulgated in 10 CFR 20, and KMC does not believe it is necessary to cite limits in this license.
Condition E Condition E stipulates the use of Policy and Guidance Directive 83 23 limits for the unrestricted release of equipment, personnel, or materials.
This license condition was established because KMC's 1992 license application referenced a different document. Ite m 9 of the enclosed revision to the license application cites Policy and Guidance Directive 83 23, rendering Condition E unnecessary. KMC therefore proposes that NRC delete Condition E.
Condition F KMC does not request any change to Condition F.
Condhion G License Condition G states, "All work in radioactive materials areas, or work with licensed material not located in radioactive materials or restricted areas shall be in accordance with an approved radiation safety procedure "
Strict interpretation of this condition results in unnecessarily restrictive requirements, some of which are discussed below.
" All work in radioactive materials areas Visitors and workers may enter radioactive materials areas but not work with radioactive materials or receive measurable exposure to radiation or radioactive materials. The license condition should not reference gE work, but only work that may result in measurable exposure to radiation or radioactive materials.
.. work with lienised material not located in radioactive materials areas or restricted areas.
- Workers often perform work outside of " radioactive materials areas", where the concentration of licensed material in the soil, waste, or debris may be above background but below established unrestricted release limits. Because licensed material is present in these areas, strict interpretation of this license condition requires radiation safety procedures when work is performed in such areas, it is inappropriate to require radiation safety procedures for work for which there is no radiation safety hazard.
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... in accordance with an approved radiajlon safety procedure 4
Workers often perform work covered under plans and procedures which are not a part of the radiation safety program. Radiation safety procedures cover work perfonned by health physics personnel, such as monitoring activities, surveying areas, calibrating instruments, assigning dose, etc. Operating plans and procedures, such as the site Samp!!ng and Analysis Plan and 1
Procedures, address sampling soil, waste, ground and surface water, and sediment, and preparing and submitting samples for analysis. Special work permits address the performance of work such as excavating and sorting soll, mowing or clearing vegetation, etc. These plans and procedures provide guidance to workers to minimize exposure to radiation safety hazards and identify the type of health physics support needed to perfonn the work. It is inappropriate to incorporate all such work in radiation safety procedures because the work is often perfonned in areas where radiation safety is not an issue.
In response to the above situations, KMC requests that license Condition G be revised te state.
" Work that could result in an annual exposure in excess of 100 mrem shall be performed in-accordance with approved plans and/or procedures that identify necessary radiation safety precautions and monitoring.
Such plans and/or procedures require the approval of the Radiation Safety Officer or designated alternate "
Conditiortli KMC does not request any change to license Condition 11.
Condition i KMC does not request any change to license Condition I.
Condition J KMC does not request any change to license Condition J.
Condition K License inspections have stated that the referenca to the license application in Condition K means statements made in the application are license requirements. Much of the 1002 license application was written to describe past or then-current licensee activities, not to become
- license requirements. Numerous statements made in the application that may have been correct and appropriate at the time of submittal may no longer be accurate for several reasons, including the following:
- The development and implementation of a radiation safety program independent from any other Kerr McGee licensed facility (Cimarron, in this case)
- Increased knowledge gained from additional site characterization performed since the license was issued.
- Statements may have reflected what was being done at the time, rather than what is appropriate to govern radiological activities as a license condition.
.O The most effective way to resolve the problems associated with such statements is to revise the license application submitted to the NRC in September,1992. The enclosed revision mo<lifies and replaces the revision submitted September 4,1996. Revising the 1992 applicaten by replacing the enclosed items 5 through 11 and Attachments 1 through 3 of the license application will make it unnecessary to reference a string of documents in Condition K. This will facilitate inspection of and compliance with the license. KMC requests that liRC replace items 5 through 11 and attachments 2 and 3 of the September,1992 license application with the attached revision.
KMC requests that Condition K t e modified to state, "Except as specifically provided in this license, the licensee shall conduct its program in accordance with the application revision submitted September 3,1997 and the Site Decommissioning Plan as approved by NRC."
