ML20246E929
| ML20246E929 | |
| Person / Time | |
|---|---|
| Site: | Framatome ANP Richland |
| Issue date: | 06/14/1989 |
| From: | Malody C SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER |
| To: | Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 25662, CWM:89:051, CWM:89:51, NUDOCS 8907130055 | |
| Download: ML20246E929 (87) | |
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' ADVANCED NUCLEAR FUELS CORPORATION AFETY, SECMTY AND UCENSING flll"",'jg % asam nwg m m w30 s
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- u. s-Uk cce Attention: Mr. L..C. Rouse, Chief comus$[agurony C c
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Washington, DC 20555 3
Dear Mr. Rouse:
Advanced Nuclear Fuels Corporation (ANF) hereby requests that License No.
SNM-1227 be amended to accommodate a change in functional organizational structure, and to further clarify the contamination limits for reuse of laundered clothing.
This Application is of significant,. physical size for four reasons.
License page revisions have resulted because:
- 1) the organization description-or responsibilities have changed; 2) title change only with no change in responsibility, 3) change in length of a preceding page caused by 1) or 2) above have forced succeeding pages to be changed; and 4) a change in word processors and printers since the origina'l license was printed caused some shifting.
Upon the retirement of the Vice President, Engineering and Production, that division was divided into two divisions, Operations and Engineering, with a Vice President appointed to head each.
In addition, Corporate Licensing'and Safety and Security sections were combined (Safety, Security, and Licensing),
and the newly formed unit was elevated to Department level, reporting directly to the Vice President, Operations Division.
Your attention is directed to Chapter 2 which describes the new organization in some detail, including functional diagrams displayed in Figures 1-2.1 and I-2.2, and the Approval and Responsibility Matrix displayed in Figure I-2.3.
Chapter 4 describes the impact of the combination of Corporate Licenisng and Safety and Secuirty on criticality safety administration.
We have included Part II, Chapter 11 which is of interest in that it contains the rdsumds of employees new to certain safety-related positions.
Other pages in Part II are being updated to reflect the new organization, and
'will be issued upon approval of this Application.
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4-i Mr. L. C. Rouse CWM:89:051 June 14, 1989 Page 2 Amendment No. 3 (to the referenced License), dated March 8,
- 1989, modified the contamination limits on cloth protective clothing to specify that the limit pertained to removable alpha contamination only.
Inadvertently, rubber shoecovers remains in the License, but under a different limit, and the limit is not specific removable alpha.
Item 3.2.6.3(1)(c) on page 3-9 has been modified to bring all protective clothing (rubber, cloth, or plastic)
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under the same limit following laundry, and prior to reuse.
Enclosed is a check for $150 to cover the License Application fee.
l Very truly yours, C. W. Malody, Manager l
Regulatory Compliance CWM:jrs Enclosures As Stated Log _ _ _ -h
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- g. g SPECIAL NUCLEAR MK/ERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART I - LICENSE CONDITIONS REV.
20 CHAPTER 2 ORGANIZATION AND ADMINISTRATION The President of Advanced Nuclear Fuels Corporation has the ultimate responsibility for ensuring that all Company operations are conducted safely, and in full compliance with applicable Federal, State and local regulations, licenses, and permits.
All functions, which handle or store special nuclear material authorized by this License, reside within two divisions of the Company, Operations and Engineering.
The relationship of those segments of the organization whict) contain a
significant safety or licensing responsibility is depic'sd in Figure I-2.1.
The organization of the t
Safety, Security, and Lic' nsing Department which contains the responsible e
safety specialists and professionals is depicted in Figure I-2.2.
2.1 Organizational Responsibilities and Authority 2.1.1 President and Chief Executive Officer In connection with his ultimate safety responsibility, the President shall assure that adequate manpower, funding, and resources are made available within the Company to achieve the capabilities committed in this Application.
Additionally, he is responsible for assuring that there is a sound, consistent safety philosophy throughout the Company.
2.1.2 Vice President. Operations Division The Vice President, Operations Division, is responsible for the overall management of the fabrication of nuclear fuels.
He carries the responsibilities of the Senior Site Representative.
With this responsibility are the safety-related functions of operations, maintenance, transportation, materials handling and storage, licensing and industrial, radiological, and nuclear safety.
-l 2.1.3 Manaaer. Operations-Richland The operation of the nuclear fuel manufacturing and ancillary facilities at the plant are directed by the Manager, Operations-Richland, j
who reports to the Vice President, Operations Division.
The Manager, Operations-Richland, is responsible for the fabrication i
of nuclear fuels within the constraints imposed by product, process, I
quality assurance, licensing, and safety requirements.
His i
responsibilities include plant operations, quality control, laboratories, and maintenance.
He has the full authority required to discharge his responsibilities for safe operation of all site manufacturing facilities.
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April 27, 1989 2-1 AhF V M 051A (5/B81 i
l ADVANCEDNUCLEARFUELSCORPORATION y74 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257
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PART I - LICENSE CONDITIONS 20 2.1.4 Manaaer. Plant Operations The operation of the fuel manufacturing facilities are directed by the Manager, Plant Operations, who reports to the Manager, Operations-Richland.
i The safe operation and control of plant activities, including the safety of the environs as influenced by the conducted activities, are the responsibility of the Manager, Plant Operations.
Other responsibilities include:
1.
Preparation of detailed work and operating procedures, and training of employees for activities under his direction.
l l
2.
Compliance with license conditions and any required corrective actions resulting from either Advanced Nuclear Fuels or NRC compliance inspections.
3.
Supervision of all manufacturing activities within the respective plants.
4.
Special nuclear materials safeguards control and protection for activities under his management.
5.
Membership in the Emergency Cadre.
6.
Membership in the ALARA Committee.
The Manager, Plant Operations, has the full authority required to discharge his responsibilities for safe operation of his plant.
2.1.5 Manaaer. Plant Maintenance
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All plant maintenance activities are directed by the Manager, Plant Maintenance, who reports to the Manager, Operations-Richland.
In addition to common maintenance activities, the Manager, Plant Maintenance, is responsible for cunducting established preventative maintenance and routine inspection programs for all safety-related e
equipment and systems. He schedules maintenance activities with Manager, Plant Operations, and he is responsible for alerting the plant management of deteriorating and/or substandard conditions of safety-related equipment and systems.
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PART I - LICENSE CONDITIONS 20 He is responsible for maintaining and calibrating radiation protection instruments and equipment, the criticality accident alarm system,. and the fire detection and alarm system in accordance with established programs.
He is also responsible for conducting tests of safety and emergency-related equipment as required by established programs.
2.1.6 Manaaer. Ooerations Plannina and Schedulina The nuclear material traffic activities for ANF-Richland facilities are directed by the Manager, Operations Planning and Scheduling, who reports to the Manager, Materials and Schedul.ing.
The responsibilities of the Manager, Operations Planning and Scheduling, include shipping, receiving, and warehousing of nuclear materials, maintaining nuclear material transfer records, and assuring that plant inventories of nuclear materials do not exceed authorized possession limits.
These activities are conducted within the confines of licensing and safety requirements.
2.1.7 Manaaer. Safety. Security. and Licensina The Manager, Safety, Security, and Licensing, reports to the Vice President, Operations Division, and is responsible for developing, administering, and auditing the licensing, health physics, criticality safety, environmental surveillance, ALARA,
- security, and safeguards programs for all Advanced Nuclear Fuels facilities located at Richland, Washington.
The Manager, Safety, Security, and Licensing, is wholly independent with no manufacturing responsibility, and has direct access to the upper management of the Company.
If the Manager,
- Safety, Security, and Licensing, judges any operation as unsafe, he has the authority to request management to i
shutdown the affected operation.
In the event of disagreement between line management and the Manager, Safety, Security, and Licensing, the operation shall be immediately shutdown, and the issue promptly brought to the attention of the Vice President, Operations Division.
Actions following from this authority are subject to review and approval solely by the President of the Company.
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ADERNCED AN) CLEAR FUELS CORPORATION g p.g SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 m
P. ART I - LICENSE CONDITIONS REv.
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i 2.1.8 Supervisor. Radiological and Industrial Safety The Supsrvisor, Radiological and Industrial Safety, who reports to the Manager, Safety, Security, and Licensing, directs the activities of industrial safety, criticality safety, and radiological safety personnel in conformance with approved Company policies and programs in direct support of plant operations.
If the Supervisor, Radiological. and Industrial Safety, judges any operation as unsafe, he has the authority to request management to shutdown the affected operation.
In the event of disagreement between line management and the ' Supervisor, Radiological and Industrial Safety, the operations shall bei immediately shutdown, and the issue promptly brought to the attention of the cognizant department manager.
2.1.9 Radiological Safety Comoonent The general function of the Radiological Safety Component is to provide information,
- advice, and assistance to the operating and engineering components such that personnel and environmental protection are maximized, and to keep adequate records to properly document conditions.
Specific responsibilities of the Radiological Safety Component include the following:
1.
Administering the plant radiological safety programs, and directing the activities of the Health Physics Technicians.
2.
Establishing radiological safety programs in accordance with i
criteria. and standards provided by the Manager, Regulatory o
Compliance.
Such programs include air sampling, contamination i
and radiation
- surveys, bioassay in-vivo examination, and associated records systems.
3.
Reviewing established programs and evaluating effectiveness.
4.
Providing radiological safety analysis of proposed operational changes or modifications.
5.
Preparing Radiation Work Procedures.
6.
Assisting in preparation of reports to regulatory agencies.
7.
Auditing operations for compliance with regulatory criteria, license' conditions, and Advanced Nuclear Fuels criteria.
8.
Assisting in health physics and radiation safety training.
April 27, 1989
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2-4 ANF,3830.D51 A ($/88)
ADMRNCEDNUCLEARFUELSCORPORATION y.g SPECIAL NUCLEA'R MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART I - LICENSE CONDITIONS 20 9.
Membership in the Emergency Cadre.
10.
Membership in the ALARA Committee.
2.1.10 Health Physics Technicians The collection and accumulation of basic radiological data, along with providing routine radiation monitoring services, is conducted by
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Health Physics Technicians who report to the Supervisor, Radiological and Industrial Safety.
Senior Health Physics Technicians may be assigned special duties, along with' appropriate titles.
Health Physics' Technicians carry out established programs, and assist in, initiating new or necessary programs; specific responsibilities shall include the following:
1.
Providing radiation monitoring.
2.
Collecting air and effluent samples.
3.
Issuing and controlling personnel dosimeters.
4.
Maintaining all records pertaining to personnel
- exposure, contamination and air surveys, sampling, inspections, tests, etc.
5.
Inspecting operations and reporting violations of written radiation protection procedure.s.
6.
Membership in the Emergency Crew.
7.
Providing personnel decontamination.
8.
Providing training in radiological safety.
2.1.11 Health Physics Component There is a Health Physics Component within the Radiological Safety organization.
The responsibilities of the Health Physics Component include the following:
1.
Providing technical bases, criteria, and methods related to health physics.
AMENDMENT APPUCATION DATE-PAGE NO.:
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ADMSNCEDNUCLEARFUElBCORPORATION g7,2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM.1227, NRC DOCKET NO. 701257 PART I - LICENSE CONDITIONS REV.
20 2.
Providing for outside sources for aid and special services related to health physics and emergencies.
3.
Performing compliance inspections.
4.
Membership in the Emergency Cadre.
5.
Membership in the ALARA Committee.
6.
Approving exceptions to whole body exposure
- limits, if required and justified.
7.
Reviewing Radiation Work Procedures.
8.
Providing professional advice and counsel concerning matters within his cognizance.
2.1.12 Criticality Safety Component There is a Criticality Safety Component within the Radiological and Industrial Safety organization.
The responsibilities of the Criticality Safety Component include the following:
1.
Providing technical bases, criteria, and methods related to nuclear criticality safety.
2.
Preparing the Nuclear Criticality Physics Methodology Manual.
3.
Providing criticality safety determinations for designs and procedures, including second-party reviews.
4.
Providing professional. advice and counsel concerning matters within his cognizance.
5.
Membership in the Emergency Cadre.
6.
Performing compliance inspections.
7 7.
Approving Criticality Safety Specifications and Limit Cards.
All determinations concerning nuclear criticality safety shall be reviewed by a Second-Party Reviewer who shall be knowledgeable in the technical data and qualified in the techniques of criticality physics.
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April 27, 1989 2-6
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ADVANCED Nt) CLEAR RJELS CORPORATION gy72 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART I - LICENSE CONDITIONS REV.
20 Second-party reviews shall be arranged by the Criticality Safety Component, and may be either from within the component or by an outside reviewer.
All nuclear criticality safety calculations and reviews shall be documented, and documents shall be held in permanent Company' records.
Calculational details, work sheets, etc., shall be held for a minimum period of six months following termination of the process or operation reviewed.
2.1.13 Manaaer. Reaulatory Como11ance j
l The Manager, Regulatory Compliance, reports to the Manager, Safety, Security, and Licensing;'and is responsible for obtaining all licenses, I
permits, and amendments; thereto necessary for plant operation _that involve the safety of the workers, public, or environment.
He is also responsible for the safeguards program.
He is responsible for ensuring that all licensing and permit requirements are appropriately implemented, and implementation adequately documented.
This is accomplished through 1
issuance of appropriate Company Policies and Standards, and by approval of certain implementing procedures.
He is the Company interface with regulatory agencies, and will host audits by Regulatory Representatives and respond to any audit reports for the Company.
2.1.14 Vice President. Enaineerina Division The Vice President, Engineering Division, is responsible for engineering support of the fabrication of nuclear fuels, including the conduct of certain demonstrations involving special nuclear materials.
2.1.15 Manaaer. Process and Eauioment Enaineerina All engineering activities to provic. maintenance engineering, methods engineering, process engineering, and design and construction of new or modified equipment, and facilitier are directed by the Manager, Process and Equipment Engineering, who reports to the Vice President, Engineering Division.
He is responsible for providing process specifications to establish limits wherein the fuel fabrication process can be operated, for providing design criteria, and Engineering Change Notices which specify the bases required for the design and construction of new or modified equipment and facilities, and for providing manufacturing engineering support to t!)e nuclear fuels fabrication plant.
The latter activity includes maintenance engineering (to establish preventative / routine maintenance.and. instrument and equipment calibration requirements),
methods engineering (to provide industrial engineering and product minoueur *peucan " "
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2-7 April 27, 1989 ANF-3830 051 A (S/881 L
ADiiANCEDNUCLEARFlm2 CORPORATION y.g SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART I - U CENSE CONDITIONS REV.
20 fabricability), equipment engineering (to implement the use of new and modified equipment), and process engineering (to provide process support and development).
He has the full authority required to assure that new or modified facilities are designed and constructed to operate within licensing and safety requirements.
2.1.16 Manaaer. Eauioment and Maintenance Enaineerina j
Plant engineering assistance for all process, utility, and safety systems is provided by the
- Manager, Equipment and Maintenance Engineering, who reports to the
- Manager, Process and Equipment Engineering.
