LD-89-126, Application for Amend to License SNM-0033,reflecting Organizational Changes

Application for Amend to License SNM-0033,reflecting Organizational Changes

ML19332D355
Person / Time
Site:	07000036
Issue date:	11/14/1989
From:	Scherer A ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY
To:	Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
26108, LD-89-126, NUDOCS 8912010064
Download: ML19332D355 (52)

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Y@gN, %L C4 Novem $4 1 usNEC - \\I. LD 2$ ,1 yd ENGINER pgrato y vsnee 989 ) & i' Nc)y221sgg y '7p ~ 1 110V221 nil 3 t,o, 'l%v y-was Jj um acuo" t, /- URN [N/ D00KU CklEK 4 g (' ty .p Docket No. 70-3 'u License No. SNM-33 i Mr. Leland C. Rouse, Chief Fuel Cycle Safety Branch Division of Industrial and Medical Nuclear Safety Office of Nuclear Material Safety and, Safeguards U. S. Nuclear Regulatory Commission Attn:. Document Control Desk Washington, D. C. 20555 s

Subject:

Revision to Licease Amendment Request for Hematite Organizational Changes

Reference:

. Letter LD-89-071, A. E. Scherer to L. C. Rouse (NRC) dated July 7,1980

Dear Mr. Rouse:

This letter transmits an update to the organizational changes described in Combustion Engineering's amendment request of July 7,1989, (Reference) for our Hematite Fuel Manufacturing Facility. This change package supersedes, in its entirety, our Reference request. These revisions represent a result of discussions between our Mr. J. F. Conant and Mr. D. A. McCaughey of your staff. Forwarded herewith are Enclosure I, containing a list of the affected { pages, Enclosure II containing a tabulation describing changes relative to the Reference amendment request, and Enclosure III, the proposed amendment package. Ten copies of Enclosures I, II and III are included for your use. ^ 8912010064 891114 {DR ADOCK0700g6 Power Systems 1000 Prospect Hill Road (203) 688-1911 Combustion Engineering, Inc. Post Office Box 500 Telex: 99297f Windsor, Connecticut 06095-0500 [9 a<

gx r ' Mr.l Leland C. Rouss : LD-89-126 November 14,.1989-Page 2 If I can-be of any assistance on this matter, please do not hesitate to call me or Mr. J. F. Conant of my staff at (203) 285-5002. Very truly yours, 1 COMBUSTION ENGINEERING, INC. A. S i Eherer Director Nuclear Licensing. AES:Jeb

Enclosures:

As Stated cc: G. D. France (NRC - Region III) D. A. McCaughey l

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y .e,(, i Enclosure !! to s LD-89-126 l i l t I COMBUSTION ENGINEERING, INC. r HEMATITE NUCLEAR FUEL MANUFACTURING FACILITY { REQUEST I?OR LICENSE AMENDMENT i i DESCRIPTION OF CHANGES I i F t I I f l NOVEMBER 14, 1999 , ~.,- -,, - ~. -, - .e-. - - -.,,

n HENAT!TE NU(! EAR FUEL NANUFACTURING FACILITY 1 REQUEST FOR LICENSE ANENDNENT Combustion Engineering requests that the application for license l (SNM 33); for the Hematite Nuclear Fuel Manufacturing facility be amended to incorporate changes to the organizaticnal description. This change package supercedes, ir, its entirety, our amendment package l dated July 7, 1989, (LD-89-071). The proposed package is provided in Enclosure III. In order to facilitate your review the following tabulation provides a description of the differences from our July 7,1989 submittal. PAGE NO. SECTION CHANGE DESCRIPTION i i Table Contents Added page. Comply with text changes. 11 Table Contents Added page. Comply with text changes. i 1.2-3 2.1.6 Clarify that " semi-annual" refers to an inspection, not an audit. I.2 4 2.1.7 Relocate position description from Part 11 for Supervisor. Health Physics. I.2-4 2.1.8 Add position description for Senior Health Physics Technicians. I.2-5 2.3 Revise Safety Committee description. I.2-6 2.6 Specify that cogalzant manager shall approve Operation Sheets. I.2-8 2.6(b) Specify that a reviewer of criticality evaluations shall have two years experience as a Nuclear Criticality Specialist. I.2-8 2.6 Clarify that the two year review of Operation Sheets is only to identify need for updating. It is responsibility of cognizant manager. I.2 9 2.7 Combine requirements for quarterly and semi-annual inspections and add requirement l for the criticality inspector. i L License No. SNM 33 Docket No. 70 36 Date: November 14, 1989

i PAGE NO. SECTION CHANGE DESCRIPTION I.2-10 Table Revise education and experience requirement I.2 1 for NLS&A Manager and add Supervisor, Health Physics and Senior Health Physics Technicians. I.3-6 3.2.4.1 Added page. Update position title. !.3 8 3.2.4.3 Added page. Update position title. I.4-1 4.1.2 Added page. Update position title and reference to revised section number. 11.3 1 3.0&3.1 Combine.two organization chart descriptions into one chart. 11.3-2 (formerly Delete position description for Project 3.I.3) Director of Manufacturing Technology. 11.3-2 (formerly Delete position description for Supervisor 3.1.4 Health Physics; relocated to Section 2.1.7. Part I) 11.3-3 (formerly Delete position description for Program 3.1.9) Manager, Radiological and Industrial Safety. II.3-3 3.1.7 Add position description for Supervisor, l' Maintenance. 11.3-3 (formerly Delete Section 3.2 and table on education 3.2 and and experience requirements for positions not Table of key importance to safety. 11.3-1) l II.3-3 3.2 Delete names and resumes for persons not in l (formerly positions of key importance to safety, Section 3.3) L i 11.3-5 3.2 Add resumes for Vice President and General l (formerly Manager, Nuclear Fuel Manufacturing; Nuclear Section 3.3) Criticality Specialist; and Supervisor, Health l Physics. (formerly Delete Table 11.3-1 Table 11.3-1) 11.3-25 Figure Revise Organizational Chart. 11.3-1 License No. SNM 33 Docket No. 70 36 Date: November 14, 1989 ,._.c. ..~.._.