Atiachment 1 Attachment I to the 1992 license application is an estimate of the volume of residual radioactive material at the Cushing refinery site. KMC has not updated this volume estimate as site characterization data is obtained because the total volume of contaminated material is not critical. The volume of contaminated material that must be removed to achieve unrestricted release is the critical value. Estimates of this volume will continue to change as methods for treating radiologically contaminated hydrocarbon are developed, as site characterization data on increasingly dense spacing is obtained, and as excavation and stockpiling takes place. Since this volume is not critical to the license itself, KMC is not submitting a volume estimate. to the 1992 license application is a list of individuals key to the decommissioning of the Cushing site, and a summary of their resumes. This is submitted as the new Attachment I to the September,1997 application revision. to the 1992 license application is a list of emergency contacts This list is submitted as Attachn,$at 2 to the September,1997 application revision. to the 1992 license application is a decommissioning funding plan.
A decommissioning t'unding plan is not normally a part of a license application. It is nonnally submitted as part of a Site Decommissioning Plan. Consequently, KMC is not revising the decommissioning funding plan for this submittal.
The existing decommissioning funding mechanism will remain in effect until the cost estimate is revised and a new funding mechanism provided to the NRC as part of the decommissioning plan. Attachment 4 to the 1992 license application is enclosed as Attachment 3 to the September,1997 revision. This funding plan will remain unchanged until a new funding plan is resubmitted as an attachment to the Site Decommissioni,w 'n.
. Condusion KMC believes that revision of the license application and deletion and/or nmdification of the cited license conditions provide the most effective means for addressing difficulties associated with the existing license record.
KMC requests NRC's expeditious review of the above requests and enclosed revision to the license application.
If you have any questions or comments regarding this license amendment request, please call me at (405) 270-2694 (Oklahoma City) or (918) 225 7753 (Cushing).
Sincerely, Jeff Lux cc:
Charles Cain NRC Region IV Rick Reiley, Cushing Citizens' Oversight Committec Gene Smith, DEQ Darrell Shults DEQ
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1 KERR-McGEE CORPORATION U. S. NUCLEAR REGULATORY COMMISSION LICENSE APPLICATION CUSHING, OKLAHOMA REFINERY SITE I
REVISION 2 (PROPOSED) i SEPTEMBER,1997
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. ITES! 5 - RADIDACTIVE MATERIAL Radioactive material present at the site consists of uranium and thorium in the form of residual contamination of soil, building material, debris, and refinery wastes. Uranium enrichment varies from less than natural isotopic ratios to highly enriched. Levels of contamination are typically less than 100 pCi/g uranium and 50 pCi/g thorium Primary radionuclides of concern are Th-232, U-234, U-235, and U-238.
Uranium was received in purified form. Its daughters are not ingrown past the U-234 isotope.
Thorium was also received in purified form, but since processing activities ceased over 30 years ago, its daughters have grown nearly into secular equilibrium with the parent Th-232 isotope.
Thorium is the only licensed material found in the only hazardous waste occurring on the Cushing site, i.e., the acidic hydrocarbon sludge contained in Pit 4.
This material is considered hazardous by EPA only because of its characteristic of corrosivity. Once treated for that characteristic, it is no longer hazardous from a regulatory perspective. This material will not be legally generated until excavated. Since it will be treated in place before it is excavated, KMC will neither generate nor dispose of any hazardous waste from the Cushing site.
The quantity of residual uranium and thorium cannot be accurately quantified. An ALARA analysis perfcrmed in 1995 estimated that a total of approximately 360,000 cubic feet of material that exceeds Option 1 limits, most of which is contaminated only with thorium, remain on site. The estimated quantity of residual licensed material has not been revised since that time.
In addition, KMC possesses a number of calibration and check sources used to calibrate and check radiation measuring and analytical instruments.
Although most sources contain quantities of radioactive material that are exenra from specific licensing requirements, there is no exempt quantity for U-235. KMC possesses sources containing less than one niroCurie of U-235 for calibration of the soil count system.
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' ITEM 6 - PURPOSES FOR LICENSED MA TERIAL USE The Cushing site will be decommissioned in accordance with an NRC-approved Site Decommissioning Plan which references NkC's Branch Technical Position (BTP) on Disposal or Onsite Storage of Thorium or Uranium Wastes from Past Operations. Licensed material above the BTP Option I limit (unrestricted release) will be identified, consolidated, and disposed of in accordance with existing regulations.