The Manager, Equipment and Maintenance Engineering, is responsible for the design and/or modification of new and existing equipment and facilities for Maintenance Engineering.
He is also responsible for establishing preventative maintenance; routine maintenance; routine equipment inspection; instrument calibration schedules, procedures, and equipment; and instrument and system testing programs for all plant facilities and operations. This includes equipment and systems installed to maintain personnel exposures to radiation and radioactive materials, as well as releases of radioactive materials to the environment, as low as is reasonably achievable.
Radiation protection instruments and equipment, the criticality accident and fire alarm systems, and the electrical power emergency generators are included in these programs.
2.1.17 Manaaer. Process Suocort Enaineerina Process engineering activities are directed by the Manager, Process Support Engineering, who reports to the Manager, Process and Equipment Engineering.
The Manager, Process Support Engineering, is responsible for providing process engineering support to the fuel fabrication plant.
This includes the preparation of process parameter operating limits and process specifications.
He provides technical support for welding operations and for developing improved welding methods.
These activities are conducted within licensing and safety requirements.
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PART I - LICENSE CONDITIONS REV.
20 j
i 2.1.18 Manauer. Chemical and Ceramic Development The Manager, Chemical and Ceramic Development, is responsible for process development activities for new and improved chemical and ceramic processes for preparing 00, and for treating liquid and solid wastes.
2 These activities are conducted within licensing and safety requirements.
2.1.19 Manaaer. Materials Research The operation of the Engineering Laboratory Operations (ELO) facility is directed by the Manager, Materials Research, who reports to the Manager, Fuel Resear'ch and Development.
1 The safe operation and control of facility activities, including the safety of the environs as influenced by the conducted activities, are the responsibility of the Manager, Materials Research.
Other responsibilities include preparation of operating procedures,
- training, and supervision of all activities involving radioactive materials within the ELO facility.
The Manager, Materials Research, has the full authority required to discharge his responsibilities for safe operation of his facility.
2.1.20 Manaaer. Fuel Development and Testina The operation of the Fuel Cooling Test facility (FCTF) (where reactor-simulated flow tests involving a single fuel element are conducted) is directed by the Manager, Fuel Development and Testing, who reports to the Manager, Fuel Research and Development.
The Manager, Fuel Development and Testing, is responsible for the safe operation of the FCTF within the constraints imposed by license conditions, Radiation Work Procedures, and Criticality Safety Specifications.
2.2 Personnel Education and Experience Requirements Responsibilities and authorities of all line managers shall be provided in writing.
Hiring of managers and key professionals in plant operations, health physics, and nuclear criticality safety shall be subject to approval by the Vice President, Operations Division.
The Manager, Operations-Richland, and managers in engineering and technical services functions which' have responsibilities for the processing, storing, or handling of special nuclear materials, shall have ausmouewr amicarm oart April 27, 1989
- ^ot ao" 2-9 ANF-3830.051 A (SIB 81
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g.g SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM.1227, NRC DOCKET NO. 701257 PART I - LICENSE CONDITIONS REV.
20 a minimum of two years of experience in the nuclear industry, and a degree in Science or Engineering.
There are certain other positions where a technical degree is not required such as the Manager, Maintenance.
In those cases, the incumbent will have adequate job training, and technical support and overview will be available. Specific requirements for those key safety professionals whose major responsibility is in a safety field are listed below.
2.2.1 Manaaer. Safety. Security. and Licensina The minimum qualifications of the Manager, Safety, Security, and Licensing, shall be a BS degree in a technical field with 10 years experience in the nuclear energy field, of which four shall have been in positions with nuclear safety responsibility.
2.2.2 Supervisor. Radiological and Industrial Safety The minimum qualifications shall be a BS degree in a technical field, with five years experience in radiatfon safety, or, in the absence of a degree, then 10 years experience shall be required.
2.2.3 Health Physics Technician The minimum qualifications of certified Health Physics Technicians shall be a high school diploma with two years of radiation monitoring experience, or four years of.similar experience in lieu of a high school diploma.
Health Physics Technicians shall complete a formal Advanced Nuclear Fuels training program, or shall have had equivalent prior training; they shall become proficient in Advanced Nuclear Fuels radiological safety programs, criteria, specifications, procedures, and routines.
2.2.4 Health Physics Specialist The minimum qualifications of at least one member of the Health Physics Component shall be a BS degree in Science or Engineering with five years experience in. radiation protection, including at least two years of radiation protection experience allied with nuclear fuel fabrication.
2.2.5 Criticality Safety Specialist The minimum qualifications of at least one member of the Criticality Safety Component, as well as for each Second-Party Reviewer, shall be a BS degree in Science or Engineering with at least two years of experience in nuclear criticality safety analysis.
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ADMMCEDNUCLEARFUELSCORPORATION y p.,
SPECIAL' NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART I - LICENSE CONDITIONS 20 2.2.6 Manaaer. Reaulatory Comoliance l
The minimum qualification for the Manager, Regulatory Compliance, shall be a BA or BS degree in Science or Engineering, plus eight years experience in the nuclear field of which four years experience shall have been in positions with nuclear safety or radiological safety responsibility.
2.3 Safety Review Committees 2.3.1 Health and Safety Council Advanced Nuclear Fuels has established the Health and Safety Council which convenes monthly at Advanced Nuclear Fuels's fuel manufacturing plant in Richland, Washington, to review various aspects of the safety program, including:
1.
Industrial safety practices and trends.
2.
Radiological safety practices and trends.
3.
Criticality safety practices and trends.
4.
Adequacy of emergency planning and procedures (including i
results of tests and drills).
j 5.
Overall safety awareness and attitude of employees and programs for promoting improveme,nts.
6.
Unusual occurrences and accident investigations, including I
recommendations,to prevent recurrences.
7.
Status of Council related action items.
Membership of this Council includes:
1.
Vice President, Operations Division (Chairman).
2.
Supervisor, Radiological and Industrial Safety (Secretary).
l 3.
Manager, Safety, Security, and Licensing (Co-Chairman).
4.
Vice President, Operations Division, staff.
5.
Vice President, Engineering Division, and his staff.
AMEhDUENT APPUCATION DATE PAGE NOa April 27, 1989 2-11 ANF 3837051 A 15185)
ADEMCSDNUCLEARFUELSCORPORATION yg SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 1
PART I - LICENSE CONDITIONS 20 6.
Appropriate managers within other organizations.
7.
Key safety engineers and specialists.
Designated members of the Council make monthly inspections of f
buildings and grounds for housekeeping and safety practices, and report I
the findings to the Council at the monthly meetings.
Findings are assigned to individuals for resolution and are held open until resolved.
l 2.3.2 ALARA Committee l
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j An ALARA (as low As Beasonably achievable) Committee maintains
' awareness of ' trends in ' employee radiation exposure and radioactivity content of effluent releases. The membership of the Committee includes:
1.
Manager, Regulatory Compliance (Chairman).
2.
Ilealth Physics Specialist (Secretary).
3.
Supervisor, Radiological and Industrial Safety.
4.
Manager, Facilities and Equipment Engineering.
i 5.
Manager, Plant Maintenance.
l 6.
Manager, Plant Operations.
7.
Manager, Process Support Engineering.
The' ALARA Committee shall convene at least semi-annually.
The l
ALARA Committee shall issue a formal report at least annually to the l
Health and Safety Council reviewing employee exposures and effluent release data to determine:
1.
Trends in personnel exposures and effluents.
2.
If personnel exposures or radioactive effluents might be lowered under the concept of ALARA.
3.
If equipment for effluent and exposure control is properly designed, used, maintained, and inspected.
Their reports shall include review of required audits and inspections performed during the past year, and review of employee external exposures, bioassay results, unusual occurrences, effluent releases, in-plant airborne radioactivity, and environmental monitoring.
AMENDMENT APPUCATION DATE.
PAGE NO.,
l April 27, 1989 2-12 1
ANF-3830 051 A (5/881 N___- _ _ _-__ _ _
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ADVANCED ARICLEAR FERLS CORPORATION gnp.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 i
PART I - LICENSE CONDITIONS REv.
20 4
2.4 Trainina In addition to normal on-the-job training, employees are instructed in radiation protection and criticality safety requirements and procedures, industrial safety, fire protection, and emergency procedures.
The degree of training is commensurate with each employee's position in the Company (related to general and special responsibilities), and with the extent of the employee's contact with radioactive and fissionable materials.
Employee instruction is provided by personnel knowledgeable in the various training topics.
All formal training is documented, and records are maintained by the Safety, Security, and Licensing Department.
2.4.1 Initial Trainina Each employee is provided initial instruction adequate to allow him to safely start on-the-job training; they are provided the full instruction within two weeks after starting work.
Prior to assignment to independent operation, each employee is required to have been instructed in radiation protection, criticality safety, and emergency requirements and procedures as appropriate to his position.
2.4.2 Followuo Trainina When changes are made in radiation protection, criticality safety controls (procedures, specifications, etc.), or 'n emergency procedures, each employee affected is promptly informed and properly instructed.
Safety topics are routinely discussed in month 1y safety meetings.
Additionally, each employee routinely working with special nuclear material receives annual refresher instruction as part of Advanced Nuclear Fuels continuing program in radiation protection and criticality safety awareness. The effectiveness of this annual refresher training is determined by giving the employees a written examination and reviewing the correct answers to the questions at the end of the test.
2.4.3 Health Physics Technician Trainina Health Physics Technicians are given special training related to their radiation protection assignment.
Previous training is accepted if considered equivalent to the Advanced Nuclear Fuels training program.
Despite previous acceptable training, the Health Physics Technicians are required to become proficient in Advanced Nuclear Fuels radiation protection and criticality safety programs, criteria, specifications,
^ " ' " " ' " ' ' " " * " ' ' * -
April 27, 1989 PAGE NO.:
2.}3 ANF 3830.051 A (SS8
ADESNCEDMJCLEARRELBCORPORATION gyp.,
SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 l
PART I - LICENSE CONDITIONS REV.
20 procedures, and routines, as demonstrated by successfully passing an Advanced Nuclear Fuels certification examination within six months after employment as a Health Physics Technician.
In addition, refresher training is provided to all Health Physics Technicians annually.
2.4.4 Inipino Evaluations Employee awareness of, and conformity to, safety requirements and procedures, as well as the effectiveness of safety training programs, shall be evaluated at least monthly by the Radiological Safety Component for radiation protection, and by the Criticality Safety Component for criticality safety.
These Advanced Nuclear Fuels staff members have the authority to require retraining of employees. These evaluations shall be i
documented along with actions required by them.
2.5 boeratino Procedures. Standards and Guides Advanced Nuclear Fuels conducts its business in accordance with a system of Standard Operating Procedures, Company Standards, and Policy Guides.
Advanced Nuclear Fuels is committed to cone olling activities involving special nuclear materials in accordance with these approved written procedures, standards, and guides. These documents are prepared, reviewed, rev: sed, approved, and implemented in accordance with the Approval and Responsibility Matrix (Figure I-2.3).
Plant and facility managers are responsible for assuring compliance with all pertinent radiation protection and criticality safety procedures, specifications, and practices within their respective facilities.
Violations of radiation protection or criticality procedures, or specifications which are of repetitive or serious hature, are subject to disciplinary action.
The Supervisor, Radiological and Industrial Safety, is responsible for assuring that Health Physics Technician activities are conducted in accordance with established and approved procedures,
- methods, and frequencies.
2.6 Jnternal Audits and InsDeCtillE Audits and inspections are conduc+ed to determine that plant operat:ans are conducted in compliance with regulatory requirements, license conditions, and written procedures. These audits and inspections apply to radiation protection, criticality safety, hazardous chemical safety, fire protection, and environmental protection.
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PART I - LICENSE CONDITIONS 90
- 2. 6'.1 Badiation Protection As part of their normal activities, the Supervisor, Radiological and Industrial
- Safety, and Health Physics Technicians perform daily inspections as a part of their procedures for collecting air samp1es and performing radiation and contamination surveys of all areas of the plant where uncontained radioactive materials are stored, processed, or otherwise handled.
Detected infractions of radiation protection procedures, exposure controls, and sound radiation protection practices
' are. corrected on-the.-spot as, part of a continuing education effort in theif field"of' expe'rtisd;' e Serio'us infractions and noncompliance with slicense conditionse are;idocumented and distributed to the respective facility management, and to the Manager, Safety, Security, and Licensing.
The Health Physics Component of Safety, Security, and Licensing makes monthly audits of radiation protection practices and exposure controls.
These audits are made in accordance with a written plan.
Results of these audits are documented, including any recommended corrective
- actions, and distributed to the respective facility management, and to the Manager, Safety, Security and Licensing.
The Health Physics Component shall followup on each detected discrepancy in subsequent audits until there is satisfactory resolution.
2.6.2 Criticality Safety While performing their daily duties, Health Physics Technicians are alert for infractions of criticality safety specifications and limits.
Detected infractions are communicated to the Criticality Safety Component.
The Criticality Safety Component conducts monthly audits of the various criticality safety control systems, (e.g., moderation control, enrichment control, neutron absorber inspections, process alarms, and trips related to criticality safety, etc.).
The Criticality Safety Component also audits new installations and modifications to equipment and processes prior to their operation with special nuclear material.
These audits are performed in accordance with a written plan, and reports of the findings are submitted to the respective facility management, and to the Manager, Safety, Security, and Licensing.
The Criticality Safety Component shall followup on each detected infraction in subsequent audits until there is satisfactory resolation.
AMENDMENT APPUCATION DATE PAG 1 NO April 27, 1989 2-15 ANF.3830.051 A (5/86)
AD%SNCEDNUCLEARMMACORPORATION gu72 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 l
REV.
PART I - LICENSE CONDITIONS 70 l
i 2.6.3 Hazardous Chemical Safety
{
As part of their normal duties, the Supervisor, Radiological and Industrial Safety, and the Industrial Hygiene Specialist make periodic inspections of all areas of the plant where hazardous chemicals are stored, processed, or otherwise handled.
Detected discrepancies of exposure controls, and sound industrial hygiene practices are corrected on-tl.e-spot as part of their continuing educational effort.
j
.The Industrial Hygiene, Specialist also monitors the levels af the various chemidals that ars present on our plant site in accordance with a
. written industrials Hygiene: Mo'nitoring Program Plan.
Results of these inspections are documented, including any recommended corrective actions, and distributed to the respective facility management, and to the Manager, Safety,
- Security, and Licensing.
The Industrial Hygiene Specialist shall followup on each detected discrepancy in subsequent inspections until there is satisfactory resolution.
2.6.4 Fire Protection The Inspection Comtuittee of the Richland Health and Safety Council performs monthly inspections of selected areas of the Richland facility.
These inspections include housekeeping concerns, as well as industrial safety concerns.