-l x \\ Enclosure ill to a LD-89-126 2 COMBUSTION ENGINEERING. INC. HEMATITE NUCLEAR FUEL MANUFACTURING FACILITY REQUEST FOR LICENSE AMENDMENT PROPOSED LICENSE AMENDMENT PAGES i i [ t i F t t NOVEMBER 14, 1989 1 .. -... ~ _. _ -.... -.. _ -.... - - _ _. _...... _ _.,

t 3 TABLE OF CONTENTS PART I LICENSE CONDITIONS Section 1.0 STANDARD CONDITIONS AND SPECIAL AUTHORIZATION 1.1 Name 1.2 Location 1.3 License Number e 1.4 Possession Limits 1.5 Location Where Material Will Be Used 1.6 Definitions 1.7 Authorized Activities 1.8 Exemptions and Special Authorizations 2.0 ORGANIZATION AND ADMINISTRATION 2.1 Organizational Responsibilities and Authority 2.2 Personnel Education and Experience Requirements 2.3 Hematite Plant Safety Committee 2.4 Approval Authority for Personnel Selection 2.5 Training 2.6 Operating Procedures 2.7 Audits and Inspections 2.8 Investigations and Reporting 2.9 Records 3.0 RADIATION PROTECTION 3.1 Administrative Requirements 3.2 Technical Requirements 4.0 NVCLEAR CRITICALITY SAFETY 4.1 Administrative Requirements 4.2 Technical Requirements 5.0 ENVIRONMENTAL PROTECTION 5.1 Effluent Control Systems 5.2 Environmental Monitoring 6.0 INDUSTRIAL SAFETY 7.0 DECOMMISSIONING PLAN 8.0 EMERGENCY PLAN 9.0 FUNDAMENTAL NUCLEAR MATERIAL CONTROL PLAN l 10.0 PHYSCIAL SECURITY PLAN l License No. SNM-33, Docket 70-36 Revision: 1 Date: 11/14/89 Page: i i l" - -

l TABLE OF CONTENTS PART 11 SAFETY DEMONSTRATION l Section 1.0 OVERVIEW OF OPERATIONS 1.1 Corporate Information i 1.2 Operating Objective and Process Summary 1.3 Site Description 1.4 Loc &tions of Buildings on Site 1.5 License History 2.0 FACILITY DESCRIPTION 2.1 Plant Layout 2.2 Utilities 2.3 Heating, Ventilation, and Air Conditioning 2.4 Waste Handling 2.5 Chemical Storage 2.6 Fire Protection 3.0 ORGANIZATION AND PERSONNEL 3.1 Organizational Responsibilities 3.2 Resumds of Parsonnel f 4.0 RADIATION PROTECTION PROCEDURES AND EQUIPMENT 4.1 Procedures e 4.2 Posting and Labeling 4.3 Personnel Monitoring 4.4 Surveys t 4.5 Records and Reports 1 4.6 Instruments 4.7 Protective Clothing 4.8 Dosimetry 4.9 Respiratory Protection l-5.0 OCCUPATIONAL RADIATION EXPOSURES 5.1 External Radiation Exposures 5.2 Internal Radiation Exposures 6.0 ENVIRONMENTAL SAFETY [ 6.1 Airborne Releases 6.2 Liquid Releases 6.3 Non-Radiological Releases 1 6.4 Environmental Monitoring Summary 7.0 NUCLEAR CRITICALTIY SAFETY 7.1 Surface Density Criteria 7.2 Array Reflection 1' 1. l l License No. SNM 33, Docket 70-36 Revision: 1 Date: 11/14/89 l Page: ii _.r s

o = j 1 i i i 2.0 ORGANIZATION AND ADMINISTRATION 3 i 2.1 Oraanizational Responsibilities and Authority The President, Nuclear Power Businesses has the ultimate responsibility for ensuring that corporate operations related to the Nuclear Power Businesses Division are conducted safely and in compliance with applicable regulations. The President has delegated the responsibility for nuclear fuel manufacturing and product development activities to the Vice President, Nuclear Fuel. 2.1.1 Vice President and General Manaaer. Nuclear Fuel Manufacturina The Vice President and General Manager, Nuclear Fuel Manufacturing i reports to the Vice President, Nuclear fuel. He has overall responsibility for the operation of Combustion Engineering's nuclear fuel manufacturing facilities located in Hematite, Missouri (SNM-33) and Windsor, Connecticut (SNM-1067). His responsibilities include operations, accountability, security, training, criticality safety, radiological and industrial safety, environmental protection, transportation, materials handling and storage, licensing, process and equipment engineering and maintenance. f 2.1.2 Plant Manaaer. Hematite The Plant Manager, Hematite reports to the Vice President and General Manager for Nuclear Fuel Manufacturing. He directs the total operation of_ the Hematite facility including the production, accountability, security, criticality safety, radiological and industrial safety, environmental protection, transportation, training, materials handling and storage, licensing, process and equipment engineering and maintenance. He fulfills these functions License No. SNM-33, Docket 70-36 Revision: 1 Date: 11/14/89 Page: 1.2-1

( l l 2.1.2 Plant Manaaer. Hematite (Continued) i by delegation to a staff at Hematite that reports to the Plant Manager. He may also request support from the Windsor, CT staff to provide functions that may include criticality analysis, production methods, nuclear licensing and others as needed. 2.1.3 Manaaer. Nuclear licensino. Safety and Accountab'lity l I The Manager, Nuclear Licensing, Safety and Accountability reports to the Plant Manager. He manages radiological protection and industrial safety, SNM accountability, criticality safety, licensing, emergency planning, and environmental protection. His activities include review and approval of procedures for control, i sampling, measurement and physical inventory of SNM, auditing of plant operations and evaluation of results from personnel and j environmental monitoring. He compares quantitative measurements and other observations of facility activities with the requirements of License No. SNM-33. To enforce compliance, he has authority to halt any operation at the Hematite facility, and the operation shall not restart until approved by the Plant Manager or a duly authorized alternate, t 2.1.4 Suoerintendent. Production The Superintendent of Production reports to the Plant Manager. The l Superintendent directs production operations in accordance with the content of Operation Sheets and Traveler documents. The Superintendent's activities may include review and approval of Operation Sheets and Travelers, scheduling of production Shift Supervisors and of the activities of the Maintenance Supervisor, recommending improvements to equipment, processes and procedures, 1 License No SNM-33, Docket 70-36 Revision: 1 Date: 11/14/89 Page: I.2-2

I l i j 2.1.4 Superintendent. production (Continued) training and qualification of production operators through their Shift Supervisors and periodically directing the cleanout of the produgtion equipment in conjunction with the physical SNM inventory. 2.1.5 Manaaer. Enaineerina The Manager, Engineering reports to the Plant Manager. He manages the engineering of new equipment and of modifications to existing equipment. With support from his staff, his activities may include recommendation, development and qualification of manufacturing processes, specification of process control methods, design, procurement and installation of processing equipment, preparation, review and/or approval of Travelers, Operation Sheets and Data Logs, and providing assistance in developing procedures for material control and inventory and in developing methods and equipment for sampling. 2.1.6 Nuclear Criticality Soecialist The Nuclear Criticality Specialist is located at Windsor, CT. He reports functionally for criticality evaluations to the Plant Manager at Hematite. The Nuclear Criticality Specialist verifies that equipment, processes and procedures satisfy the criticality criteria in Section 4 of Part I by performing the review described in Section 2.6 of Part I. Alternatively, for criticality analyses that require elaborate computational techniques, he may supervise the analysis and review at Windsor. He may also perform the annual audit at Hematite required by Section 2.7. License No. SNM-33, Docket 70-36 Revision: 3 Date: 11/14/89 Page: 1.2-3