Licensed material is also used to calibrate and/or check various instruments as noted in item 5.
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e ITEM 7 - INDIVIDUALS RESPONSillLE FOR RADIA TION SAFETY Kerr-McGee Corporation's Safety and Environmental Affairs Division (SEAD) has been delegated responsibility for the decommissioning and release of the Cushing site.
SEAD management provides, through employee and contract staff, the resources necessary to decommission the Cushing site. Management is committed to the safe cleanup of the refinery site in accordance with the Consent Order negotiated with the ODEQ, the NRC license, and applicable regulations. Radiological cleanup activities will be done in a manner that maintains exposures to levels As Low As Reasonably Achievable (ALARA).
An organization chart for the Cushing decommissioning project is presented in Figure 2. The chart identifies individuals responsible for the Cushing site radiation safety program.
The Site Manager oversees the operations and clerical staff, and is responsible for perfonning characterization surveys, decommissioning the site, and performing fmal release surveys.
The Radiation Safety Officer (RSO) is responsible for the Cushing site radiation safety program and the radiological analysis of samples. The RSO, in conjunction with employee and contract staff, monitors decommissioning activities and provides health physics services.
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ITEh! 8 - RADIA TION SAFETY TRAINING Individuals working in radiologically restricted areas are given radiation safety training commensurate with the potential radiological health hazard in the restricted area. The RSO (or designated alternate) determines the potential radiological health hazard for individuals who work in these restricted areas and the level of training required.
Workers classified as " radiation workers" under the site Radiation Safety Plan shall receive initial radworker training and annual radworker requalification training as appropriate. All radworker training shall include, at a minimum, the topics listed in 10 CFR 19.12.
l In some instances, radiation safety training may be given to individuals who are not classified as " radiation workers" The RSO (or designated alternate) determines the radiation safety topics and level of detail appropriate based on the potential radiological exposure associated with performing the work.
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.- ITEM 9 - FACILITIES AND EQUIPMENT The section on facilities is not applicable to this license application.
. Equipment used to manage radioactive material will remain within the confines of radioactive
- materials -- areas !- until appropriate ' decontamination and/or : exit : surveys are performed.
-Equipment will. be allowed to exit RMAs when it meets release criteria presented in
" Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of _ Licenses for Byproduct, Source, or Special Nuclear. Material", Policy
.and Guidance Directive 83-23, August,1987.
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. ITEM 10 - RADIATION SAFETY PROGRAM Radiation surveys and several years of experience at the Cushing site have shown that there is little potential for workers to receive exposures above 10% of the occupational dose stipulated in 10 CFR 20. Nevertheless, areas that may require decommissioning in accordance with the proposed Site Decommissioning Plan have been delineated and posted as Radioactive Materials Areas (RMAs).
Decommissioning work is performed in accordance with an environmental remediation program that governs non-radiological as well as radiological cleanup activities at the Cushing site. Other environmental remediation work is performed in accordance with agency-approved documents such as the Consent Order with the Oklahoma Department of Environmental Quality (ODEQ), NRC license SNM-1999, the Site Decommissioning Plan, the GDEQ Record of Decision, and the Phase i Remedial Design (for the cleanup of acid hydrocarbon waste).
Special Work Permits identify radiological hazards associated with individual activities (such as excavating soil) and measures taken to protect against those hazards. SWPs identify what type of radiological monitoring will be required and what precautions will be taken to ensure that work 's performed in a manner that keeps exposures As Low As Reasonably Achievable (ALARA).
The radiation safety program provides assurance that all radiological decommissioning work is performed safely. The Radiation Safety Plan outlines the program, and radiation safety j
procedures address the performance of specific health physics and radiation survey and l
monitoring activities. The radiation safety program complies with 10 CFR 19 and 20, and includes monitoring and control measures discussed below.
10.1 Surveys and Monitorine of Rad Work Film badges, lapel samplers, and area air samplers monitor radiological work as appropriate.
Air sampling is not required by regulation because KMC does not anticipate exposures in excess of 40% of the acupational limit. Ilowever, survey instruments, air samplug, f.im badges, and thermoluminescent dosimeters may be used to monitor the performance of radiological work as the RSO deems appropriate. The types of monitoring required for various tasks are outlined in SWPs and/or radiation safety procedures.