A fa'cility with good housekeeping (combustible wastes properly contained, emergency exits accessible and uncluttered, fire extinguishers properly maintained), will experience fewer and less serious fires.
Results of these inspections are documented, including any recommended corrective actions, and distributed to the respective facility management.
The Inspection Committee shall followup on each detected discrepancy and recommended corrective action in subsequent inspections until there is satisfactory resolution.
The Radiological and Indu.strial Safety Supervisor ensures that a monthly inspection is made of all plant fire extinguishers in accordance with a written plan.
Results of these inspections are documented, and any detected discrepancies are corrected during the inspection.
2.6.5 Environmental Protection Inspections The Industrial Hygiene Specialist monitors the levels of regulated material released to the environment in accordance with a written plan.
l The Health Physics Technicians are responsible for the field sampling under the guidance of the Industrial Hygiene Specialist.
Results of this monitoring are documented and distributed to the Mar,ager,
- Safety, Security, and Licensing.
AMENDMENT APPUCATION DATL PAGE NO:
April 27,1989 2-16 AW3MA m a
ADMANCED NUCLEAR FlJELS CORPORATION g7 2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM.1227, NRC DOCKET NO. 701257 PART I - LICENSE CONDITIONS 20 The Health Physics Component makes monthly inspections of environmental protection practices and exposure controls.
These inspections are made in accordance with a written plan.
Results of l
these inspections are documented, including any recommended corrective actions, and distributed to the respective facility management, and to the Manager, Safety, Security, and Licensing.
The Health Physics Component shall followup on each detected discrepancy and recommended correct.ive action in subsequent inspections until there is satisfactory resolution.
f 2.7 Ninvestidations and Reportina of Reportable Incidents t
Ji I'n ' add'itidn to, "and/or in-line with, the reporting requirements specified in other sections of this Application, or in Regulatory Guide 10.1, the following reporting schedule is adhered to:
1.
Employee, former employee, or terminating employee radiation exposure information shall be reported to individuals in accordance with 10 CFR 19.13(b)(c)(e);
2.
Personnel exposure upon termination of employment or work shall N: su';mitted to the NRC in accordance with 10 CFR 20.406(b) u d N CFR 20.409; 3.
Employee exposures and monitoring information shall be reported to the NRC in accordance with 10 CFR 20.407; 4.
Overexposure and excessive levels and concentrations sh' 1 be reported to the NRC in accordance with 10 CFR 20.405(a) and 10 CFR E0.409; 3.
The NRC shall be notified of incidents in accordance with 10 CFR20.403(a)(b);
6.
Theft, or loss of licensed material, shall be reported in accordance with 10 CFR 20.402(a)(b)(c);
7.
Effluent monitoring infor. nation shall be reported to the NRC in accordance with 10 CFR 70.59; 8.
In the event that the radioactivity in plant gaseous effluents exceeds 50 microcuries per calendar quarter, a report shall be I
submitted within 30 days to the NRC (Director, Office of Nuclear Material Safety and Safeguards, with a copy to NRC AMENDMENT APPUCATION DATE-PAGE No; April 27, 1989 2-17 ANF 3830 051 A (548) o
AD%4NCEDNUCMARRELSOORPORATION
,n p.g SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM.1227, NRC DOCKET NO. 70-1257 PART I - LICENSE CONDITIONS 20 Region V Office of I&E), identifying the cause for exceeding this value, and the corrective actions to be taken to reduce release rates; 9.
If parameters important to dose assessmeiit of the public relative to gaseous effluents from the plant change, a report shall be submitted to the NRC (Director, Office of Nuclear Material Safety and Safeguards, with a copy ' to NRC Region V Office of I&E) within 30 - days identifying the changes in parameters, and providing an estimate of the resultant change i
r in dose commitmAnt;a 10.
Reports of exdessive radioactive contamination on packages of radioactive material, and excessive radiation levels external,
to the packages on receipt, shall be reported to the NRC immediately in accordance with 10 CFR 20.205(b)(2) and 10 CFR 20.205(c)(2);
- 11. Accident reports on transportation of licensed material shall be reported to the NRC and DOT in accordance with 10 CFR 71.5(b) and 49 CFR 171.15 and 49 CFR 171.16.
The tianager, Safety, Security, and Licensing, has the responsibility for investigating, recording, reporting, and following up on actions taken for reportable incidents in accordance with NRC reporting requirements.
2.8 Records In addition to, and/or in-line with, the documentation requirements specified in other sections of this Application and 10 CFR 20.401, the following records are retained:
1.
Personnel radiation exposure histories and determinations of personnel accumulated dose.
(Information on personnel prior radiation exposure histories is obtained in accordance with 10 CFR20.102(c)(1).)
i 2.
Employee radiation exposures, external and internal, including dose evaluations.
3.
Health Physics Technicians' radiation and contamination surveys, including room air and exhaust air monitoring.
4.
Environmental surveillance data and waste discharge reports.
l AMENDMENT APpuCADON DATE.
PAGE NO4 April 27, 1989 2-18 ANF.3830 051 A $88)
. ~ - -
. ~. - - -
. - _ = - - _
ADMANCEDNUCLEARFRELSCORPORATION
,np.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART I - LICENSE CONDITIONS 20 5.
Incident investigation reports.
6.
Employee indoctrination, training, and retraining reports.
7.
Facility and process acceptance tests.
8.
Radiatian saf.ety, health physics, and criticality safety inspection reports.
i 9.
Richland Health and Safety Council meeting reports.
r a
- 10. ALARA Committee. reports.
- 11. Criticality dosimeter inspection reports.
- 12. Reports of test results for the criticality accident alarm system.
13.
Reports of test results for the emergency electrical power supply system.
- 14. Radiation detection instrument maintenance and calibration;
'also for the neutron detectors of the criticality accid 6nt alarm system.
- 15. Results of sealed source leak checks.
16.
HVAC system monitoring cnd test results.
17.
Engineering Change Notices (ECN).
- 18. Revisions to Nuclear Criticality Safety Analysis.
Sut.h records are maintained for a minimum period of five years, unless there are legal requirements for longer retention periods for specific records.
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AMENDMENT APPkfCATION DATE-PAGE NO.:
April 27, 1989 2-19 ANF 3830.051 A (5/88) e
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20 FIGURE I-2.2 SAFm,SECUNTY, AND IJCENSING MANAGER MADl0 LOGICAL AND REGULATORY INDUSTRIAL SAFETY PLANT SECURITY COMPUANCE SUPERVISOR MANAGER HEALTH PHYSICS LICENSING -
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SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART I - LICENSE CONDITIONS REY.
20 f
Chapter 3 RADIATION PROTECTION 3.1 Special_ Administrative Requirements 3.1.1 ALARA Policy Advanced Nuclear Fuels's policy is to conduct its business in a manner such as to assure that its facilities are in compliance with radiation and other nuclear regulations, and that its operations will not be detrimental to the environs.
In implementing this policy, Advanced Nuclear Fuels shall assure that radiation exposure to persons both in-plant and off-site is maintained as low as reasonably achievable (ALARA).
In providing this assurance, conditions of applicable NRC and State licenses, and other regulatory permits or licenses, shall be complied with, and regard shall be given to applicable NRC regulatory guides and industry standards.
Responsibility for establishing and assuring adherence to this policy shall rest with the President, Advanced Nuclear fuels Corporation.
This policy shall be implemented through appropriate delegations, to Vice Presidents responsible for facilities processing or handling radioactive and nuclear materials.
In order to facilitate implementation of this policy, key positions in organizations involved with facilities processing or handling radioactive or nuclear materials shall be filled by persons knowledgeable of, and experienced in, the nuclear industry, and the responsibilities under this policy shall be identified in writing.
Each responsible manager shall be required to know, understand, and carry out the provisions of this policy, and the procedures for its implementation.
3.1.2 Radiation Work Procedures Radiation Work Procedures (RWPs) are prepared by Radiological and Industrial Safety, and establish the radiological safety requirements of all work (operation and maintenance) involving radiation and/or radioactive materials.
The RWP shall be immediately available to personnel working with the material.
RWPs are approved in accordance with Figure I-2.3.
RWPs cover such items as:
1.
The identification number of the procedure; 2.
A description of the nature and extent of the work to.be done and the location of the work;
~~**
April 27, 1989 3-1 ANF 3830 051 A (5/68)
t ADuMCEDARJCLEARFLELBCORPORATION
,n p.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART I - LICENSE CONDITIONS REV.
20 3.
Contaminated Radioactive Material Areas. Visible contamination in these areas artd/or smearable contamination in er. cess of z
10,000 dpm/100 cm (alpha) will be cleaned up immediately.
These limits are not applicable to nonroutine tasks being conducted under special controls.
4.
Plutoniun Contamination.
Plutonium contamination ig limited to 100 dpm/100. cmz avqrage fixed, 300 dpm/100 cm' maximum fixed, and 20 dpm/100 cmz removable.
3.2.6.2 Release of Personnel. Materials. Eauipment. Facilities, and Shioments i
Contamination surveys are performed on all personnel leaving contaminated areas, on all materials, equipment and facilities to be released from radiation protection requirements, and on all incoming and outgoing shipments of radioactive materials.
Release of equipment and packages from the plant site, or to clean areas on-site, shall be in accordance with NRC guidelines dated May 1987 (see Appendix A).
1.
Personnel.
Personnel contamination surveys are conducted according to the following schedule:
a.
All persons leaving contaminated areas are required to l
survey themselves for contamination with survey instruments located at respective step-off areas after removing protective clothing, and prior to leaving the step-off area.
b.
Personnel are not released to eat or leave the respective facility, except with the approval of the Radiological and Industrial Safety Supervisor and the respective facility manager, if their personal clothing is contaminated in of 200* dpm/100 cm2 (alpha) direct, or skin is excess contaminated in excess of E10* dpm/100 cm2 (alpha).
Protective cloihing is not reused if jhe removable alpha c.
contamination exceeds 1000 dpm/100 cm after laundering.
During the workday, protective clothing in a contaminated area will pe changed if contamination is visible (210,000 dpm/100 cm alpha).
200 dpm/100 cm2 (alpha) represents the practical lower detection level for most direct-reading contamination survey instruments.
aus=oueur amcare= oars.
April 27, 1989 3-9 ANF 3830.05 t A 4/88)
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ADERNCEDNUCLEARFUELSCORPORATION y
SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM.1227, NRC DOCKET NO. 701257
-1 PART I - LICENSE CONDITIONS l
REV.
20 CHAPTER 4 NVCLEAR CRITICALITY SAFETY I
Nuclear criticality safety shall be assured through both administrative and technical practices. Administrative practices clearly include establishing the responsibilities for nuclear criticality safety, providing adequate and skilled personnel, preparing written standards and procedures, process
- analysis, materials and operational
- controls, operational and incident reviews, and emergency procedures.
Technical practices include exercising control over the mass and distribution of significant quantities of special nuclear materials, and the mass, distribution, and nuclear properties of all other materials with which special nuclear materials are associated.
4.1 Administrative Conditian_1 The responsibilities and authorities for nuclear criticality safety are as described in Section 2 of this Application, as well as the professional requirements for criticality safety personnel.
4.1.1 Process Analyses (Critically Safe Determinations)
Before any operation with special nuclear material is begun or changed, it is determined that the entire process will be subcritical under tioth normal and credible abnormal conditions, and within the technical requirements specified in Section 4.2.
Criticality safety analyses are performed on all applicable processes in accordance with Section 2.1.12, and all determinations of nuclear criticality safety are reviewed and approved by a second-party reviewer in accordance with the requirements specified theroin.
Criticality safety analyses are performed and/or reviewed by Advanced Nuclear Fuels or contractor personnel who meet the professional requirements specified in Section 2.1.20.
Records of criticality safety analyses of processes shall be documented and retained in accordance with Secticn 2.1.20.
Additionally, I
basic criteria, data, methods, and references pertaining to nuclear criticality safety shall be documented and retained in Company files by the Criticality Safety Component.
Operations, in which nuclear criticality safety is pertinent, are governed by written procedures, and all persons participating in these operations are required to be familiar with the procedures.
Each major process step is described by a written Process Specification which, together with the respective Criticality Safety Specification (CSS),
provides the basis for Written Operating Procedures.
auswoveut amicinon oare.
April 27, 1989 4-1 ANF3830 051 A (S/88)
\\
1 ADVANCEDNUCLEARFUELSCORPORATiON
,n72 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART I - LICENSE CONDITIONS I
g, 20 CSS's are prepared in a standardized format containing the following information:
work location, equipment description, special nuclear material description (element, isotope, enrichment, form, density),
operation involved, control limits, moderator and reflector restrictions, spacing restrictions, criticality safety procedures, date, and approvals.
CSS's are maintained up-to-date and reflect all approved process and/or equipment changes.
Additionally, they shall be kept current by annual reviews, and updated as appropriate.
CSS's are prepared based on limits established in criticality safety analyses.
The CSS's are accepted and approved in accordance with Figure I-2.3.
Copies of current CSS's are maintained it, the work or storage areas in which the respective specifications apply.
4.1.2 Criticality Safety Standards Advanced Nuclear Fuels has established, and maintains, a system of written Criticality Safety Standards for processes, equipment, and facilities involving special nuclear material.
These Standards are prepared and maintained by the Manager, Regulatory Compliance, and are approved and accepted in accordance with Figure I-2.3.
These standards shall be kept current by annual review, and updated as appropriate.
4.1.3 Fissile Content Verification The fissile isotope content of all incoming special nuclear material is verified by gamma energy analysis techniques or laboratory analysis of representative samples prior to the conduct of any activity other than storage.
4.1.4 Special Nuclear Material Control The movement of fissionable materials is controlled.
The CSS'c describes the materials control practices, including the following requirements:
1.
Workstations, procedurally controlled only on the basis of a safe mass of material, are limited to one safe batch, where a safe batch is defined as no more than 0.45 of the minimum critical mass of the material ir, process.
AMENDMENT APPLICATION DATE PAGE NO.;
April 27, 1989 4-2 ANOS30 051 A (548)
.. ~ ~...-
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r ADifANCED AN) CLEAR MELS CORPORATION gup.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM.1127, NRC DOCKET NO. 701257 PART I - LICENSE CONDITIONS
- ggy, 20 4.1.7 Confirmation of Analysis Assumptions Prior to the introduction of special nuclear material into a new operation or process, a criticality safety analysis will be performed, and the Criticality Safety Component shall inspect the respective facility and/or equipment and confirm that the assumed controls are in place and/or functional.
The results of these inspections shall be appropriately documented.
4.2 Technical Practices Wherever practicable, criticality safety will depend upon equipment designs where dimensions are limited, rather than upon decisions or actions of people.
Where this is not practicable, reasons for not using favorable geometry shall be documented as a part of the criticality safety analysis.
The following criteria form the bases for criticality safety controls.
4.2.1 Rgyuble Contingency Policy Process and equipment designs and operating procedures incorporate sufficient factors of safety to require at least two unlikely, independent, and concurrent errors, accidents, equipment malfunctions, or changes in process conditions before a criticality accident is possible.