a 7-j js i 2.1.7 Sunervisor. Health Physics The supervisor of Health Physics reports to the Manager of Nuclear 2 Licensing, Safety and Accountability. He supervises the health physics technicians in the radiological surveillance of activities f that involve radioactive materials, in personnel radiation monitoring and in the collection and measurements of environmental i samples. He may initiate, for approval by his manager, Travelers I and Operation Sheets for non routine activities involving radioactive materials and may suspend unsafe operations. 2.1.8 Senior Health Physics Technicians The Senior Health Physics Technicians report to the Supervisor, Health Physics. The Technicians are responsible for the day to-day monitoring of operations. Monitoring is accomplished through the collection of data which allows the effectiveness of radiological, criticality and industrial safety, environmental protection and emergency planning programs to be assessed.- Technicians also monitor the proper implementation of radiation work permits (called Special Evaluation Travelers). 2.2 Personnel Education and Experience Recutrements [ I Table 1.21 lists the minimum education and experience requirements for the positions described in Section 1.2.1. License No. SNM-33, Docket 70-36 Revision: 1 Date: 11/14/89 Fage: 1.2-4

l l- [ 5 2.3 Hamatite Plant Safety Comittee The Hematite Plant Safety Comittee meets at least once each calendar quarter to review plant operations, to compare them with the safety requirements of Part I and the License Conditions and,to . consider other aspects of safety the Committee believes appropriate. The Committee chairman or Plant Manager determines which committee members, as a minimum, shall attend each quarterly meeting, according to the topics to be considered. The Committee submits a quarterly meeting report to the Hematite manager level personnel and i to the Vice President and General Manager, Nuclear Fuel Manufacturing at Windsor. The Plant Manager appoints the committee members to represent, as a minimum, engineering, production, health i physics, and criticality safety. He also approves alternates for l the members, f.ach member shall have at least five (5) years experience in the nuclear industry. The health physics and criticality safety member (s) shall have, as a minimum, the education and experience requirements of the NLS&A Manager and the Nuclear [ Criticality Specialist, respectively. The Committee Chairman or Plant Manager may invite participation by others from within l Hematite or from the staff at Windsor. { 2.4' ADoroval Authority for Personnel Selection Two higher levels of management shall approve personnel for safety-related staff positions. 2.5 Trainina i Hematite staff conduct or supervise the indoctrination of new employees in the safety aspects of the facility. The indoctrination topics shall include nuclear criticality safety, fundamentals of radiation and radioactivity, contamination control, ALARA practices and emergency procedures. After test results License No. SNM-33, Docket 70-36 Revision: 2 Date: 11/14/89 Page: 1.2-5

L l j 2.5 Trainina (Continued) demonstrate that a new employee has sufficient knowledge in the above topics, the new employee begins on-the-job training under i direct line supervision and/or experienced personnel. The Supervisor monitors performance until it is adequate to permit work l t without close supervision. The training and personnel safety program continues with on-the job training supplemented by regularly scheduled meetings conducted by line supervision and specialists in the subjects covered. Topics include personnel protective equipment, industrial safety and-accident prevention, and other safety topics. Production Supervisors receive formal training in radiation and criticality control. Testing detennines when they have sufficient knowledge to enable them to carry out their training functions. Operating personnel. receive a re-training course in criticality control and radiation safety on a biennial basis. The effectiveness of retraining is determined by testing. Formal training shall be documented. 2.6 Ooeratino Procedures Operating procedures, called Operation Sheets, are issued and controlled by Quality Control. They provide the detailed instructions for equipment operation and material handling and the limits and controls required by the License. Operation Sheets are the basic control document; before issuance or revision they receive approval by signature of the cognizant manager or his designated alternate. l License No. SNM 33, Docket 70-36 Revision: 2 Date: 11/14/89 ll Page: 1.2-6 l 1

s .4 l-2.6 Doeratina Procedures (Continued) f i Supervision is required to assure that handling, processing, f storing, and shipping of nuclear materials is given prior review and approval by the NLS&A Manager or his designated alternate, that, suitable control measures are prescribed, and that pertinent control procedures relative to nuclear criticality safety and radiological safety are followed. i Primary responsibility and authority to suspend unsafe operations is placed with Operating Supervision. Within their respective responsibilities, members of NLS&A also have authority to suspend operations not being performed in accordance with approved procedure. l Supervision is further required to assure that, prior to the start of a new activity involving nuclear materials, approved procedures are available. A review procedure has bean established for changes ~ in processes, equipment and/or facilities prior to implementation. NLSLA authorization must be obtained for each change involving nuclear safety, radiological safety or industrial safety. NLS&A reviews shall be documented, except for minor changes within existing safety parameters. The NLS&A Manager or his designated alternate shall grant approval only when: l l a. A nuclear criticality safety evaluation has been performed 4 l based on the criteria and standards of Chapters 3.0 and 4.0 by a person who meets the education and experience requirements for a Nuclear Criticality Specialist (who may be the NLSLA Manager). This evaluation shall be in sufficient detail to permit subsequent review. i . License No. SNM-33, Docket 70-36 Revision: 2 Date: 11/14/89 Page: I.2-7

1 'b i i 2.6 Doeratina ProcedEt1 (Continued) j i i b. The criticality safety evaluation has been reviewed by a person who has fulfilled the education and experience j requirements for a Nuclear Criticality Specialist for at least two years (who may be the NLSLA Manager). This review is based on the criteria and standards of Chapter j 4.0 and includes verification of each of the following: j 'l 1) assumptions 2) correct application of criteria of Section 4.0. 3) completeness and accuracy of the evaluation. J i 4) compliance with the double contingency criteria. c. The NLS&A Manager or his designated alternate has concluded that the operation can be conducted in accordance with applicable health physics and industrial-1 safety criteria. Review and verification shall include written approval by the reviewer. The minimum frequency for review, for the purpose of updating, of operating procedures involving Special Nuclear Materials shall be every two (2) years. Updating of operating procedures is the l-responsibility of the cognizant manager. 2.7 Audits and Inspections Audits and inspections shall be performed to determine if plant operations are conducted in accordance with applicable license conditions, C-E policies, and written procedures. Audits shall apply to safety-related and environmental programs. Qualified l l License No SNM-33, Docket 70-36 Revision: 1 Date: 11/14/89 Page: I.2-8 3