Effluent analysis will be performed when there is potential for release of licensed radioactive material to the environment to verify that effluent limits are not exceeded. Such sampling is covered by the radiation safety plan and procedures. ALARA principles will be employed.
10.2 Instruments and Calibration Calibrated survey instruments are used to measure radiation exposure and activity levels in the field. An air sample counter and computer based soil counting system are used to analyze samples taken from the field. Equipment is calibrated either at Cushing or by an outside vendor. The frequency of calibration and procedures for verifying that equipment is in calibration and fully functional are addressed in the radiation safety plan and procedures.
IQJ Personnel Monitorine Devices Personnel monitoring devices are used to monitor worker exposure in accordance with the Radiation Safety Plan.
10J Bioassays KMC has conservatively assumed that licensed material remaining on site has a "Y" lung solubility classification. Air monitoring data collected to date indicate only minimal intakes.
Air monitoring is the primary means of evaluating internal exposure. Bioassay samples are not collected on a routine basis. Bioassay sampling requirements, based on other personnel monitoring data, are stipulated in the Radiation Safety Plan.
10J Audits KMC contracts with a third party to perform an annual audit of the radiation safety program, in accordance with 10 CFR 20. This third-party audit focuses on regulatory and license requirements and standard industry practice, in addition, the QA Coordinator performs periodic quality assurance audits of various aspects of the Cushing site cleanup. The radiation safety program is included in the scope of these audits.
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ITEM 11 - WASTE MANAGEMENT Past decommissioning activities are described in the Site Decommissioning Plan, submitted to the NRC in April,1994. No decommissioning has been performed since KMC received license SNM-1999 in April,1993.
IL1 Decommissionine Activities Decommissioning activities will involve characterizing the nature and extent of contamination, excavating soil and waste exceeding decommissioning criteria stated in an approved Site Decommissioning Plan, possibly stockpiling the excavated material, and shipping these materials to a licensed disposal site. Building surfaces will be surveyed, and on the basis of surface contamination will be either decontaminated or shipped to a licensed disposal site for disposal. Decommissicning activities will not concentrate the licensed material contained in soils and wastes.
Soil and waste that do not require decommissioning under the approved Site Decommissioning Plan will be managed as though it were not radiologically contaminated. Such material contaminated by refinery waste will be disposed ofin accordance with Oklahoma regulations governing industrial waste.
Further detail concerning decommissioning activities already performed at the site and proposed decommissioning activities are addressed in the Site Decommissioning Plan.
IL2 Safecuardine Reauirements Licensed material at the Cushing site exists in a form that is not suitable for recovery of either special nuclear material or source material. Preliminary studies indicate that soil washing and chemical extraction provide little or no separation of licensed material from the matrices it exists in.
These materials are acceptable for land disposal and will be handled in accordance with 10 CFR 61 provisions for Class A unstable waste. The waste does not contain any nuclides listed in Tables 1 or 2 of 10 CFR 61.55 and is therefore Class A waste.
In accordance with the Commission's position on safeguarding waste containing special nuclear material, the Cushing site materials are not of a form or concentration that requires protection as set forth in 10 CFR 73.
IL3 Material Control and Accountine Containers destined for off site disposal at a licensed disposal site may contain more than one gram of special nuclear material. The transfer of all such material will be documented.
Records will be maintained in accordance with 10 CFR Part 70.51(b)(1)-(b)(6). Events requiring reporting under 10 CFR Part 70.52 will be made promptly via telephone to the NRC Operations Center at (301) 951-0550.
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l ILf Criticality Considerations
. Conditions at the Cushing site are such that a criticality monitoring system is not needed. The concentration of special nuclear material in Cushing waste is so low that no more than a few l
grams of U-235 could be placed in one large container.
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e ATTACHMENT 1 KEYINDIVIDUALS CUSHING SITE REMEDIATION PROJECT G. D. Christiansen Vice President, Assessment and Remediation Department, Safety and Environmental Affairs Division. Executive responsibility for the remediation and decommissioning of all inactive nuclear, chemical, refming, marketing, distribution, and retail sites owned by Kerr-McGee Corporation and/or its subsidiaries.