4.2.2 Limits on Maximum Multiplication Factors The maximum evaluated neutron multiplication factor at normal and as defined below.
l credible abnormal, conditions shall not exceed ka The maximum allowable multiplication factor will be calculated from the expression:
i k
kc - Aku - Akm a
where The value of k that results from the calculation of k
c benchmark experNnts using a particular calculational method. The value represents a combination of theoretical techniques and numerical data.
The uncertainty in the benchmark experiments, including Ak
=
u random and systematic errors (bias) within the range of parameters encountered in the equipment design.-
(
AMENDMENT APPUCATION DATE.
PAGE NO.:
l April 27,1989 4-4 ANF-3830 051 A (S/88)
o,,
ADVANCEDNUCLEARFERLSCORPORATION
,n72 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART I - LICENSE CONDITIONS 20 CHAPTER 6 SPECIAL PROGRAMS 6.1 Proprietary Information With application for license amendment dated June 12, 1985 for operation of a dry conversion process, Advanced Nuclear Fuels submitted copies of document XN-NF-837, Part II, " License Amendment Application, Dry Conversion Process, Proprietary Supplement," dated June 1985, and requested that it be withheld from public disclosure pursuant to 10 CFR 2.790. An accompanying affidavit dated June 13, 1985 was also submitted.
The U.S.
Nuclear Regu'atory Commission (NRC) did determine that the submitted document did contain trade secrets or confidential er proprietary commercial information (letter, R. E. Cunningham to C. W. Malody, dated July 19, 1985).
Amendment No. 26, dated November 7, 1986, was subsequently issued permitting operation, and no additional conditions of license were imposed.
6.2 Occupational Safety Advanced Nuclear Fuels follows the current American Conference of Governmental Industrial Hygienists (ACGIH), Washington Industrial Safety and Health Administration (WISHA), and the NRC maximum permissible concentrations, threshold value limits, and permissible exposure limits for radioactive and hazardous chemicals in the design and operation of its fuel fabrication facility.
In case of a known release, Plant Operations personnel will contact Safety, Security, and Licensing personnel to ascertain the concentration levels and the recommended personnel protective equipment required for cleanup operations to proceed. Safety, Security, and Licensing personnel conduct routine or periodic surveys, as appropriate, to determine the concentrations of routinely utilized radioactive and hazardous chemicals.
6.3 Emeroency Utilities 6.3.1 EmeraencY Electrical Power Sucoly Turbine generator sets are installed to provide emergency electrical power to' operate the Criticality Accident Alarm System, selected exhaust fans, telephones, radiation detection instrumentation, critical process equipment, and also provide emergency lighting.
These generators are tested at least monthly for proper startup and operation.
Functional tests consisting of tying the generator to a normal emergency load are performed at least annually.
AMENDMENT APPtXAT40N DATE.
pagg No; ANF.3830 051 A (5/86)
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ADitAniCED AGUCLEAR Ft2LB CORPORATION g p.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART II - SAFETY DEMONSTRATION REV.
20 CHAPTER'll ORGANIZATION AND PERSONNEL 11.1 Organizational Responsibilities f
It is the policy of Advanced Nuclear fuels to conduct its business in a. manner so as to assure that its facilities are safe from radiation and other nuclear hazards, that its operations will not be detrimental to the environs, and to assure that personnel (both in-plant and off-site) radiation exposures are maintained as low as is reasonably achievable (ALARA).
In providing this assurance, conditions of applicable NRC licenses shall be complied with, and full regard shall be given to app.licable NRC Regulatory Guides.
Responsibility for establishing and assuring adherence to this policy shall rest with the President of Advanced Nuclear Fuels Corporation, and exercised through the Vice President, Operations Division, and Vice President, Engineering Division. This policy shall be l
implemented through appropriate delegations to managers responsible for particular facilities processing, or otherwise handling radioactive and nuclear materials.
Each responsible manager shall be required to know, understand, and carry out the provisions of this policy and the procedures for its implementation.
11.2 Functions of Key Personnel The organization at the Corporate Level are depicted in Figure 11-9.1.
The function and responsibiliticis of the various safety-related positions are described in Chapter 2 with the flow of responsibility depicted by Figures I-2.1 and I-2.2.
During the absence of key individuals, another individual is delegated, in writing, to assume his l
responsibilities.
In the case of a plant emergency, the Radiological l
Co~ntingency Plan lists alternates to the Emergency Director.
11.3 Education and Experience of Key Personnel R6sumds of personnel who currently occupy key safety-related positions are listed hereunder.
t i
l April 27, 1989 11-1 ANO3830 05I A (S/881
i I
s ADMSNCEDNUCLEARFUELS CORPORATION g7 y SPECIAL NUCLEAR MATERIAL LICENSE NO, SNM 1227, NRC DOCKET NO. 701257 PART II - S,AFETY DEMONSTRATION ny, 20 11.3.1 President and Chief Executive Officer - R. B. Stephenson Education BS Mechanical Engineering 1965 Purdue University MS Nuclear Engineering 1970 University of Michigan MBA Business / Finance 1972 University of Michigan Exoerience 1965-1970 Various capacities as a commissioned officer in the U.S. Navy Nuclear Power Program, including service aboard a nuclear-powered, attack-class submarine.
1972-1985 Employed by Advanced Nuclear Fuels Corporation (Exxon Nuclear Company, Inc., prior to January 1, 1987).
Manager, Test Facilities, responsible for operations and operations support for the Atomic Vapor Laser Isotope Separation Research and Development Program.
(1972-1975)
Manager, Methods Engineering, responsible for industrial engineering for the light water reactor fuels manufacturing division.
(1975-1976)
- Manager, Plant Engineering, responsible for all equipment and facilities engineering related to operation, maintenance, and improvement for fuels manufacturing.
(1976-1977) i
- Manager, U02 Shop Operations, responsible for manufacturing operations for pressurized water and boiling water fuel assembly production.
(1977-1980)
Managing Director and Manager, Manufacturing, for Exxon Nuclear GmbH in
- Lingen, West
- Germany, responsible for all logistics, manufacturing, engineering,
- security, and health physics for European manufacturing operations.
(1980-1983)
Manager, Marketing Analysis,. responsible for market environment and l
competitor analysis supporting sales.
(1983-1984)
AMENDMENT APPt.tCAftON DATE:
PAGE NO.;
April 27, 1989 11-2 ANF 3830.05t A (5168)
c.:. u.. ~.n.
- - = - - - -
1 ADEMCSDNUCLEARFLELSCORPORATION l
gu72 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 70125T PART II - SAFETY DEMONSTRATION REv.
pn Regional Sales Manager responsible for fuel sales to approximately one-fourth of the U.S. nuclear utilities.
(1984-1985) 1985-1987 Employed by Exxon Enterprises as President, Chief Executive Officer, and Chairman of the Board of EPID, Inc., responsible for general management of an enterprise engaged in the development, manufacturing, and sales of computer components.
(1985-1986)
Vice President, Administration.
(1986) i Vice President, Commercial Division.
(1986-1987) e 1988 - Present Employed by Advanced Nuclear Fuels Corporation (Exxon Nuclear Company, Inc., prior to January 1, 1987) as President and Chief Executive Officer.
I R
AMENDMENT APPteCATIC'N DATE.
PAGE NO..
April 27, 1989 11-3 ANF 3830 051 A (5188)
g.
ADESNCEDNUCLEARNELSCORPORATIO,4 gn p.,
L SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART II - SAFETY DEMONSTRATION REv.
20 11.3.2 Vice President. Operations Division - R. G. Frain Education BS-IndustrialAdEinistration 1963 Villanova University Exoerience 1960-1967 Employed by General Electric Company in varh. prmressively responsible positions in manufacturing.
1967-1968 Employed by Polyphase Instruments Company as a Production Manbger.
1968-1975 Employed by General Electric Company as Senior Engineer for business development studies related to gas centrifuge uranium enrichment, and as Manufacturing Project Engineer assigned to Goddard Space Flight Center for installation and startup of the ground data handling system for the earth resources satellite.
s 1975-Present Employed by Advanced Nuclear Fuels Corporation (Exxon Nuclear Company, Inc., prior to January 1, 1987).
- Manager, Malta Operations, developing centrifuge manufacturing capability.
(1975-1980)
Manager, Shop Operations-Richland (1980).
Managing Director of Exxon Nuclear European affiliate, ENGmbH (1980).
Manager, Operations-Richland (1983).
Vice President, Operations Division (1989).
{
AMENDMENT APPUCATON DATE PAGE NO.:
April 27, 1989 11-4 ANF 3830.051 A ($/88)
.~
O NE ANF-2 I
SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART II - SAFETY DEMONSTRATION av, 20 11.3.3 Manaaer. Operations-Richland - B. N. Femreite Education BS Metallurgical Engineering 1966 University of Idaho MS Metallurgical Engineering 1967 University of Idaho Post-Graduate MBA Studies 1974 University of Washington Experience 1967-1970 Employed by United Nuclear, Richland, Washington as a Senior Process Development Engineer responsible for manufacturing process and materials development for defense reactor fuels.
1970 - Preso_qt.
4 Employed by Advanced Nuclear Fuels Corporation (Exxon Nuclear Company, Inc., prior to January 1, 1987).
Senior Engineer, Research and Engineering, responsible for process development, materials evaluation, and process support for U02 and H0X commercial fuels.
Manager, Shop Operations, responsible for manufacturing operations for UO2 and M0X fuels.
Manager, European Projects, responsible for planning, staffing, startup, and initial startup of the European Fuel Plant.
Manager, Uranium Waste Project, responsible for process development, design, installation, and startup of liquid and solid waste recovery systems in Richland manufacturing, plant.
- Manager, Richland Employee Relations, responsible for Human Resources function for Richland site.
- Manager, Plant Operations, responsible for design
- criteria, staffing, training, and startup of manufacturing operations for a DOE plant at the Idaho National Engineering Laboratory.
AMENOMENT APPUCATION DATE PAGE NO.:
April 27, 1989 11-5 ANF 3830 OSI A (S48)
L 4
ADEANCEDNUCLEARFERLSCORPORATION gnp.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM.1227, NRC DOCKET NO. 701257 j
PART II - SAFETY DEMONSTRATION
- nay, 70 Manager, Corporate Employee Relations, responsible for corporate Human Resources function in U.S. and Europe.
l Manager, Operations-Richland, responsible for Manufacturing, Quality
)
Control, and Maintenance for the Richland site.
l A
l AMENDMENT APPLICATION DATE.
PAGE NO.:
April 27, 1989 11-6 ANF 3630.051 A (S/88) a
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AD%$n\\CED nlUCLEAR FUELB CORPORATION y7 2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257
)
4 PART II - SAFETY DEMONSTRATION
- ngy, 1
20 11.3.4 Manaaer. Plant Ooeratio_n_1 - T. W. Patten Education-BS Chemical Engineering 1973 University of Minnes'ota i
MS Nuclear Engineering 1975 University of Washington MS Chemical Engineering 1977 University of Washington Exoerience 1974-1976 Employed by Exxon Nuclear Company, Inc., at Richland, Washington as an Engineer in the Thermal Hydraulic Design 'section.
Activities included analysis of fuel designs for conformance to licensing limits, development of methodology and computer codes for thermal hydraulic analysis of fuel bundles, analysis, and correlation of test data.
1977-1978 Employed by Batteile at the Pacific Northwest Laboratories in Richland, Washington as a Development Engineer for computer codes used to analyze thermal hydraulic performance of fuel assemblies during normal operation, and'during transient and accident conditions.
1978-Present Employed by Advanced Nuclear Fuels Corporation (Exxon Nuclear Company, Inc., prior to January 1,1987) in a variety of positions in Richland and t
Bellevue, Washington.
Engineer responsible for development of thermal hydraulic methodology for licensing reload fuel for Boiling Water Reactors with emphasis on core hydraulics and fuel critical heat fl ux.
Responsible for coordinating Company's critical heat flux testing program.
(1978-1980)
- Manager, Fuel
- Testing, responsible for supervision of group conducting thermal hydraulic, critical heat flux, mechanical, and dynami:: testing on fuel assemblies.
(1980-1983)
Customer Service Engineer (Bellevue) responsible for engineering project interface with Company's customers.
(1983-1984)
AMENDMENT APPUCATION DATE.
PAGE NO:
April 27, 1989 11-7 ANF 3830 051 A (5481
1 ADMANCEDNUCLEARFUELSCORPORATION
,n72 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART II - SAFETY DEMONSTRATION
- ngy, 20 Senior Planner (Bellevue) responsible for coordination of corporate planning efforts and conduct of various business analyses.
(1984-1985)
Manager, Neutronics and Fuel Management, responsible for managing section which specifies the enrichment design of Company's futi assemblies, determines core loading plans to meet utility power generation goals, and performs ~ analyses in support of licensing effort.
(1985-1987)
Manager, Affiliate Liaison, responsible for interface with parent company in Germany and other affiliates following acquisition of Exxon Nuclear by Siemens.
(1987-1988)
- Manager, Plant Operations, responsible for management of fuel manufacturing and material recovery operations, including the preparation of operating procedures, the development and maintenance of essential material controls and inventories, and the review, initiation and implementation of plant safety procedures.
(1988-Present)
AMENDMENT APPUCATION DATE-PAGE NO :
April 27, 1989 11-8 ANF.3830 051 A (Seep
L *..
ADuan\\MDhlUCLEARREESCORPORATION gu p.,
SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART II - SAFETY DEMONSTRATION m,
20 11.3.5 Manaaer. Plant Maintenance - J. L. Glesener Education Technical courses completed:
Electronic Technician School, U.S. Navy Instrument Technician Apprentice Program f-Reactor Training for Maintenance ~ Supervision Certified Vibration Analyst Codes and Standards for Fabrication of Nuclear Power Piping and Vessels High Vacuum Systems and Helium Leak Detection Basic Data Processing Exoerience 1951-1955 Electronics Technician in the U.S. Navy.
1955-1972 Employed by General Electric Company, Battelle Northwest and Westinghouse n
Electric Company in Richland, Washington.
Instrument Technician.
Specialist, Scheduling and Methods, Craft-Reactor Maintenance (all l
crafts).
Foreman, Multi-Craft Reactor Maintenance.
Acting Manager, PRTR, Reactor Maintenance.
Specialist, Planning and Scheduling for FFTF related Sodium Facilities Maintenance and Fabrication.
Other related ex'perience during this period included:
Administered all Craft Apprenticeship Programs for Battelle Northwest and Westinghouse.
Advisory Committee, Co'lumbia Basin College Electronic Technology Program.
I AMENDM(NT APPLgCATON DATL PAGE NO.
April 27, 1989 11-9 ANF 3830 OSI A ($46)
(
I-ADifANCEDNUCLEARRELSCORPORATION
,y72 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM.1227, NRC DOCKET NO. 701257 g
PART II - SAFETY DEMONSTRATION
- ngy, 20 Industrial Representative for Washington State Office of Vocational Education.