2.7 Audits and Insoections (Continued) personnel having no direct responsibility for the plant operation being audited shall be used to ensure unbiased and competent audits. Daily checks for safety-related problems are made by NLSLA technicians, who observe, note and make general observations in i addition to their other duties. Problems are normally corrected on { the spot by the Shift Supervisor. More significant problems are listed on the daily exception report distributed to the Plant Manager and manager level staff. The Superintendent, Production, is responsible for corrective action. Quarterly inspections, performed by an individual who meets the education and experience requirements of the NLS&A Manager, cover criticality control, radiation safety and industrial safety. The inspection of criticality control shall be performed by an individual meeting at least the education and experience requirements of a Nuclear Criticality Specialist and at least one of the quarterly inspections regarding criticality control will be by an individual who is not the NLSLA Manager. Items requiring corrective action are documented in a report distributed to the Plant Manager and manager level staff. The Superintendent, Production is responsible for corrective action, except where another manager is specifically designated. Follow up actions taken by the Superintendent, Production or responsible manager, shall be t documented. Documentation shall be maintained for at least the period stated in Section 2.9. O License No. SNH 33, Docket 70-36 Revision: 2 Date: 11/14/89 Page: 1.2-9

i 2.7 Audits and Inspections (Continued) l l t Annual audits are conducted in which the results of previous j inspections or audits are reviewed, as an evaluation of the j effectiveness of the program. These audits may also involve a l detailed review of non-safety documents such as' operation t procedures, shop travelers, etc., and are documented by a formal l report to the Vice President and General Manager, Nuclear Fuel Manufacturing. Annual audits are performed by a team appointed by I the Vice President and General Manager, Nuclear Fuel Manufacturing. l l The team shall include, as a minimum, a Nuclear Criticality l Specialist and a radiation specialist who shall audit criticality f and radiation safety. The annual audit will review ALARA l requirements in conformance with Regulatory Guide 8.10, as applicable. The NLS&A Manager shall be responsible for follow up of recommendations made by the audit team. 2.8 Investiaations and Reoortina Events specified by applicable regulations or license conditions shall be investigated and reported to NRC. The NLS&A Manager or his l designated representative shall be responsible for conducting the investigation and documentation of reportable events. Non-reportable occurrences shall be investigated and documented as appropriate and these reports shall be available for NRC inspection. 5 2.9 Records Retention of records required to be maintained by the regulations, and by the conditions of this license, shall be the responsibility of the cognizant manager. Records of tests, measurements, and l surveys identified as requiring preservation until the NRC authorizes disposition shall be retained indefinitely. Records of License No. SNM-33, Docket 70-36 Revision: 2 Date: 11/14/89 Page: I.2 10

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f 2.9 Records (Continued) NLS&A evaluations and approvals shall be retained for a period of at least six months after use of the operation has been terminated, or i for three years, whichever is longer. Other safety significant, records shall be retained for at least three years. i l' i i f I r License No. SNM-33, Docket 70-36 Revision: 1 Date: 11/14/89 Page: 1.2-11

l TABLE I.2-1 MINIMUM EDUCATION AND EXPERIENCE REQUIREMENTS FOR KEY PER50188EL i i Position Described In i Section No. Title Education Experience-(Years / Field) I.2.1.1 Vice President and General Bachelors, Science or 10 Total, 5/ Nuclear industry Manager, Nuclear Fuel Mfg. Engineering management 4 I.2.1.2 Plant Manager Bachelors, Science or 5/ Nuclear manufacturing Engineering I.2.1.3 Manager, NLS&A Bachelors, Science or 5/ Health Physics, with Engineering 2/ Operational health physics with uranium bioassay techniques, l internal exposure control, and radiation measurement techniques I.2.1.4 Superintendent, Production High School Diploma 10 Total / Nuclear industry, with 5/ nuclear fuel manufacturing including 3/ Production coordination I.2.1.5 Manager, Engineering Bachelors, Engineering 5/ Engineering design of process, systems or facilities 1 1.2.1.6 Nuclear Criticality Bachelors, Science or 2/ Nuclear criticality evaluations Specialist Engineering I.2.1.7 Supervisor, Health Physics High School Diploma 5 Total / Nuclear industry, with 3/ Senior Health Physics Technician 1.2.1.8 Senior Health Physics Tech. High School Diploma 2/ Training and experience in Radiation Protection aqtivities 4 License No. SNM-33, Docket 70-36 Revision: 0 Date: 11/14/89 Page; I.2-12

i 3.0 RADIATION PROTECTlQN l i 3.1 Administrative Reauireg ati 3.1.1 Radiation Work Permit Procedures Operations not covered by an effective operating procedure shall be conducted under a Special Evaluation Traveler (S.E.T.). Prepared by i the responsible function, it 1 hall contain detailed instructions for the procedure and shall include all safety requirements to assure that the proposed operation is conducted in a safe manner The same approvals as required for Operation Sheets shall be reo red on all j S.E.T.s. Completion of the operation shall be appropriately documented as indicated on the traveler. 3.1.2 ALARA Commitment I It is the policy of Combustion Engineering to maintain a safe r workplace and healthful work environment for each employee. It is also C E's policy to keep radiation exposures to both employees and the general public as low as reasonably achievable (ALARA). The annual audit team, described in Section 2.8 considers ALARA requirements in conformance with the intent of Regulatory Guide 8.10. 3.2 Technical Reauirements 3.2.1 Access Control The facility shall be zoned to define contamination areas and clear areas. Protective clothing shall be worn in the contamination areas. A sink and alpha survey meter or alpha monitor shall be provided at the exit from the contamination area. All personnel are required to wash and monitor their hands, and to monitor other body surfaces and personal clothing as appropriate, when exiting a contaminated area. Except for hand contamination which is easily removed on the first rewashing, health physics assistance and approval for release above background levels shall be required. License No. SNM 33, Docket 70 36 Revision: 2 Date: 11/14/89 Page: I 3-1

3.2.4 Internal and External Exposure 3.2.4.1 Snecial Surveys All non routine operations not covered by operating procedures shall be reviewed by NLSLA and a determination made by NLSLA if radiation safety monitoring is required. With the exception of incidents requiring immediate evacuation, spills or other accidental releases shall be cleaned up immediately. Criticality restrictions on the use of containers and water shall be followed at all times. The Shift Supervisor and NLS&A must be notified immediately of such incidents. Appropriate precautions such as use of respirators shall be observed. t 3.2.4.2 Routine Surveillance Surveys shall be conducted on a regularly scheduled basis consistent with plant operation and survey results. The frequency of survey depends upon the contamination levels common to the area, the extent 7 to which the area is occupied, and the probability of personnel exposures. The frequency for contamination surveys in plant l operating areas shall be as specified in Table 1 of Regulatory Guide 8.24, where applicable. Clear areas with high potential for tracking of contamination may be surveyed more frequently. Areas with a low use factor may be surveyed less frequently. j. Cleanup action for restricted areas shall be initiated when surface l contamination exceeds the action limits specified in Table 2 of l Regulatory Guide 8.24. l l License No. SNM 33, Docket 70 36 Revision: 2 Date: 11/14/89 i Pcge: 1.3 6 l