S. J. Larsen Project Leader, Assessment and Remediation Department, Safety and Environmental Affairs Division (also Vice President, Cimarron Corporation). Management responsibility for the remediation and deconunissioning of the Cushing site, as well as approximately fifteen other nuclear, refmery, and chemical sites.
J. J. Lux
- Project Manager, Assessment and Remediation Department, Safety and Enviromnental Affairs Division. Management responsibility for the remediation and decommissioning of the Cushing site as well as one additional refinery site.
R. E. Pounds Site Manager, Cushing, Assessment and Remediation Department, Safety and Environmental
. Affairs Division. Operations responsibility for the remediation and decommissioning of the Cushing site as well as one additional refmery site.
T. M. Moore Staff Health Physicist (Radiation Safety Officer), Assessment and Remediation Department, Safety anu Environraatal Affairs Division. Responsible for the development anu implementation of the Cushing radiation safety program and health physics department.
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GEORGE D. CHRISTIANSEN Kerr-McGee Corporation Safety and Environmental Affairs Division Assessment and Remediation Department Current Position:
Vice President, Assessment and Remediation Safety and Environmental Affairs Division Education:
B.S. Geology, University of Wyoming,1968 Experience:
1968 - Present - Kerr-McGee Comoration l
Positions held:
1994 - 1995 Minerals Exploration, Environmental Assessment, Hydrology, and Real Estate Management 1980 - 1994 Minerals Expleration Management 1974 - 1980 Uranium Exploration Management 1970 - 1974 Uranium and Coal Exploration Geology
'968 - 1970 Uranium Mine Geology i
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S. JESS LARSEN Kerr-McGee Con poration Safety and Environmental Affairs Division Assessment and Remediation Department Current Position:
Project Leader, Assessment and Remediation Safety and Environmental Affairs Division Education:
B.S. Civil Engineering, University of Utah,1968 Experience:
1978 - Present - Kerr-McGee Corporation Positions held:
Project Leader, Safety and Environmental Affairs Division, Oklahoma City, Oklahoma Executive Assistant, TiWest Joint Venture, Perth, Western Australia General Manager, Kerr-McGee Chemical Corporation Western Australia Pty Ltd.
Mine Manager, Clovis Point Coal Mine, Gillette, Wyoming Min: Manager, Jacobs Ranch Coal Mine, Gillette, Wyoming _
1967 - 1978 - Kenecott Cooper Corporation Positions held:
Mme Maintenance Superintendent Truck Area Superintendent Truck & Dozer Repair General Foreman Truck General Foreman Mine Safety Engineer Truck Area Safety Engineer Truck Shift Foreman
.. s-6 JEFFREYJ. LUX Kerr-McGee Corporation Safety and Enviromnental Affairs Division Assessment and Remediation Department Cutrent Position:
Project Manager, Assessment and Remediation Safety and Environmental Affairs Division Education:
B.S. Geological Engineering, University of Missouri-Rolla, 1975 M.S. Geological Engineering, University of Missouri-Rolla,-
1986 Radiation Safety Instrumentation and Compliance, Oklahoma State University,1991
_l Principles of Radiation Safety, Oklahoma State University,1992 Certification:
Registered Professional Engineer - Oklahoma PE 16528 Experience:
1987 - Present - Kerr-McGee Corporation l
Positions held:
I 1991 - Present - Project Manager, Environmental Operations, later Safety and Environmental Affairs Division Responsible for the remediation and decommissioning of the Cushing site as well as one additional refinery site.
1987 - 1991 - Kerr-McGee Corporation, Hydrology Department Hydrologist, Senior Hydrologist, Staff Hydrologist - Responsible for groundwater assessment and remediation, aquifer test analysis, and groundwater recovery system design. Planned and implemented RCRA and CERCLA facility investigation and remediation programs.