1972-Present Employed by Advanced Nuclear Fuels Corporation (E'xxon Nuclear Company, l
Inc., prior to January 1, 1987).
Supervisor, Rod finishing, U02 Operations.
(1972-1973)
Manager, Plant Maintenance.
(1973-Present)
Administration of all Richland site maintenance services.
Member of Plant Emergency Cadre since 1972.
Member of ALARA Committee since 1980.
1 1
l l
l l
l l'
l 1
l AMENDMENT APPUCAtaON DATE.
PAGE NO..
April 27, 1989 11-10 ANF 3830.051 A,:$/88)
{
l ADMSAMDARJCLEARMEE2 CORPORATION
,u72 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART II - SAFETY DEMONSTRATION
- ngy, 20 11.3.6 Manaaer. Safety. Security, and Licensino - W. E. Stavig Education BS Chemistry 1956 University of Puget Sound Exoerience 1956-1970 Employed by General Electric in the manufacturing of nuclear fuels.
1 Process Development Engineer engaged in UF6 conversions process and development.
Manager, Quality Control, responsible for quality function nuclear fuel manufacturing.
Manager, Operations Engineering, responsible for prevention and solutions of process problems for manufacturing of nuclear fuel.
1970-Present Employed by Advanced Nuclear Fuels Corporation (Exxon Nuclear Company, Inc., prior to January 1, 1987).
- Manager, Plant Operations, responsible for management of fuel fabrication.
(1970-1975)
- Manager, Manufacturing Engineering, responsible for providing technical directions for plant modifications and improvements.
(1976-1980)
Manager, Plant Equipment and Design, Advanced Projects, responsible for planning engineering analyses and scope, conceptual, and detail design for process equipment.
Coordinate overall plant equipment l
arrangements for increase throughput and efficiency.
(1980-1983)
Staff Engineer, Plant Operations, responsible for engineering project interface with plant operations, define, analyze and develop implementing plans for compliance to criticality, health physics and applicable licensing documents.
Audit plant operations for l
AMENOWENT APPUCATION DATE; FAGE NO.:
April 27, 1989 11-11 ANF-3530.051 A ($188)
,s
,a ADifANCED NUCLEAR FtELS CORPORATION gnp.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART II - SAFETY DEMONSTRATION
[
REv.
20 compliance to all licensing activities.
Member of Design Review group which reviewed the design and work scope for Engineering Change Notices for conformance to plant safety criteria.
(1983-1989)
Manager, Safety, Security, and Licensing.
(1989-Present) l l
l l
l l
l l
AMENDMENT APPLICATION DATE PAGE NO.:
April 27, 1989 11-12 ne um wa m l
l
ADMANCEDNUCLEARFtmLBCORPORATION gn72 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART II - SAFETY DEMONSTRATION m,
20 11.3.7 Suoervisor. Radiological and Industrial Safety - T. C. Probasco Education-BS Microbiology 1970 Oregon State University BS Military Science 1970 Oregon State University Certified Safety Professional 1982 Board of Certified Safety Professionals Exoerience 1970-1972 Highway Engineering Technician for the Oregon State Highway Department.
1972-1975 Employed by a food processing company.
Supervised chemical and bacteriological laboratories in Quality Assurance Department.
(1972-1973)
Safety Engineer.
(1973-1975) 1975-Present Employed by Advanced Nuclear Fuels Corporation (Exxon Nuclear Company, Inc., prior to January 1,1987).
Plant Safety Engineer.
(1975)
Plant Criticality Safety Engineer.
(1975-1984)
Supervisor, Radiological and Industrial Safety, responsible for supervising Health Physics Technicians, Radiological Safety Specialist, and Industrial Hygiene Specialist.
(1985-Present)
I AMENDMENT APPLICAff0N DATE PAGE No; April 27,1989 11-13 ANF.3830 061 A ($188)
=
1
.a ADitkNCED MJCLEAR FUELS CORPORATION y7 2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART II - SAFETY DEMONSTRATION m,
20 11.3.8 Criticality Safety Sacialist - L. D. Gerrald Education BS Chemical Engineering 1967 University of South Carolina MS Chemical Engineering 1971 University of South Carolina Exoerience 1968-1971 Employed by Westinghouse Electric Corporation at the Nxlear Fuel Fabrication Plant in Columbia, South Carolina, as a Process Engineer responsible for the startup and operation of the UF -UO2 conversion 6
process lines.
1971-Present Employed by Advanced Nuclear Fuels Corporation (Exxon Nuclear Compan),
Inc., prior to January 1, 1987).
Process Engineer responsible for pellet fabrication process.
(1971-1974)
Process Development Engineer responsible for numerous studies related to several fuel fabrication processes.
Developed computer codes for calculating pore size distributions for pellets using
- canning electron microscope and image analyzer.
(1974-1981)
Process Engineer responsible for the ceramic part of the Spherc-Pac project.
Developed equipment and parameters for drying and sintering the U09 spheres to be used.
Also developed continuous-flow vertical sin'tering furnace for this process.
(1981-1983)
Criticality Safety Analyst primary responsibility for converting l
several SCALE modules (KEh0, XSDRN, BONAMI, NITAWL) to computer I
systems; responsible for verification of codes and cross sections, and numerous major criticality safety analyses were performed for operations at ANF-Richland, ANFGmbH-Lingen, West Germany, and for fuel storage racks for power reactors.
Analyses have also been performed for submittal to the USNRC Transportation Certification Branch.
(1983-Present)
)
i AMENDM1MT AP8ZATON DATE; PAGE NO.:
l April 27, 1989 11-14 Ae m Atsem l
0' ADESNCEDNUCLEARFUELSCORPORATION g 7.g SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM.1227, NRC DOCKET NO. 701257 PART II - SAFETY DEMONSTRATION REv.
20 11.3.9 Health Physics Soecialist - J. E. Pieper l
Education BS Nuclear Engineering 1973 Oregon State University Technology Conditional Operator 1972 BWR Power Plant Training Certificate Center Exoerience 1973-1976 Employed by Aerojet Nuclear Company, Idaho Falls, Idaho.
Design engineering.
(1973)
Nuclear technology.
(1983)
Nuclear (criticality safety program, analyses, and training) and environmental safety.
(1973-1974)
Management Oversight and Risk Tree.
(1974) 1976-1981 Employed by Rockwell Hanford Operations, Richland, Washington.
Nuclear Safety.
(1976-1977)
Criticality safety prograrn appraisal.
Review of criticality safety anaiyses and procedure, and system designs.
Radiological safety inspections and audits.
Health, Safety and Environment function repr3sentative to the Chemical Processing, Waste Encapsulation, and Fractionalization Programs.
(1978)
Health, Safety and Environment Design Review Coordinator.
(1978-1980)
Safety review and approval of new projects and designs.
AMENOMENT APPUCATION DATE:
PAGE NO.:
April 27, 1989 11-15 ANF4830.051 A (5/88)
..O 8
6 ADifAhMD AN) CLEAR FEREB CORPORATION guy.g SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET 90. 701257 PART II - SAFETY DEMONSTRATION m,
20 Technical consultant on DOE requirements for packaging and shipping radioactive materials.
Flying Tigers Hazardous Materials Shipping Seminar and Workshop.
(1979)
Radiological Engineer in the Decontamination and Decommissioning Program.
(1980) 1981-Present Employed by Advanced Nuclear Fuels Corporation (Exxon Nuclear Company, Inc., prior to January 1, 1987).
Licensing Engineer responsible for assuring compliance with the health physics requirements of the license for a uranium fuel fabrication
- facility, and performing criticality analyses in support of the facilities operation.
Internal Radiation Dosimetry.
(1983)
Introduction to Power Reactor Health Physics.
(1983)
Health Physic Certification Preparation.
(1983,1985,1986)
Biokinetics and Analysis of Uranium in Man.
(1984)
Radioactive Materials Training Course (DOT).
(1984)
Internal Dose Assessment.
(1985)
I AMENDMENT APPLICATION DATE-PAGE NO.:
April 27, 1989 11-16 ANF 3830.0$1 A (S<68)
)
ADifANCEDAUCLEARMELSCORPORATION g7 2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART II - SAFETY DEMONSTRATION
- pgy, 20 11.3.10 Radiological Safety Soecialist - E. L. Foster Education High School Diploma 1960 Richland, Washington Columbia Basin College Nuclear Weapons Technician School U.S. Air Force Technical courses completed:
Radiation Technician Chemistry Course Radiation Dosimetry Biological Effects of Radiation Radioactive Waste Disposal Environmental Monitoring Elementary Nuclear Physics Mathematics in Radiation Protection Ionizing Radiation Measurements Radiation Protection Techniques Air Sampling Principles and Evaluations Radioactive Decontamination Principles Radiation Exposure Records Disaster Monitoring Exoerience 1967-1971 Employ'd by Battelle Northwest in ~Richland, Washington as a Radiation Monitor in the development and application of health physics programs for radioactive chemical separations
- plants, multi-curie laboratory operations, and nuclear fuel manufacturing.
Performed monitoring duties during major cleanup and modification of plutonium hot cells and gloveboxes.
Direct participation in surveillance of effluent from plutonium facilities while assigned to an environmental monitoring group.
Direct participation in setting up routine hrwth physics program for PRTR.
Completed.special assignment involving modification of plant air monitoring program.
AMENDMENT APPLICATION DATL PAGE NOa April 27, 1989 11-17 ANF 382051 A ($t88)
1 ADMANCEDNUCLEARFUELSCORPORATION ANF2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET N7. 701257 PART II - SAFETY DEMONSTRATION
- pay, 1
20 1971-Present Employed by Advanced Nuclear Fuels Corporation (Exxon Nuclear Company, Inc., prior to January 1, 1987).
Health Physics Technician involved primarily in all phases of the radiological safety program throughout the entire plant site.
(1971-1976)
Technician Specialist, Radiological Safety.
(1977)
Radiological Safety Assistant.
(1980)
Radiation Safety Officer for Washington State License.
(1984)
Radiological Safety Specialist responsible for implementation of radiological safety training program, dosimetry program, bioassay
- program, writing of Radiation Work Procedures, reporting of radiological conditions to plant supervision.
(1985)
Completed training course in Respiratory Protection at Nuclear Power Plants.
(1985)
Completed training course as a Radiation Safety Officer.
(1986)
Completed training course in Air Sampling. (1986)
Completed training course in NVLAP Accreditation.
(1987)
Completed training course in Hot Particle Dosimetry.
(1987)
Completed training course in Radiation Detection and Measurement.
(1989) l AMENDMENT APPUCATION DATE.
PAGE NO.:
I April 27, 1989 11-18 ANF.3830 051 A (S/88)
l4.
p V
ADEMCEDNUCLEARMELSCORPORATION l
ANF2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM.1227, NRC DOCKET NO. 701257 PART II - SAFETY DEMONSTRATION
- ngy, l
l 70 11.3.11 Health Physics Technician - D. L. Belt Educati.gn High School Diploma 1954 Columbia High School 1975 Columbia Basin College Radiation Protection Training 1977 Battelle Northwest National Registry of Radiation 1979-Protection Technologists 1982 Technical courses completed:
Engineering Laboratory Techniques Radiation Control Practices Theory of Power Plant Operation
]
Radiography Techniques i
Dosimetry l
Radiation Shielding and Radioactive Material Containment First Aid Training Annual First Aid Refresher Courses (1977-1986) l Annual Plant Emergency Cadre Training (1977-1986)
Experience l
1975-Present 1
l Employed by Advanced Nuclear Fuels Corporation (Exxon Nuclear Company, Inc., prior to January 1, 1987).
Technician in the UO fuel fabrication operation.
(1975-1977) 2 Health Physics Technician responsible for overall
- auditing,
)
inspection, monitoring, and evaluating health physics-related i
criteria.
The application of procedures used in the control of I
radiation, radioactive materials, and criticality are also functions I
of this position..
Responsible for auditing, recognizing and evaluating radiological and nuclear hazards, and/or taking emergency l
action as necessary to protect health and property.
Additional l
responsibilities of this job include training of new employees, l
maintaining records of. bioassay, prsonnel monitoring and survey l
results, exposures, room air and exhaust sampling and monitoring.
l Daily audits are performed of compliance to State and NRC license corditions.
Daily air sampling, and analysis of same of all areas AMENDMENT APPUCATION DATE.
PAGE NO.:
April 27, 1989 11-19 ANF 3830 OSI A ($4m
ADMANCED n\\UCLEAR FUELE CORPORATION g7 2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM.1227, NRC DOCKET NO. 701257 PART II - SAFETY DEMONSTRATION
- ngy, 20 of the plant.
Responsible for environmental monitoring, H0 2
sampling of waste lagoons obtaining environmental (fluoride and vegetation) samples within a 10-mile radius of plant. Also included as major responsibilities of this position are recordkeeping, issuing reports and entering data in computerized Environmental Monitoring Program.
(1977-Present) l AMENDMENT APPLICATION DATE.
PAGE NO.:
April 27, 1989 11-20 ANF 3830.051 A (5188)
'o,
- r ADHANCEDNUCLEARFUELSCORPORATDN g7 2 SPECIAL NUCLEAR MATEnlAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 i
PART II - SAFETY DEMONSTP.ATION REV.
20 11.3.12 Health Physics Technician - L. G. Bradley Education High School Diploma 1947 Salem, OR UFAFI Program 1962-U.S. Air Force 1965 Commercial Pilot Rating 1968 Pasco, WA Radiological Protection 1983 Rockwell Hanford Company Technical Certification Health Physics Technician 1987 Certification Exoerience 1962-1965 U.S.
Air Force, Disaster Control Officer, responsible for training Disaster Control Teams throughout the squadron, responsible for setting up decontamination facilities, and training personnel in the use of radiation detection devices.
1965-1974 Worked in various construction projects as a heavy equipment operator and truck driver; was also employe.1 as an a riculture pilot for H&W sprayin9, <
Midland, Texas.
1974-1984 Emp? iyed by Atlantic Richfield as a Radiation Monitor.
1984-Present Employed by Advanced Nuclear fuels Corporation (Exxon Nuclear Company, Inc., prior to January 1,1987) as a Health Physics Technician.
Dismantle plutonium hoods in the Specialty Fuels Building.