3.2.4.3 Air Samnlino Criteria I P Air sampling shall be performed using fixed location samplers, personal (lapel) samplers, and air monitors. 3 i The tipe of air sample collected at a specific operation or location j shall depend on the type, frequency, and duration of operations being performed. One or more of these sample methods shall be i employed at intervals prescribed by the NLS&A Manager. General criteria for sampling are: a. Fixed location samplers shall be used where uranium handling i operations are pursued for extended periods of time, or where short term operations occur frequently. These samplers shall l be located in or as near as practical to the breathing zone of j the person performing the operations. Fixed sampling may also be used for investigative purposes. In this case, the samples may be collected near the point of suspected release of material. b. Lapel samplers may be used where work stations are not defined or for supportive measurements and special studies. Continuous air monitors may be used for early warning of unexpected releases. c. Emphasis shall be placed on sampling new operations or i processes until adequate, effective, control of airborne i contamination is assured. i l l l' j l. 1 License No. SNM 33, Docket 70 36 Revision: 2 Date: 11/14/89 Page: 1.3 8

l i 4.0 NUCLEAR CRITICALITY SAFETY i 4.1 Administrative Reauirements 4.1.1 Double Continoency Poliev Process Designs shall, in general, incorporate sufficient factors of safety to require at least two unlikely, independent, and concurrent i changes in precess conditions before a criticality accident is

possible, t

4.1.2 Criticality Safety Review i L Final design, initial installation, modification, or relocation, of i special nuclear material processing, handling or storage equipment, or related operations, shall be reviewed and approved by the NLS&A Manager. Such changes as could effect nuclear criticality safety shall be reviewed prior to implementation according to the review l and approval procedure described in Section 2.6 of this part. 4.1.3 Postino of limits Signs listing approved nuclear criticality safety limits shall be posted such that information thereon is readily discernible to employees. This posting may be for individual pieces of equipment or groups of equipment, depending on the nature of the operations covered. License No. SNM-33, Docket 70-36 Revision: 2 Date: 11/14/89 Page: 1.4-1

l j 3.0 QRGANIZATION AND PERSONNEL i I Section I.2.1 describes the key positions important to safety and the line of authority to top management. Section 1.2.2 lists the j education and training requirements for those positions. The following Section 11.3.1 similarly describes additional positions of I the organization. Section !!.3.2 gives the resumes for personnel i currently holding the key positions described in Part I. 3.1 Oraanizational Responsibilities Figure II.3-1 is the Hematite plant organization chart. The following sections describe some of the supervisory and higher level positions shown in Figure 11.3-1 that are not included in Section I.2.1. 3.1.1 Manaaer. Administration and Production Control The Manager, Administration and Production Control reports to the Plant Manager. He manages the control of SNM from receipt at the i Hematite facility, through the production process until it is shipped as product or waste. His activities include scheduling of production, selection of SNM for use in the production process, specification of the product lot makeup, scheduling of SNM shipments from the supplier to Hematite and from Hematite to the customer, coordination of the packaging and shipment of SNM waste and residues to a commercial, licensed disposal facility and development of procedures for packaging, shipping and receiving. He also performs facility administration duties includ;ng the supervision of the guards, site purchasing and personnel services. License No. SNM-33, Docket 70-36 Revision: 1 Date: 11/14/89 Page: 11.3-1

a i 3 3.1.2 Manaaer. Quality Control The Manager, Quality Control reports to the Plant Manager. He manages the measurement activities which verify that the product conforms to specification. These activities may include development of the Operation Sheets that are the procedures for acquisition 6f product data, approval of laboratory measurement methods, approval of statistical methodology for data evaluation and establishment of the system for control and distribution of data documentation. The manager maintains separation between his measurement activities and the production activities that he monitors. He has authority to halt production and it shall not restart until approved by the Plant Manager or a duly authorized alternate. 3.1.3 Coordinator of Nuclear Materials Accountability The Coordinator of Nuclear Materials Accountability reports to the Manager of Nuclear Licensing, Safety and Accountability. He maintains the SNM accounting records, prepares NRC required reports i on material balance, transfer and inventory, periodically verifies current knowledge of the presence of SNM and computes Inventory Differences. l t 3.1.4 Supervisor. Material Control l The Supervisor, Material Control reports to the Manager, Administration and Production Control. He implements the production l schedules provided by the Manager through supervision of the production clerk, the material control operators and the material handlers. He monitors the sequence of steps in the processing and handling of each material unit including the proper use of the Traveler that documents each process step. License No. SNM-33, Docket 70 36 Revision: 1 Date: 11/14/89 Page: 11.3-2

3.1.5 Sunervisor. Quality Control Enoineerino l The Supervisor, Quality Control Engineering reports to the Manager, Quality Control. He superv$ses the quality control technicians who l obtain the measurement samples and he supports the activities of the Manager. His support may include recommendations on sampling plans, j development of statistical methods, evaluation of data trends, recommendations on measurement standards, participation in writing procedures, review and approval of Travelers and Operation Sheets i and administration of the document control system. 3.1.6 Suoervisor. Laboratory The Laboratory Supervisor reports to the Manager, Quality Control. He supervises and trains the laboratory technicians, recommends sampling procedures, establishes laboratory methods and reviews and approves all chemical measurements on SNN. He also selects subcontractors and qualifies and coordinates their measurement services. t 3.1.7 l y rvisor. Maintenance r The Supervisor, Maintenance reports to the Superintendent, Production. He supervises technicians in the maintenance activities related to the facility and the production equipment within the constraints of applicable radiation and industrial safety practice. 3.2 Resumds of Personnel. Resumes of key personnel important to safety are provided in this section for the following personnel: C. R. Waterman - Vice President and General Manager, Nuclear Fuel Manufacturing (located in Windsor) J. A. Rode - Plant Manager License No. SNM-33, Docket 70-36 Revision: 1 Date: 11/14/89 Page: 11.3 3 e,---- vw -

t 17 3.2 Resunds of Personnel (Continued) q R. J. Klotz - Nuclear Criticality Specialist (located in Windsor) f H. E. Eskridge - Manager, Nuclear Licensing, Safety, and Accountability i i A. J. Noack - Superintendent, Production f R. W. Griscom - Manager, Engineering C. W. Proctor - Supervisor, Health Physics i l i 6 License No. SNM-33, Docket 70-36 Revision: 1 Late: 11/14/89 Page: 11.3-4

i. l o c i I CHARLES R. WATERMAN - VICE PRESIDENT AND GENERAL MANAGER, NUCLEAR FUEL MANUFACTURING EDUCATION 4 i B. S. Electrical Engineering, Tri-State College,1957 i EXPERIENCE l COM8USTION ENGINEERING, INC. Windsor, Connecticut [ Vice President and General Manaaer. 1989 to Present i Nuclear Fuel Manufacturina [ Overall responsibility for the safe operation of Combustion Engineering's nuclear fuel manufacturing facilities located in Hematite, Missouri and in { Windsor, Connecticut. Continuing responsibility as the Plant Manager for the l Windsor Nuclear Fuel Manufacturing facility, r Plant Manaaer. 1988 to Jan. 1989-i Windsor Nuclear Fuel Manufacturina Responsible for day-to-day manufacturing operations, accountability, security, nuclear criticality safety and radiological safety related. to all special nuclear and source material received by Windsor Nuclear Fuel Manufacturing and l used in any manufacturing process. Assured compliance with Federal and State and local regulations and the requirements and limitations set forth in facility license SNM-1067. j Director. Outaae Services 1986 to 1988 i Responsible for management of outage services, for development test and application of maintenance and inspection services provided to nuclear utilities. These services included integrated refueling and maintenance License No. SNM-33, Docket 70-36 Revision: 1 Date: 11/14/89 Page: 11.3-5 I .. _.,,. ~.