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ROBERT E. POUND 5 Kerr-McGee Corporation Safety and Environmental Affairs Division Assessment and Remediation Department Current Position:
Site Manager, Cushing, Assessment and Remediation Safety and Environmental Affairs Division Education:
B.S. Construction Science, University of Oklahoma,1988 Exp:rience:
1993 - present - Kerr-McGee Corporation, Environmental Operations, later Safety and Environmental Affairs Division Positions held:
1996 - present - Site Manager, Cushing and Cleveland, Operations responsibility for the remediation and decommissioning of the Cushing site as well as one additional refinery site.
1993 - present - Site Manager, Cleveland, q
l Operations responsibility for the remediation and decommissioning of the Cleveland, Oklahoma refinery site 1989 - 1994 - Technology & Engineering Division, Engineering
& Construction Department 1987 - 1988 - University of Oklahoma Physical Plant 1975 - 1986 - Kerr-McGee Cornoration, Transworld Drilling Company l
c TERENCE M. MOORE Kerr-McGee Corporation Safety and Environmental Affairs Division Assessment and Remediation Department Current Position:
Health Physics Specialist, Assessment and Remediation Safety and Environmental Affairs Division Education:
B.S. Health Physics, Oklahoma State University,1980 Certification:
National Registry of Radiation Protection Technologies,1988 Part 1 ABHP Certification,1993 Experience:
1993 - Present - Kerr-McGee Corporation Staff Health Physicist Responsible for the development and implementation of the Cushing radiation safety program and health physics departr :nt.
1991 - 1993 - Denartment of Enercy Weapons Production Plant, EG&G Rocky Flats, Golden, Colorado Health Physicist VK/ Radiological Engineer - Responsible for development and implementation of procedures relating to release of waste and property, as well as implementation of DOE Radiological Control Manual. Involved with determination of hazardous & non-hazardous waste sticams.
1980 - 1991 - Wolf Creek Generatine Station 4
Positions held:
1988 - 1991 - Health Physiu Engineer - Developed mixed waste program. Track and trend waste generation data. Administer radioactive waste transportation and burial program.
1986 - 1991 - Health Physics Operations /ALARA Engineer - Performed ALARA plant modification studies. Served as HP shift lead and HP containment coordinator during three refueling outages and provided radiological engineering support for a fourth refueling outage.
1980 - 1986 - Health Physics Lead Technician - HP lead foreman in respiratory protection. Assisted in setup of radiation protection program. Wrote radiation protection and training procedures.
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ATTACHMENT 2 EMERGENCY CONTACTS U.S. NUCLEAR REGULATORY AGENCY Mr. Stewart Brown Office of Nuclear Materials Safety & Safeguards U.S. Nuclear Regulatory Commission
- Washington, D.C. 20555 (301) 415-6605 Mr. Charles Cain
- U.S. Nuclear Regulatorv Commission - Region IV 611 Ryan Plaza, Suite 100 Arlington, TX 76011 (817) 860-8186 I
NRC Emergency Operations Center Washington, D.C.
(301) 816-5100 (301) 951-0550 OKLAHOMA DEPARTMENT OF ENVIRONME14TAL OUALITY Mr. Gene Smith Oklahoma Department of Environmental Quality -
Radiation Management Section 1000 N.E.10* Street Oklahoma City, OK 73117-1212 (405) 271-1902 Darrell Shults Waste Management
-(405) 271-7131 CITY OF CUSHING Mr. Robert Collings, City Manager City Hall 100 Judy Adams Boulevard Cushing, OK-74023 (918) 225-5176 Mr. Joe ManJng, Mayor City Hall 100 Judy Adams Boulevard Cushing, OK 74023 (918) 225-2394
- Mr. John Henckel, Fire Chief P.O. Box 311 Cushing, OK 74023 (918) 225-3361
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j' Mr. Rick Reiley, Chairman Cushing Citizens' Oversight Committee c/o Cushing Library P.O. Box 551 Cushing, OK. 74023 (918) 225-6318 NATIONAL RESPONSF, CENTER Environmental Protection Agency
.(202) 426-2675 L
KERR-McGEE CORPORATION J.' J. Lux, Project Manager
.(405) 270-2694 1.
l S. J. Larsen, Project Leader (405) 270 2288 l
R.E. Pounds, Site Manager (918) 225-7753' State Wide Pager (405) 647-6805 T.M. Moore, Staff Health Physicist (918) 225-7753 State Wide Pager (405) 636-8831 I