(1984-l 1987) l L
AMENDWNT AMCATION DATE PAM NO.:
April 27, 1989 11-21 ANF.3630.051 A (S/88)
ADMANCEDNUCLEARFUELSCORPORATION m
SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART II - SAFETY DEMONSTRATION
- ggy, 20 11.3.13 Health Physics Technician - J. D. Cudmore Education High School Diploma 1946 Washburn, WI Industrial Welding / Burning Ashland Vocational School Ashland, WI General Columbia Basin College U.S. Army Airplane School Nara, Japan Business courses Northland College
~
Ashland, WI Technical courses completed:
Elementary Nuclear Physics Ionizing Radiation Measurements Air Sampling Principles and Evaluations Shipments of Radioactive Materials Radiological Civil Defense Mathematics in Radiation Protection Radiation Protection Techniques Radioactive Decontamination Principles Radiation Exposure Records Disaster Monitoring Experience 1953-1971 Worked in Richland, Washington in the following capacities related to radiation protection:
Chemical Technician assisting Chemists and Engineers in operation of the radioactive hot cell liquid waste solidification techniques.
Knowledge of chemistry, chemical tank makeup, vacuum and pressure, control rod instruments, and manipulation of the same. Also filled,
- shipped, and received radioactive samples and liquid casks.
. Complete knowledge of decontamination of equipment (large and small), including personnel.
AMENDMENT APPUCATION DATE PAGE NO.;
April 27, 1989 11-22 ANMtw %1 A ($188)
L_
ADifAhiCED NUCLEAR FLELS CORPORATION
,yp.g SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART II - SAFETY DEMONSTRATION
- ngy, 20 Manipulator-0perator experience in Am, Pu, Pm, Cs, Ce, Np, Sm separation, and purification using ion exchange columns and glovebox techniques.
Made radiation surveys of radiation zones and non-radiation zones, report, and recommend corrections for unsatisfactory conditions.
Made surveys and authorized release of equipment.
Prescribe dose rates and clothing requirements 'for entry into radiation zones and for work within these zones in contaminated equipment and ra'dioactive material.
Investigate the circumstances leading to clothing or skin contamination or uncontrolled contamination spread.
Prescribe the necessary respiratory protection after taking air samples and evaluation.
Provide either constant or intermittent monitoring of radiation zone work. Made legible, concise, accurate, and complete records of all activities.
Provide radiation-protection trainirg to operating and maintenance personnel.
1971-Present Employed by Advanced Nuclear Fuels Corporation (Exxon Nuclear Company, Inc., prior to January 1,1987) as a Health Physics Technician.
I AMENOMEW) APPUCATION DATE.
PAGE NO:
April 27, 1989 11-23 AN# 4830 051 A (5/88)
U
AOKANCEDNUCLEARRELSCORPORATION gnp.2 SPECIAL-NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 l
l PART I' SAFETY DEMONSTRATION REV.
20 11.3.14 Health Physics Technician - D. A. Marlin Education m
High School Diploma 1950 Selah, WA Chemical, Biological and 1952 Gifu, Japan i
Radiological School Radiation Monitoring Training 1954-Richland, WA Programs-1970 Radiation Technology 1954-Columbia Basin College 1966 Electrical Appliance Repair 1969 Richland, WA Exoerience 3954-1973 Employed at Richland, Washington in the 'following capacities related to radiction monitoring:
Provided radiation protection for personnel in the Hanford laboratory divisions consisting of constant scientific experiments, storing contaminated liquid waste, and disposing of extremely high radiated and contaminated solid waste.
Rrovided routine and special surveys to promote contamination and exposure control.
Radiation Monitoring Journeyman providing radiation monitoring for all crafts needed to maintain and operate both the graphite reactors and a dual-purpose power reactor.
Radiation Monitoring Supervisor supervising the activities of Radiation Monitoring Journeymen during reactor operations and shutdown. Scheduled and assigned this manpower to various jobs with consideration to the requirements of job safety, labor costs, radiation exposure control, and coordination with operating and maintenance groups.
Provided radiation protection for persorael in all phases of operations and maintenance in nuclear reactors.
Provided routine and special survey to promote contamination and exposure control.
AMENOMENT APPUCATION DATE.
PAGE NO:
April 27, 1989 11-24 AN C3830.051 A (5/88)
.=
)
ADifANCED WJCLEAR FLELS CORPORATION gnp.,
SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART II - SAFETY DEMONSTRATION
- ngy, 20 Advise on requirements, procedures, and optimum methods for accomplishing work, including shielding, decontamination and remote operations.
Collected and analyzed data for use in determining present and future needs in radiation protection.
ProvidL radiation protection for tank farm personnel.
Burying radioactive liquid waste and processing waste to remove different elements in each process until waste was made into a hard state.
In conjunction with tank farm work, cove red laboratory work dealing with sampling radioisotopes in gloveboxes and hoods.
Provided control of radiation exposure by monitoring and using preventive shielding methods, and keeping areas clean by constant smearing and monitoring with survey instruments.
1973-Present Employed by Advanced Nuclear Fuels Corporation (Exxon Nuclear Company, Inc., prior to January 1, 1987) as a Health Physics Technician.
4 AMENOMENT APPUCATCN DATE-PAGE NO.:
April 27, 1989 11-25 ANF 3830.051 A (S$8)
ADifANCED ARJCLEAR FUELS CORPORATKW mp.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART II - SAFETY DEMONSTRATION
- ggy, 20 11.3.15 - Health Physics Technician - J. A. Rosscup Education High School Diploma 1954 Glasgow, MT 1975-Columbia Basin College 1976 Health Physics Technician 1978 Training Advanced First Aid Training 1979 Course Experience 1976-Present Employed by Advanced Nuclear Fuels Corporation (Exxon Nuclear Company, Inc., prior to January 1, 1987).
Technician in the UO fuel fabrication operation.
(1976-1977) 2 Health Physics Technician.
(1978-Present)
)
l 1
1 i
1 1
1 1
AMENDMENT APPUCATION DATE PAGE NO.:
l April 27, 1989 11-26 ANF.3830.0)1 A ($186) a
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SPEClAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 l
PART II - SAFETY DEMONSTRATION nev.
1 20 11.3.16 Health Physics Technician - W. W. Smith l
Education High School Diploma 1956 Radiation Technology 1984 Golnick Home Correspondence NRRPT Certification 1985 University of Washington Course Richland, WA Advanced and Basic First Aid (currently certified)
Experieng3 1980-Prggant Employed by Advanced Nuclear Fuels Corporation (Exxon Nuclear Company, Inc., prior to January 1,1987) as a Health Physics Technician.
a AMENDMENT APPUCATION DATL PAGE HQ.:
April 27, 1989 11-27 ANF-3830051 A ($/88)
i.-.
ADiMNCEDNUCLEARFEMLSCORPORATION
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g7 2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART II - SAFETY DEMONSTRATION REv.
20 11.3.17 Health Physics Technician - G. A. York Education High School Diploma 1970 Walla Walla, WA 1970-Western Washington State 1971 College, Bellingham, WA 1977-Walla Walla Comrtr.ity College 1978 Walla Walla, WA Hanford Radiation Monitor 1979 Training Program 1981-Columbia Basin College 1983 NRRPT Certification 1985 University of Washington Course Richland, WA Experience 1979-Present
~
Employed by Advanced Nuclear Fuels Corporation (Exxon Nuclear Company, Inc., prior to January 1,1987) as a Health Physics Technician.
AutNDMENT AFRICATON DATE.
PAGE NO:
April 27, 1989 11-28 ANF 3830.051 A (stb 8)
.,4 kOttANCED NUCLEAR FUELS CORPORATION g p.g SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART II - SAFETY DEMONSTRATION
- ngy, 1
20 l
11.3.18 Manaaer. Reaulatory Como11ance - C. W. Malody, Jr.
Education AB Chemistry 1950 University of Kansas I
Experience 1950-1963 Employed by General Electric Company, Richland, Washington.
Process Control Engineer responsible for operating procedures, flowsheet testing,' devising process control programs for coatrol of prodat purity and nuclear safety, and plant technical support.
Manager, Uranium 0xide, responsible for operation, maintenance, and radiation monitoring.
1963-1964 Employed by Isochem, Inc., Richland, Washington.
Manager, Uranium 0xide.
Manager, Purex Operations, responsible for plant operations, process control, and radiation monitoring.
1964-1977 Employed by Atlantic Richfield Hanford Company, Richland, Washington.
- Manager, Process Control Engineering, responsible for process control, nuclear safety control, process test authorization, and direct technical support to the purex Plant.
(1964-1968)
Manager, Technical Services, responsible for $5 million annual
- budget, approximately 230 employees in three process control laboratories, and radiation and monitoring control. (1968-1970)
Manager, Purex Plant, responsible for annual budgets greater than
$10 million, and managed approximately 160 employees in operations, maintenance, process engineering and radiation monitoring.
(1970-1973)
AMENDMENT APPUCATION DATE.
PAGE NOJ April 27, 1989 11-29 ANF 3830 051 A (5/B8) 4
,i ADuthMDNUCLEARFUELSCORPORATION ANF-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART II - SAFETY DEMONSTRATION gy, 20 l
- Manager, Production Department, responsible for annual budgets greater than $25 million, and managed more than 700 employees in i
three major processing operations, maintenance, process engineering and, radiation monitoring.
(1973-1976)
I Manager, Production and Waste Management, responsible directly to the President for the overall direction of 1,200 employees, and more than $40 million annual operating budget.
Member of Company's negotiating team during Union Contract renewals.
Also member of an Executive Council determining Company priorities and resource allocations.
(1976-1977) 1977-Present Employed by Advanced Nuclear Fuels Corporation (Exxon Nuclear Company, Inc., prior to January 1, 1987).
Consultant responsible for providing consulting services in support of the proposed reprocessing and spent fuel storage programs.
(1977-1979) 4 Manager, Process Engineering, responsible for keeping abreast of research and development activities in the field of reprocessing.
This was accomplished by maintaining contact with and providing supporting studies for those DOE sites involved in the back end of the fuel cycle such as ORNL, Sandia, Idaho Falls, etc.
(1979-1981)
Manager, Licensing and Compliance, resp'onsible for all licensing activities and criticality and radiological safety programs for the fuels fabrication plant and research laboratory.
(1981-1985)
Manager, Corporate Licensing, responsible for overall licensing and regulatory responsibility for fuel production and transportation activities, and for defining, administering and auditing health
- physics, environmental surveillance, ALARA, nuclear criticality safety, and nuclear material safeguards programs.
(1985-1989)
Manager, Regulatory Compliance, responsible for overall licensing and regulatory responsibility for nuclear activities, and for establishing health physics, nuclear safety, hazardous materials safety, environmental safety, ALARA, and nuclear material safeguards proorams in compliance with legal and regulatory requirements, and l
soSe.J industrial practices.
(1989-Present) l AME'sDMENT APPUCAh0N DATE:
PAGE NO.:
April 27, 1989 11-30 ANF 3830 OSI A IS/B8l l
- v. "
ADESNCEDNUCLEARRJELSCORPORATION g7 2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART II - SAFETY DEMONSTRATION nev.
?n 11.3.19 Specialist. Licensina - R. A. Schneider Education BS Chemistry and Mathematics 1949 Seattle University Secondary' Education Certificate 1950 Seattle University 5-Year MS Chemistry 1957 University of Idaho t
Expgrience 1950-1967 Sixteen (16) years of combined professional and management experience in the nuclear industry. Techn' cal areas include nuclear materials safeguards research and development, analytical chemistry research and development, separation processes, and applied analytical chemistry.
Contributor and team leader of a number of projects aimed at establishing nuclear materials measurement
- methods, and in determining the reliability of measurement systems.
Directed development efforts for the measurement and recovery of byproducts of spent reactor fuels.
- Manager, Analytical Laboratories, responsible for operational aspects of industrial and radiological safety, and for criticality safety of the plutonium laboratory.
1967-1976 Team Leader of Battelle Northwest's nuclear materials safeguards research and development effort.
Contributions include various safeguards systems studies, the development of independent methods of verification, and definition of systems needs.
Author of the Plutonium / Uranium ratio method of input accountability to a chemical processing plant, the " Cesium Index" method for coating waste, and a principal developer of the use of isotopic correlations for verifying the plutonium content of spent power fuel s.
Regular lecturer at the Argonne Safeguards School.
AMENDMENT APPUCATION DATE-PAGE NO.:
l April 27, 1989 11-31 AN _ A -
l
AD1tANCED NUCLEAR FLELS CORPORATION gu72 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM.1227, NRC DOCKET NO. 701257 PART II - SAFETY DEMONSTRATION
- ngy, 20 Published extensively in Analytical Chemistry, the Institute of Nuclear Materials Management, and in Hanford formal reports.
I Consulted for the IAEA, the USACDA and NRC.
1976-Present Employed by Advanced Nuclear Fuels Corporation (Exxon Nuclear Company, Inc., prior to January 1, 1987).
Senior Specialist, Nuclear Materials Safeguards, primarily responsible for assisting in formalizing corporate policies in the area of safeguards, and to prepare the Exxon Nuclear Safeguards Development Program.
Current responsibilities include designation as Accountability Coordinator for safeguards, and as main working level liaison contact with NR0.
Other safeguards responsibilities include Acting Measurement Control Program Coordinator and Director of safeguards courses conducted for international safeguards.
Professional qualification now include election to the rank of Fellow in the first group elected by the Institute of Nuclear Materials Management in 1984.
Specialist, Licensing.
(1989)
I AMENDMENT APPLICATION DATE:
PAGE NO -
April 27, 1989 11-32 ANF 3830.051 A ($48) e
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- ngy, 20 11.3.20 Industrial Regulations Soecialist - S. R. Lockhaven Education BA Biology 1974 Central Washington University BA Environmental Studies 1976 Central Washington University Industrial Hygiene Training 1979-Courses Present Exoerience 1976-Present Employed by Advanced Nuclear Fuels Corporation (Exxon Nuclear Company, Inc., prior to January 1, 1987).
Senior Analytical Laboratory Technician.
(1976)
Industrial Hygienist duties included scheduling environmental sampling, environmental data review, and assisting Plant Criticality Safety Engineer.
(1979)
Plant Criticality Safety Engineer.
(1986)
Industrial Regulations Specialist.
(1989)
AMENDMENT APPLICATION DATE-PAGE NO.:
April 27, 1989 11-33 ANF 3830. dst A (1.3m j
' 1!
ADERNCEDNUCLEARFUELSCORPORATIOV y7 2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART II - SAFETY DEMONSTRATION m,
70 11.3.21 Manaaer. Materials and Schedulina - I. J. Samaritano Education BChE Chemical Engineering 1960 Polytechnic Institute of New York MSchE Chemical Engineering 1962 Rensselaer Polytechnic Institute Industrial Administration 1970-Union College 1973 Schenectady, NY 1
Licenses / Memberships Licensed Professional Engineer, New York Licensed Professional Engineer, Nuclear Branch, California Member, American Institute of Chemical Engineers Experience
)
1960-1970 Employed by General Electric Company at the Knolls Atomic Power Laboratory.
{
Design Engineer responsible for reactor performance analysis, reactor accident analysis, reactor primary shield design, and in-reactor corrosion and crud buildup on nuclear fuel elements.
Responsibilities included computer analysis, design, implementation, analysis of test loop experiments, and experiments in operating nuclear reactors.