i CHARLES R. WATERMAN (continued) outages, fuel services, major plant retrofits, full steam generator services using advanced remote controlled devices designed and built by outage services. Responsible for all aspects of compliance with Windsor facility NRC by product license. Responsible for the operation of Amdata, Inc., a wholly owned subsidiary of CE. Amdata designs and manufactures advanced ultrasonic imaging equipment and inspection services for the Nuclear, Oil and Gas and Aerospace industries, j i President / General Manaaer 1985 to 1986 CE/Delas Weir. Inc. Responsible for strategic direction of this joint venture company as well as day-to-day operations. CE/Delas Weir provided new and replacement heat exchanger equipment to Electric Utilities. ENGINEERING PLANNING AND MANAGEMENT CO. 1984 to 1985 President and CEO Responsible for strategic direction and day to-day operations. EPM supplied i engineering services to the Nuclear Utility Industry and Maintenance Management Software Programs to the Food and Pharmaceutical Industries. l SENSOR ENGINEERING COMPANY 1981 to 1984 DIVISION OF ECHLIN. INC. l President Responsible for strategic direction and day-to-day operations for a high-tech manufacturing company of magnetic devices for use in security, automotive and industrial control systems. l License No. SNM-33, Docket 70-36 Revision: 1 Date: 11/14/89 Page: 11.3-6

] CliARLES R. WATERMAN (contirued) I ELECTRO MECHANICS, INC. 1977 to 1981 Etesident and Chairman of the Board Responsible for strategic direction and day-to-day operations for a manufacturer of custom electronic control systems for the Electric Utility and Commercial Industries. COMBUSTION ENGINEERING, INC. 1965 to 1977-Q1tector. Plant Acoaratici 1975 to 1977 Responsible for technical specification and procurement of all NSSS mechanical hardware. Established the organization and QA Manual for CE's Engineering "N" stamp. c 1 l i Project Manaaer. Boston Edison 1972 to 1975 Nuclear Reactor Project Responsible for representing Combustion Engineering with Boston Edison and all governmental agencies in matters relating to con _ tracts, licensing, design, fabrication schedules, erection, startup and acceptance of the nuclear steam u supply systems and associated fuel. Authorized all work to be done on the 1 project. Reviewed, evaluated, and approved a'11 technical work on the projec', l including purchase orders, purchase order supplements, drawings, and specifications, i Assistant Pro.iect Manaaer. 1970 to 1972 l Maine Yankee Nuclear Reactor Proiect L Assisted the Project Manager in the direction of technical and administrative l activities. l License No. SNM-33, Docket 70-36 Revision: 1 Date: 11/14/89 Page: 11.3-7 3

..s,- 1 i CHARLESR. WATERMAN (continued) General Manaaer. Naval Reactor Division 1968 to 1970 Overall responsibility for the operations of the SIC land-based submarine prototype facility under contract between CE and the U.S. Atomic Energy Commission. Operations Manaaer. 1967 to 1968 Naval Reactors Division Responsible for operation-and maintenance of the SIC prototype and support facilities. Responsiblities included the approval and implementation of schedules for operation testing, training, maintenance, plant modifications - 5 and for the' control and forecast of department budgets. L Assistant Operations Manaaer. 1965 to 1967 Trainina Manaaer. Naval Reactor Division l Responsible for training SIC prototype operating personnel including coordination of Naval and Division personnel. CONNECTICUT YANKEE ATOMIC POWER COMPANY 1964 to 1965 Nuclear Enaineer l l In training as Assistant Plant Superintendent. COMBUSTION ENGINEERING, INC. 1959 to 1964 Senior Shift Suoervisor. Naval Reactors Division Responsible for the safe and efficient operation of the SIC prototype. 9 Electrical design engineer responsible for the evaluation of electrical and electronic systems and equipment. License No. SNM-33, Docket 70-36 Revision: 1 Date: 11/14/89 Page: 11.3-8

., i s, [, f i 9 f CHARLES R._ WATERMAN (continued)- i 2 ELECTRIC BOAT DIVISION, 1959 3 GENERAL DYNAMICS CORPORATION Test Director 4 Test l Director on the Nuclear Submarine USS (BN) George Washington for. . preoperational and ' operational tests. COMBUSTION ENGINEERING, INC. 1957 to 1959 Electrical Control Enaineer. Reactor Develooment Division ~ Reactor analysis for the SIC /S2C reactor plants. L t L License No. SNM-33, Docket 70-36 Revision: 1 Date: 11/14/89 Page: II.3-9

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^^ t c 1 JAMES A. RODE LPLANT MANAGER, HEMATITE f EDUCATIQH: B.S.~,' Chemical Engineering, University of Texas, 1953 EXPERIENCE:. t COMBUSTION ENGINEERING, INC. 1974 to Present Plant Manaaer. Nuclear Fuel Manufacturino. Hematite i f Responsible for all Nuclear Fuel Manufasturing activities at the Hematite = l Plant. Manages Engineering, Production and Materials Control, Manufacturing, { Nuclear and Industrial Safety, Nuclear Material Management, and Quality ~ Control. GULF UNITED NUCLEAR FUELS CORPORATION 1968 to 1974' Technical Consultant i Respon'sible fhr establishing process flow sheets and capacities for production ' of UO, U02 pellets, and uranium recovery; and coordinating development 2 activities. Also responsible for preparation of stable density pellets 'and ~ development of process modifications. Technical Assistant to the Manager of Chemicals Operations on major operational. problems. r i License No. SNM-33, Docket 70-36 Revision: 1 Date: 11/14/89 Page: 11.3-10 - -i.

. c.,,- -JAMES A. RODE (continued) UNITED NUCLEAR CORPORATION Manaaer of Facilities Develooment and Technical Director 1964 to 1968 Responsible for design, construction and startup of the first large scale ' fluidized-bed process for the production of UO fr m UF and of companion 2 6 facilities for converting oxide to pellets. Responsible as Technical Director for Chemicals Operations for process engineerins supervision and development activities including design, construction, and operations of a pilot plant for preparation of UO via the 2 reaction of UF and steam and for development, design,-construction and 6 startup of a fluid-bed vapor phase coating system. Assistant Technical Director 1962 to 1964 Responsible for process and equipment design in the Rhode Island Scrap Recovery Facility, development work on process for producing pyrolytic carbon coated U0, and for continuing development work in Naval Fuel Program. 2 1 Pro.iect Leader 1961 to 1962 Assumed total responsibility for salvaging a non-operative Naval Fuels Plant including production, quality control, development and customer contacts. The facility was converted into.the primary source of profits for the Chemical Operations. l l License No. SNM-33, Docket 70-36 Revision: 1 Date: 11/14/89 Page: 1I.3 11

1 1 E JAMES A. RODE (continued) MALLINCKRODT CHEMICAL WORKS Group Leader and Production Superintendent 1958 to 1961 Responsible for the startup of high enrichment metal production and development and startup of the Hematite Pellet Plant.- Responsible as Production Superintendent for detailed supervision of production in Doth high and low enrichment conversion operations. Process Enaineer and Research Chemist 1953 to 1958 Participated in preparation of proposals for production of yttrium metal and conversion of 5000 tons per year of UF. Responsible for operation of the 6 first ADU pilot plant and startup of the Hematite Oxide Plant. i l l 1 l i License No. SNM-33, Docket 70-38 Revision: 1 Date: 11/14/89 Page: 11.3-12

ROBERT J. KLOTZ - NUCLEAR CRITICALITY SPECIALIST EDUCATION Graduate, Oak Ridge School of Reactor Technology,1957. M.S. Physics, Kansas State College, 1954 A.B. Physics and Mathematics, Kansas State Teachers College of.Emporta, 1952. Graduate Studies, Texas Christian University 4 EXPERIENCE COMBUSTION ENGINEERING, INC. 965 to Present Windsor, Connecticut Senior Consultina Physicist 1977 to Present Responsible for the physics design of new and spent fuel racks, fuel transfer machines, and other equipment involved in moving, testing or storing fuel. Nuclear Criticality Specialist provide technical support and criticality audit function at both the Windsor Manufacturing and Hematite Fuel Manufacturing facilities. Involved in solving special physics problems. Section Manaaer. Radiation and 1965 to 1977 Criticality Physics Responsible for radiation shielding, the ex-core criticality, and l l-determination of source terms for Nuclear Steam Supply Systems. Also for providing nuclear heat generation rates for structures in the NSSS, and radiation dose rates for assessing physical changes in NSSS materials and ~ L equipment in the radiation environment. l License No. SNM-33, Docket 70-36 Revision: 2 Date: 11/14/89 Page: 11.3-13

m 7 7, - I ROBERT J. KLOTZ (continued) GENERAL NUCLEAR ENGINEERING CORPORATION -Physicist 1959 to 1965 Responsible for the shield design of the heavy water research' reactor at the Georgia Institute of Technology and the thermal and biological shield design analysis for the Boiling Nuclear Superheat Reactor (BONUS) located in Rincon, Puerto Rico. Reviewed all. the literature on radiation shielding for the publication Power Reactor Technoloav. CONVAIR DIVISION 0F GENERAL DYNAMICS Physicist 1954 to 1959 i Responsible for.the design of a shield for a mobile reactor of the Army Compact Core Design and for a Nuclear Ramjet Missile. Performed analysis of 1 aircraft nuclear shielding experiments, developed shielding programs for computers, and contributed to the Aircraft Shield Design Manual. L l i ) l l License No. SNM-33, Docket 70-36 Revision: 2 Date: 11/14/89 Page: 11.3-14

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j HAROLD E.'ESKRIDGE - MANAGER, NUCLEAR LICENSING,' SAFETY AND ACCOUNTABILITY ~ EDUCATION: y B.S., Physics, tiorth Carolina State University,1961 l M.S.. Physics. North Carolina State University, 1963 i m EXPERIENCE: t COMBUSTION ENGINEERING, INC. Manaaer. Nuclear'Licensina. Safety and Accountability 1989 to Present j --Hematite Suoervisor, Nuclear Licensing, Safety and 1974 to 1989 . Accountability - Hematite -Responsible for licensing, safety, and safeguards at Nuclear Fuel' ~ Manufacturing -. Hematite-Develops-and-implements the health physics, l criticality and _ industrial safety, and accountability programs-for-the Hematite. facility. Audits manufacturing operations and supervises-safety and safeguards personnel in day-to-day operations. I GENERAL ELECTRIC COMPANY 1972 to 1974 Nuclear Safety Enaineer L.. l Analyzed chani.is and specified requirements for Wilmington nuclear fuel l 1 manufacturing to assure compliance. Audited manufacturing operations and l radiat' ion protection programs. Planned and conducted development programs in L dosimetry, radiation monitoring and environmental sampling. 'i Y 1 h License No. SNM-33, Decket 70-36 Revision: 1 Date: 11/14/89 l Page: 11.3-15 e

3 --,. - ( r 'HAROLDE..ESKRIDGE(continued). - l SALISBURY METAL PRODUCTS COMPANY 1971 TO 1972 Co-Manaaer Managed operations for manufacturer of precision components; including salis, finance, production control and quality assurance. Consultant to Institute for Resources Management on decontamination and radioactive waste disposal projects and a member of Rowan Technical Institute Advisory Committee. EVIRON0NICS, INC. 1970 to 1971 Vice President - Nuclear Acolications Performed variety of functions, including market research, proposal preparation and technical analyses relating to remote sensing, environmental surveys, and health physics services. Contacted potential customers, including. government agencies and utility companies with power reactors. 'EG&G, INC. 1967 to 1970 Senior Scientist and Scientific Executive Head, Radiological Sciences Section and Senior Health Physicist, responsible for radiation and nuclear safety and regulatory compliance for Las Vegas Operations. Provided technical direction for Nuclear Counting Laboratory, Nevada Aerial Tracking System, and Aerial Radiation Measuring Surveys Programs. Acting Manager, Environmental Measurements Department, which included High Energy Neutron Reactions Experiment and Metrology Sections. License No. SNM-33, Docket 70-36 Revision: 1 Date: 11/14/89 Page: 11.3-16

r HAROLD E. ESKRIDGE (continued) . NORTH CAROLINA STATE BOARD OF HEALTH 1962 to 1967 Public Health Physicist Technical, policy, and procedural consultation in all aspects of health' physics, environmental surveillance and radiological health. Functioned as administrator of Radioactive Materials Licensing and Regulation. Served as Team Chief of State Radiological Emergency Team and established and equipped a laboratory for radiological and chemical analysis of environmental samples. U.S. AIR FORCE -1954 to 1957 Nuclear Soecialist~ Responsible for criticality and radiological safaty for nuclear weapon systems and components. Also was an instructor in nuclear safety and weapons systems. 1 License No. SNM-33, Docket 70-36 Revision: 1 Date: 11/14/89 Page: 11.3-17

[*. m p .p 0 1 .j ] l -{ ARLON'J.' NOACK - PRODUCTION SUPERINTENDENT, HEMATITE EDUCATION:. Hillsboro High School,- 1961 Graduate EXPERIENCE: s . COMBUSTION ENGINEERING, INC. Production' Superintendent - Hematite 1981 to Present Responsible for_ production' and maintenance operations, operator and 4 maintenance training manpower scheduling, interviewing and hiring operating personnel, handling. Union grievances, and' training new production and maintenance supervisors.- ' Maintenance Suoervisor - Hematite 1980 to 1981 Responsible for the maintenance of-production equipment, building and grounds maintenance, ordering' repair parts, and porter service. Production Suoervisor-- Hematite 1974 to=1980 Shift Supervisor in charge of production operations, dealing with Union L problems, operator training, and scheduling-production to assure fulfillment of customer. schedule requirements. ( i l 1 License No. SNM-33, Docket 70-36 Revision: 1 Date: 11/14/89 l Page: 11.3-18 p