Supervising Engineer responsible for the hydraulic design of the reactor for a nuclear powered aircraft carrier.
i 1210 Employed by General Electric Steam Turbine Department as a Unit Manager of Shop Operations with responsibilities for a manufacturing unit of 250 i
machinists engaged in the precision machining of major components for AMENOMENT APPLW'ATION DATE.
PAGE NO.:
April 27, 1989 11-34 Aw.amosi A <s..
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ADitANCEDMCLEARFUELSCORPORATION gn p_,
SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM.1227, NRC DOCKET NO. 701257 PART II - SAFETY DEMONSTRATION
- agy, 20 large steam turbine generators.
Both nuclear and fossil design steam l
turbines were fabricated.
Responsibilities also included management of daily operations, training of personnel, scheduling utilization of equipment, production control planning, and material utilization.
i 1911 Employed by General Electric Research 1.aboratory of the General Electric Corporate Research and Development ~ Center as a Chemical Engineer responsible for the development of a process for the separation of uranium isotopes using high performance centrifuges.
191A Employed by Exxon Nuclear Corporation in Malta, New York.
Senior Manufacturing Engineer responsible for developing equipment, plant layouts, and facility design and staffing plan for the manufacture of high performance centrifuges to be used for isotope separation, supervised the architect engineer, and produced a complete plant design including associated cost estimates.
Assigned increased responsibilities as a Project Manager for marketing, contract administration, manufacture, and testing of high performance centrifuges and components utilized in the U.S.
Department of Energy Centrifuge Demonstration Program.
(1976) 1980-Present Employed by Advanced Nuclear Fuels Corporation (Exxon Nuclear Company, Inc., prior to January 1, 1987).
Manager, Production and Inventory Control responsible for plant scheduling and control of all material inventory utilized for producing
- fuel, determining required quantities and assuring material availability. Responsible for formulating requirements for an advanced computet system to fully control both material supply and actual production.
Also responsible for employee training utilizing the new system.
This sophisticated computer system was successfully implemented.
(1980)
- Manager, Materials and Sched.uling responsible for
- planning, procuring, and managing all material requir.ements.
In addition, full responsibility for all plant ' scheduling, production control activities, including workstation scheduling, receiving, warehousing, and international shipping and traffic.
(1983-Present)
AMENDMENT APPUCATION DATE-PAGE NO.:
April 27, 1989 11-35 ANF.3830.051A $38)
ADERNCED NUCLEAR FlJELS CORPORATION
- lnp_,
SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART II - SAFETY DEMONSTRATION
- ngy, 20 11.3.22 Manaaer. Operations Plannina and Schedulina - D. C. Lehfeldt Education BS Industrial Engineering 1954 Montana State University BS Mechanical Engineering 1954 Montana State University Experience 1954-1965 Employed by General Electric Company in Richland, Washington.
Manufacturing engineering on fuel fabrication for production reactor and N-Reactor.
(1954-1962)
Supervisor, Equipment Development and Maintenance Engineering, N-Reactor Fuels.. Involved with plant equipment and maintenance programs.
(1962-1965) j 1965-1972 Employed by Battelle Northwest Laboratory, Richland, Washington.
Senior Engineer on isotope source fabrication, recycle fuel equipment, Pu-Al plate type fuel development, and fueled shim rods.
(1965-1966)
Manager, Radiometallurgy, involved with personnel, equipment and facilities in the examination of irradiated fuels and materials.
(1967-1969)
Manager, Nuclear Fuels, involved with development and fabrication of UO, M0X, and graphite fuels.
(1969-1972) 2 1972-Present Employed by Advanced Nuclear Fuels Corporation (Exxon Nuclear Company, Inc., prior to January 1,1987).
Senior and Staff Engineer involved with materials and hardware specifications and procurement for power reactor fuels, project coordination, and contract administration.
(1972-1984) i AMENDMENT APPUCATION DATE:
PAGE NO.:
April 27, 1989 11-36 ANF-3830.051 A $48)
ADMUCCEDNUCLEARMJELSCORPORATION y7 2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART II - SAFETY DEMONSTRATION pg, 20 Manager, Operations Planning and Scheduling, involved with planning and scheduling fuel fabrication activities, and logistics for national and international shipments of fuel hardware materials and waste shipments.
(1985-Present) 1 4
0 e
AMENDMENT APPUCATION DATE PAGE NO.;
ANF.3830.061 A 15868) l.
MMMCORPORAD gnp.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO.701257 PART II - SAFETY DEMONSTRATION
- pgy, 20 11.3.23 yjce President. Enoineerino Division - T. A. Bjernard Education BS Physics 1971 Kalamazoo College MS Nuclear Engineering 1976 Massachusetts Institute of Technology PhD Nuclear Engineering 1977 Massachusetts Institute of Technology Exoerience 1971-1973 Employed by Consumers Power Company, Jackson, Michigan.
Miscellaneous tasks in the Nuclear Operations Department related to the nuclear fuel cycle.
1974-Present Employed by Advanced Nuclear Fuels Corporation (Exxon Nuclear Company, Inc., prior to January 1, 1987).
Nuclear Safety Engineer developing LOCA analysis models for the j
licensing of boiling water reactors.
Leave of absence from Exxon Nuclear Company to complete Masters and PhD degrees at Massachusetts Institute of Technology, Cambridge, MA.
(1975-1977)
Production and Engineering Engineer responsible for the development of computer models for LOCA analysis, and Project Manager for development of advanced BWR fuel designs.
Engineering Representative, Engineering and Production,
- ENGmbH,
- Lingen, Federal Republic of
- Germany, responsible for the implementation of design and process engineering specifications in the fuel fabrication plant.
Manager, Incore Monitoring, responsible for developing, maintaining, and installing computers and software systems for the on-line core monitoring of BWR's and PWR's.
AMENDMENT APPLICATON DATE; pagg go,;
April 27, 1989 11-38 ANF.3830.D$1 A ($188)
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' Manager, Technology Applications, ENII, Brussels, Belgium.
Manager, European Business Operations, ENII, Brussels, Belgium.
Vice President and Manager, European, Business Operations, ENII,
- Brussels, Belgium, responsible for providing engineering and management support for European nuclear fuels business.
Vice President and Manager, European Business Operations, ANFI, Brussels, Belgium, responsible for European operations in support of ANF's European fuels business, including business development.
(1987-1989)
Vice President, Engineering
- Division, responsible for the engineering aspects of nuclear fuels business including research, fuel design, neutronics and fuel management, fuel licensing and safety engineering, corporate computer
- services, and process engineering and equipment engineering (in support of the fuel fabrication facilities).
Member of ANF Corporation's Executive Committee.
(1989-Present)
AMENDMENT APPUCATION DATE:
PAGE NO.:
April 27, 1989 11-39 ANF 3830 061 A (5/88)
r ADVANCEDNUCLEARFUELSCORPORATION mp.2 L
SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART II - SAFEri DEMONSTRATION 20 11.3.24 Manaaer. Process and Eouipment Enaineerina - D. C. Kilian Education BChE Chemical Engineering 1966 University of Minnesota MS Chemical Engineering 1977 University of Idaho Exoerience 1966-1974 Employed by Allied Chc.nical Corporation, Idaho Falls, Idaho.
Chemical. Engineer - Project leader for development of a fluidized-bed combustion process for graphite matrix nuclear fuels, developed dissolution process for zirconium matrix fuels, developed a novel fluoride volatility process for purPying uranium.
Group Supervisor responsible for fluidized-bed, waste calcination process development and technical liaison with Idaho Chemical Processing Plant (ICPP) plant operations.
Prepared design criteria for the New Waste Calciner Facility.
1974-1984 Employed by Exxon Nuclear Company, Inc., Richland, Washington.
Senior Engineer responsible for providing technical design bases for uranium calcination and fluorination processes for Exxon's Nuclear Fuel Recovery and Recycling Center. Directed supporting development programs at Oak Ridge National Laboratory and Battelle Northwest Laboratories.
(1974-1977)
Manager, Reprocessing Process Engineering, responsible for process development and engineering for the Nuclear Fuel Recovery and Recycling Center.
Prepared preliminary plant design, preliminary safety analysis, and environment assessment.
(1977-1978)
Assistant Project Manager responsible for implementing project management discipline, and completed preliminary design for the proposed $65 million Laser Isotope Separation Demonstration Plant.
(1978-1979)
AMENDMENT APPLICATION DATE.
PAGE Noc April 27, 1989 11-40 ANF 3830 05t A 45/88)
s.,'
1 ADVANCEDNUCLEARFLELSCORPORATION gnp.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART II - SAFETY DEMONSTRATION na 20
- Manager, Process Technology, responsible for directing the development of technology for uranium chemical processing, uranium metallurgical processing, and dye / solvent processing for the Laser Isotope Separation Program.
(1979-1981)
- Manager, Chemical Engineering, responsible for managing the development of chemical, ceramic, and mechanical processes for manufacturing spherical particle (Sphere Pac) nuclear fuel.
Successfully demonstrated 0.1 MTV/ day pilot plant operation, and prepared a conceptual plant design for a commercial Sphere-P.ac Production Facility.
(1981-1984) 1984-1987 Employed by Exxon Nuclear Idaho Company, Idaho Falls, Idaho.
Manager, Technology Department, responsible for directing process engineering, development, computer engineering, and regulatory compliance for the Specific Mwufacturing Capability (SMC) project, a classified DOE program involving automated, high production rate manufacturing.
Part of the six member management team involved in design, construction, startup, and operation of a several hundred million dollar SMC facility employing over 500 people.
1987 to Present Employed by Advanced Nuclear Fuels Corporation, Bellevue, Washington.
Customer Services Engineer responsible for providing technical liaison between nuclear utility customers and ANF technical organizations for U.S. Marketing Department.
(1987-1989)
- Manager, Process and Equipment Engineering, responsible for providing process support engineering, equipment and maintenance engineering, chemical and ceramic development, equipment and methods development, and capital project management for all ANF fuel fabrication facilities in Richland.
Also responsible for new construction projects in Lingen, West Germany (ANFGmbH).
(1989-Present)
AMENDMENT APPUCATION DATE.
PAGE Nou April 27, 1989 11-41 ANF-3830 051 A (S/881
t ADESNCEDNUCLEARFUELSCORPORATKW m7 2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART II - SAFETY DEMONSTRATION pg, 20 11.3.25 Manaaer. Process Support Enaineerina - R. B. McLees Education BS Ceramic Engineering 1959 Clemson University MS Ceramic Engineering 1960 Clemson University Experience 1960-1969 Employed by Y-12 Plant, Oak Ridge, Tennessee, as a Development Engineer engaged in materials research and development.
1969-1975 Employed by General Electric, Wilmington, North Carolina as an Equipment Engineer responsible for equipment installation and startup.
1975-1976 Employed by General Atomic Plant, San Diego, California, as a Staff Engineer responsible for the liaison with A/E on design of HTGR fuel fabrication plant.
1976-Present Employed by Advanced Nuclear Fuels Corporation (Exxon Nuclear, Company, Inc., prior to January 1,1987).
Equipment Engineer.
(1976-1977) j Supervisor, Chemical Conversion Operation.
(1977-1978)
Lead Engineer, Incremental Plant Expansions.
(1978-1980)
Project Engineer, 550 MTU Plant Expansion and Lingen Pelletizing Project.
(1981-1985)
Manager, Process Support Engineering.
(1985-Present)
\\
AME.NDMENT APPLICATION DATE; PAGE NO.;
April 27, 1989 11-42 ANF 3830.0S1 A (5481 i
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s.; *.,s, AD%MCEDhlUCLEARFUESCORPORATION gu p,,
SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART II - SAFETY DEMONSTRATION
- ngy, 20 11.3.26 Manaaer. Eauioment & Maintenance Enaineerina - J. H. Fastabend Education BS General Engine,ering 1956 University of Portland Professional Enaineer Mechanical Engineer License No. 7787, State of Washington Experience 1956-1968 Employed by General Electric, Richland, Washington.
Responsible for the mechanical design and development of reactor hardware, including special valve development and application for PWR primary coolant systems.
Initiation and direction of development and testing programs in support of large nuclear projects sponsored by AEC primarily connected with pressure piping systems.
Supervisor of nuclear plant engineering organization directing mechanical engineering support programs for an AEC PWR production reactor.
~
1968-1970 Employed by Douglas United Nuclear, Richland, Washington.
Participated in commercial business development activities in nuclear service areas of steam generator and pressurizer repair, modification, and upgrading.
1970-Present Employed by Advanced Nuclear Fuels Corporation (Exxon Nuclear Company, Inc., prior to January 1, 1987).
Project Engineer,and management activities in establishment 'of a commercial nuclear fuels manufacturing plant.
Management of design and construction of high pressure, high temperature test loop l
AMENDMENT APPUCATION DATE.
PAGE NO.:
April 27,1989 11-43 ANF 3830.061 A (5/861
ADEANCEDNUCLEARFUELSCORPORATION g 7,2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM.1227, NRC DOCKET NO. 701257 PART II - SAFETY DEMONSTRATION
- ngy, 20 facilities for nuclear fuels. Management of design and construction of facilities in support of laser-isotope separation experiments.
Design management of an Experimental Test Facility for piloting the laser-isotope separation process.
(1970-1980)
Management of Design Engineering organization and administration of A/E contracts in providing facility, equipment and process designs on Nuclear Fuels Manufacturing plant improvement, and expansion projects.
(1980-1983)
Management of Equipment and Maintenance Engineering organization providing technical direction for maintenance, modification upgrades and improvements to plant, services, and equipment in support of nuclear fuels manufacturing.
(1983-Present)
AWENDMENT APPL.lCATION DATE-PAGE NO.:
April 27,1989 11-44 Avr.mo w A sa,
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ADMSNCEDNUCLEARMELSCORPORATION ap.2 i
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20 11.3.27 Manaaer. Chemical and Ceramic Development - I. J. Urza Education BS Chemical Engineering 1971 University of Idaho MS Chemical Engineering 1972 University of Idaho Experience 1972-1974 Employed by Allied. Chemical Corporation, Idaho Falls, Idaho.
Engineer responsible for conceptual and feasibility
- studies, economic and consequence analysis, and project design support.
Served as a
technical representative at Oak Ridge National Laboratory on the HTGR development program.
1974-Present Employed by Advanced Nuclear Fuels Corporation (Exxon Nuclear Company, Inc., prior to January 1,
1987) in Oak Ridge, Tennessee, Richland, Washington, and Lingen, West Germany.
Engineer, Reprocessing Process Engineering, responsible for the ENC uranium conversion development program at ORNL.
Pilot plant and laboratory process equipment was designed, constructed, and tested for conversion of uranyl nitrate to U0, UO3 fluorination to uranium 3
oxide, and purification of UF -
(1974-1977) 6 Engineer, Reprocessing Process Engineering, responsible for lead processing engineering for the uranium conversion portion of the ENC fuel reprocessing plant.