'4 I ARLON J. NOACK (continued) GULF UNITED NUCLEAR FUELS CORPORATION Production Suoervisor - Hematite 1970 to 1974 Production Supervisor in charge of production operations, dealing with Union problems, operator training, and scheduling production to fulfill customer schedule requirements. Enoineerino Technician - Hematite 1969 to 1970 Responsible for production engineering functions as assigned by the Procoss Engineer, some drafting responsibilities, and Engineering technical assistance. UNITED NUCLEAR CORPORATION 1966 to 1969-Process Develooment Technician - Hematite Participated in development of. Uranium 0xide Conversion Plant, such as operating and repairing development equipment, and assisting in the i development of new operating techniques. LUDLOW SAYLOR WIRE CLOTH COMPANY 1963 to-1966-Production Operator - St. Louis Operated wire screen loom, wire stretcher, and punch press. [ l HOWARD INDUSTRIES COMPANY 1962 to 1963 L Junior Draftsman - Festus Responsible for drawing changes, drawing minor equipment, and document control of production drawings. I License No. SNM-33, Docket 70-36 Revision: 1 Date: 11/14/89 Page: 11.3-19

h ~ ] ca g<. y ":/ - .e;-- ROBERT W. GRISCOM - MANAGER, ENGINEERING, HEMATITE EDUCATION: , B.S;, Chemical. Engineering, Georgia Institute of Technology,1969 Co-op M.S.C.E.-Sanitary, University of Missouri-Rolla,1974. s EXPERIENCE: 1 COMBUSTION: ENGINEERING,-INC.. 1981 to Present MAiaaer. Enaineerina - Hematite 1989 to Present-Enaineerina Suoervisor - Hematite 1981-to 1989 i .e 1 esponsible for managing. Engineering Department. Activities including process R engineering,; plant expansion' design and management, drafting, instrument maintenance, and staff assistance to other plant departments. s NATIONAL STEEL ENGINEERS & ASSOCIATES 1977 to 1981 ( Pro.iect Manaaer - St. Louis Project'Managerincorporateenvironmentalconsuliinggroup. Directly responsible for engineering, fabrication, and installation of multi-million dollar. air pollution control and wastewater treatment systems for major steet companies. L L 1 ? License No. SNM-33, Docket 70-36 Revision: 0 Date: 11/14/89 L Page: II.3-20

I e/ o.'. t 7 ROBERT W. GRISCOM (continued) ROCKWELL INTERNAT.ONAL 1974 to 1977 Senior Test Enaineer - St.-Louis Responsible for establishing and gathering an hourly emission inventory for EPS sponsored St. Louis Regional Air Pollution Study-(RAPS). Also supervised and performed stack sampling in St. Louis and New Mexico. MONSANTO COMPANY 1969 to 1974 Process Enaineer - St. Louis Rasponsible for process and cost improvements in various chemical production departments. Designed and installed a wastewater treatment system for removing phenolics. I 1 e

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i L L 's 1 l l l l l l l-l l l l License No. SNM-33, Docket 70-36 Revision: 0 Date: 11/14/89 Page: 17.,3-21 l

{ >; , 0 9 j C. W. PROCTOR, JR. - SUPERVISOR, HEALTH PHYSICS g EDUCATION: 4 B.S., Biology, Centenary College,1966 M.S., Entomology, University of Georgia, 1970 Nuclear Engineering Graduate Studies, Univ. of Cincinnati,1976 M.S., Engineering Management, University of Missouri, Rolla,1983 EXPERIENC1: COMBUSTION ENGINEERING, INC., HEMATITE 1989 to Present Suoervisor. Health Physisi Responsible for the daily operations management of the health physics department and staff at Nuclear Fuel Manufacturing - Hematite. Implements health physics and industrial safety program through training, supervision, and daily audit. Develops and revises departmental operations procedures and emergency plan ir,Umenting procedures. IMPELL CORPORATION-1988 Lead Senior Enaineer Worked with a team which designed and installed 18,000 permanent signs on the process piping at the Zion nuclear power station. Managed the development of off-site emergency plan implementing procedures for Duane Arnold nuclear power plant. UNITED ENERGY SERVICES, INC., 1987 to 1988 Nuclear Consultant Performed pre-INP0 mini-audit of health physics procedures for Waterford 3 nuclear power plant. License No. SNM-33, Docket 70-36 Revision: 0 Date: 11/14/89 Page: II.3-22

w r ~. a. gr. CHARLES W. PROCTOR, JR. (continued) Developed emergency response lesson plans for Rancho Seco.. Trained the~ plant' staff in nuclear emergency response procedures. Audited control room and management response to emergency drills. GENERAL TECHNICAL SERVICES-(GENERAL PHYSICS) 1986 to 1987. ? Nuclear Instructor Taught radiation protection, industrial safety, and nuclear emergency response at Votgle Plant. Developed on-site nuclear emergency implementing procedures. NUTECH ENGINEERS, INC. 1986 Consultant Wrote on-site nuclear emergency implementing procedures for Davis Besse nuclear power plant. . UNION ELECTRIC COMPANY 1976 to 1986 Supervisor. Nuclear Information Conceived and executed a nuclear public~ information and education program including technical lab presentations on nuclear radiation and radioisotope decay to physics and chemistry classes._ UNIVERSITY OF CINCINNATI, DEPT. OF CHEMICAL 1974 to 1976 & NUCLEAR ENGINEERING Administrator and Sookesman Studied energy and nuclear issues at Oak Ridge Associated Universities. Made informational and technical lab presentations on these issues. License No._SNM-33, Docket 70-36 Revision: 0 Date: 11/14/89 Page: 11.3-23

_A': qb: A-' p' %.:*J 9 b e e L:e .) 4. CHARLES W. PROCTOR, JR. (continued): DAMES & MOORE, CONSULTANTS 1971 to 1973 . Environmentalist l ' Analysis and' characterization of terrestrial ecosystems including _ f - environmental site characterizations-of nuclear power plants. t 1. l-t t l' s 4 ? i; L H 1 License No. SNM-33, Docket 70-36 Revision: 0 Date: 11/14/89 Page: 11.3-24 H l -. n-

'}' ~ SJ ;/ ';:l ~ Of. ~ ~ 3 ,. z: *s_h ' -43 Proskient 4 Nuclear Power. Businesses l (Brewer) Vim President Nuclear Fuel l 01c6Ho Vtos Preset and - General Menaar Nuclear Fuel Mfg l (weterman) Plant Honopr Hematite I (m ee) i I I I I I tierv. Manager. Aenintstration Superintendent, Nenager. fosciese Criticality EngineerM and Proeuction Proestion tienseer. ~ Osehty Controi Spuistist NLSLA c..aroi tefigcwa I (niller) tM (Eskridid grown) suetz) Prue ue Se. s e c m ar. co-crenetori s. or m er. ? nenoruturm notoriei centroi tie = terme Acct m.cieer aanty centrei Engineers f1sterials Engwring i cift* # ws SN-I' ~ instwnentetm a Souwnst., Health Physics Laboratory l < proctor) Technicians. neelth Physts (Staff)

• Wasser Besee Seppart Positten FIGURE'II.3-1 HEMATITE PLANT ORGANIZATION CHART License No. SNM-33, Docket 70-36 Revision.

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