Served as Task Leader in a DOE-sponsored advanced fuel cycle study.
(1977-1978)
Engineer, Design and Mechanical Development, responsible for design of uranium chemical operations and dye solution processing systems for the JNAI Experimental Test Facility, and conceptual studies of a commercial scale laser isotope separatio.n plant.
Directed design activities of an A/E firm.
Prepared conceptual plant designs to define capital and operating costs.
Prepared process flowsheets, selected and sized equipment, material of construction, layouts, l
etc.
(1978-1981)
AMENDMENT APPt.lCATION DATE.
PAGE NOa April 27, 1989 11-45 ANF 3830.051 A (S/88) e
ADVANCEDNUCLEARFERLSCORPORATION gu72 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM.1227, NRC DOCKET NO. 701257 PART II - SAFETY DEMONSTRATION REv.
20 Staff Engineer, Dry Conversion Process Development, responsible for the Dry Conversion Development Progran including
- design, construction and experimental operation of pilot plant, and a prototypical test facility. Developed and demonstrated a unique dry process for conversion of UF6 to ceramic grade UO2 (patent pending).
The dry conversion process is being installed in the ANFGmbH fuel fabrication plant.
Directed and coordinated process and equipment
- design, equipment procurement, installation, and process development.
(1981-1985)
Senior Staff
- Engineer, Process and Equipment Engineering, responsible for supervision, planning, and technical direction for the Lingen UF6 Dry Conversion project ($8.5 million) through design, licensing, procurement, construction, and startup.
Responsibilities included providing technical direction of related process and equipment development work.
(1986-1989)
Manager, Chemical and Ceramic Development, responsible for providing ongoing and long range engineering and development support to fuel production and waste management operations in the chemical and ceramic development areas.
Responsibilities include development of new and improved processes and processing techniques which improve product quality, and reduce manufacturing costs.
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AMENDMENT APPJCATION DATE PAGE NO..
April 27, 1989 11-46 j
ANF-3830.051 A S168:
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ADifANCED NUCLEAR FUELS CORPORATION mp.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART II - SAFETY DEMONSTRATION gy, 20 11.3.28 Manaaer. Fuel Enoineerino and Technical Services - G. L. Ritter Education BA Chemistry 1961 Pacific Lutheran University BS Chemical Engineering 1962 University of Washington MS Chemical Engineering 1964 University of California Experience 1964-1965 Employed by General Electric as a Process Engineer at the Hanford Purex Plant and Semiworks Facility.
1966-1968 Employed by 1sochem, Inc., as a Senior Process Engineer responsible for developing the technology to recover fission products (Cesium-137, Strontium-90, Technetium-99 and Promethium-147) from Hanford high level liquid wastes.
1968-1971 Employed by Atlantic Richfield Hanford Company.
Senior Engineer responsible for defining and planning research and development programs for managing radioactive wastes.
(1968-1970)
Manager, Separations Process Engineering, responsible for process control and process development support.
(1970-1971) 1971-Pregni n
Employed t,y Advanced Nuclear Fuels Corporation (Exxon Nuclear Company, Inc., prior to January 1, 1987).
Senior Engineer responsible for portions of the technology to support a proposed commercial reprocessing plant.
(1971-1973)
- Manager, Reprocessing Process Engineering, responsible for all process technology and safety analyses for the commercial reprocessing plant project.
(1973-1977)
AMENDMENT APPUCATION DATE-PAGE NOJ Aprg 27, 1989 11-47 ANF.3830.051 A 15/88)
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SPECIAL NUCLEAR MATERIAL LfCENSE NO. SNM 1227, NRC DOCKET NO. 701257 I
PART II - SAFETY DEMONSTRATION
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- Manager, Reprocessing Engineering, responsible for engineering activities to support reprocessing projects performed for the l
Department of Energy and Oak Ridge National Laboratories.
(1977-1979)
Vice President, Technical Department, responsible for all technical activities for supporting the Idaho Chemical Processing Plant at the l
Idaho National Engineering Laboratory.
(1979-1981)
- Manager, Process and' Engineering Development, responsible for process engineering and research and development.
(1981-1983)
Manager, Process and Equipment Engineering, responsible for all process and project engineering support.
(1983-1985)
Manager, fuel Engineering and Technical Services, responsible for nuclear fuel management, licensing and in-core monitoring.
Also responsible for Fuels Research and Development and Corporate Computer Services.
(1985-Present)
AMENDMENT APPLICATION DATE.
1 PAGE NO..
April 27, 1989 11-48 ANF 3830 061 A (Sr88)
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ADKANCEDNUCLEARFUELSCORPORATION g p,2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC' DOCKET NO. 701257 PART II - SAFETY DEMONSTRATION m,
20 11.3.29 Manaoer. Fuel Research and Development - K. N. Woods Education l
BS Materials Science 1962 Stanford University MS Metallurgical Engineering 1963 University of Michigan PhD Materials Science 1968 Northwestern University Experience 1969-1972 Employed by General Electric's Corporate Research and Development Center in Schenectady, New York. Performed basic research on ceramic material.
1972-1977 Employed by General Electric's Nuclear Fuel Department in Wilmington, North Carolina.
Managed advanced process development in a large U02 fabrication plant.
Included responsibility for UF6 to U02 conversion, U02 pelletizing, and liquid waste stream treatment 1977-Present Employed by Advanced Nuclear Fuels Corporation (Exxon Nuclear Company, Inc., prior to January 1, 1987).
Manager, Fuel Performance.
(1977-1979) i Manager, Fuel Performance and Process Development.
(1979-1982)
Manager, Research.
(1982-1984)
Manager, Fuel Research and Development.
(1984-Present)
AMENDMENT APPUCATION DATE PAGE No.
April 27, 1989 11-49 ANF-3630.061 A (548)
ADEANCED NUCLEAR Fin lLB CORPORATION gnp.2.
SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART II - SAFETY DEMONSTRATION arv.
?n 11.3.30 Manaaer. Materials Research - R. A. Busch Education BS Metallurgical Engineering 1961 Rensselaer Polytechnic Institute MS/PhD Materials Science 1963-University of California 1966 Post Doctoral Fellowship, UC Exoerience 1966-1979 Employed by Battelle Northwest as a Senior Research Scientist responsible for contract research and development programs sponsored by government and industry.
Major portions of effort in coating deposition, characterization, and actinide elements.
1979-Present Employed by Advanced Nuclear Fuels Corporation (Exxon Nuclear Company, Inc., prior to January 1, 1987).
Manager, Materials Research, responsible for materials aspects of fuel and cladding development and characterization including laboratory work with nuclear materials.
AMENDMENT APPLICATION DATE, PAGE HO..
April 27, 1989 11-50 AwawA m
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ADEMCEDNUCLEARFUELSCORPORATION y p.y SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART II - SAFETY DEMONSTRATION
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11.3.31 Manaaer. Fuel Development and Testina - J. F. Patterson I
Education BS Mechanical Engineering 1952 Colorado State University MS Nuclear Engineering 1957 University of Michigan Experience 1952-1954 Employed by Phillips Petroleum Company in the Materials Testing Reactor Department as a Design Engineer.
1957-195.1 Employed by Allis-Chalmers in the Nuclear Power Department as Supervisor of Mechanical Engineering.
1963-1972 Employed by Westinghouse Electric Corporation in the Advanced Reactors Division as Manager of Mechanical Development, and PWR Systems Division as Manager of Reactor Mechanical Development.
1972-Present Employed by Advanced Nuclear Fuels Corporation (Exxon Nuclear Company, Inc., prior to January 1, 1987).
Manager, Mechanical Engineering.
- Managte, Fuel Development and
- Testing, responsible for the develtznent of new fuel assembly designs, and thermal-hydraulic and mechanical t~esting for reload fuel.
AMENDMENT APPt.lCATION DATE-PAGE NO.:
April 27,1989 11-51 ANF-38M OS1 A MISS
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SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM.1227, NRC DOCKET NO. 701257 PART II - SAFETY DEMONSTRATION
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11.4 Operatina Procedures I
i Plant operations are conducted according to written procedures.
The I
procedures are written by the Managar, Plant Operations, or his designee.
l They are approved by the Manager, Plant Operations, Quality Control, Safety, Security, and Licensing, Facilities and Equipment Engineering, and Process Support Engineering. These procedures include, by reference, appropriate Criticality Safety Specifications, Radiation Work Permits, and other safety-related, or prrtinent, documents or procedures.
The procedures are documented and issued by Document Control to appropriate 1
personnel and locations.
There are Mini-Libraries located within the various operating facilities which contain. copies of the approved '
operating procedures for ease of access by operating personnel.
11.5 Trainina 11.5.1 Initial Trainina Each employee is provided initial instruction adequate to allow them to safely start on-the-job training by his/her manager or supervisor.
This initial instruction includes emergency procedures.
If the employee routinely works with special nuclear material, radiation protection, and criticality safety, requirements and procedures will be included.
Within two weeks after starting work, full instruction in Standard Operating Procedures (including instrumentation and control, methods of dealing with process malfunctions, control of hazardous chemicals, control of. contamination, and decontamination. procedures), industrial
- safety, fire protection, emergency response procedures, radiation protection (including ALARA practices, nature and source of radiation, interactions of radiation and matter, biological effects of radiation, i
and the use of radiation monitoring equipment and step-off pad procedures), and criticality safety, requirements and procedures will be provided.
The degree of training is commensurate with each employee's position in the Company (related to general and special responsibilities), and with the extent of the employee's contact with radioactive and fissionable materials.
Employee instruction is provided by personnel knowledgeable in the various training topics.
Prior to assignment to independent operation, each employee is required, by signature, to indicate that he has been instructed in radiation protection, criticality
- safety, and emergency response requirements and procedures.
AMENOMENT APPLICATION DATE.
PAGE NO.:
April 27, 1989 11-52 ANF 31L10.061 A ($48)
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SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART II - SAFETY DEMONSTRATION
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11.5.2 Followuo Trainina When changes are made to processes involving special nuclear materials, radiation protection procedures, criticality safety controls (procedures, specifications, limits, etc.),' fire protection, or emergency response procedures, each employee affected is promptly informed and properly instructed by his/her manager or supervisor.
Additionally, each employee who routinely works with special nuclear l
material receives annual refresher instruction as part of Advanced Nuclear Fuels continuing program in radiation protection and criticality safety awareness.
This training is provided by radiological and nuclear safety personnel knowledgeable in the various training topics.
The effectiveness of this annual refresher training is determined by giving the employees a written examination, and reviewing the correct answers to the questions at the end of the test.
All employees routinely discuss safety topics in monthly or quarterly scheduled safety meetings.
11.5.3 Emeraency Response Trainina Training in operating plant fire extinguishers is offered to all
. employees on an annual basis.
Plant Emergency Response Team members are trained in incipient fire fighting techniques, advanced first
- aid, self-contained breathing apparatus training in a smoke-filled environment, and radiological incident stabilization techniques on an annual basis.
Semiannual training is provided to all employees in the proper response to a criticality accident when a preannounced criticality evacuation drill is conducted.
11.6 Chanaes in Procedures. Facilities and Eauioment 11.6.1 Facility and Eauipment Chanaes Changes in Facilities and Equipment involving licensed materials are accomplished through application of the Engineering Change Notice (ECN) procedure.
This procedure provides the instructions for authorizing and documenting the installation of new equipment, facilities, and services and modifications to existing equipment, facilities and services.
AMENDMENT APPUCATION DATE.
PAGE NO '
April 27, 1989 11-53 ANF 3830 O!1A (SS6
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ADMMCEDNUCLEARFUELSCORPORATION g.,
SPECIAL NUCLEAR MATERIAL L1 CENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART II - SAFETY DEMONSTRATION arv.
20 11.6.1.1 Scoce - Included The ECN procedure is used when the work involved meets one or more of the following conditi,ons:
Affects the basic principles of operation of the manufacturing process.
Directly invo'1ves fissile material.
Affects criticality or radiological safety.
Impacts industrial health and safety.
Affects product quality.
Involves licensing matters.
Affects environmental protection.
Requires a process building wall penetration.
Requires underground work.
Affects manufacturing plant equipment layout.
Requires municipal building permit and/or fire marshall inspection.
11.6.1.2 Scooe - Excluded ECN's are not required for normal maintenance, repair, or direct component replacement. ECN's are not required for minor changes which do not meet any of the above criteria.
11.6.2 Review Prior to preparation of an ECN, the drawings and scope packages are reviewed by a group made up of. the Supervisor, Radiological and Industrial
- Safety, the responsible
- engineer, a
representative of Maintenance, and a representative of Operations.
The group reviews the design package for industrial safety and health, radiological safety, and criticality safety problems.
Changes arising from the review are implemented prior to ECN routing.
Verification of review and l
implementation of necessary changes is indicated by sigr.-off of the ECN by members of the review group.
11.6.3 Control / Documentation The ECN form, and any excavation or penetration forms included in the package, are edited for completeness and assigned a number by the Design and Drafting Clerk.
The ECN title and ncmber is recorded in the ECN logbook, and a permanent f.ile established in the ECN record file.
^ ~ ' " " ' " ' ' ' ^ * * ' ' '
April 27, 1989 11-54 ANF 3830.D51 A ISl88)
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sy*.o ADVAhCED ARJCLEAR FtRLS CORPORATION gup.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 PART II - SAFETY DEMONSTRATION REV.
20 11.6.4 Review / Concurrence /Aooroval The ECN receives one approval, that by the User / Operator Manager.
Prior to that approval, however, several other managers have reviewed and concurred with the package.
Following sign-off by the review group, the 1
ECN package is routed in accordance with the Approval and Responsibility Matrix (Figure 1-2.2).
11.6.5 Execution Work begins upon receipt by either Maintenance or the Construction Engineer of copies of the fully approved ECN package issued by the Design and Drafting Clerk.
11.6.6 Acceptance for projects np.1 involving fissile material, acceptance of the work is documented by signatures of the Project Engineer, the Manager, Plant
~
Maintenance, and the affected manager.
For projects involving fissile material, a physical review of the installation is made prior to introducing fissile material by a Criticality Safety Review Team, consisting of the Criticality Safety Component and the Project Engineer.
The Supervisor, Ra'diological and Industrial Safety, documents the team's approval by signing the ECN form.
l 11.6.6.1 Startuo Council A separate overview of certain projects is provided by a Startup Council prior to acceptance and operation of facilities, services, and equipment which have incurred significant change.
Projects requiring Startup Council review are:
Those having impact on production.
Those with new safety issues or implications.
New major projects (facilities / operations).
Others as determined by the Chairman.
Membership of the Council consists of:
Chairman:
Manager, Process & Equipment Engineering Secretary:
Manager, Equipment & Maintenance Engineering l
AMENDMENT APPLICATION DATE' PAGE NO.:
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ADilANCED NUCLEAR FEMLS CORPORATION gup.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM.1227, NRC DOCKET NO. 701257 PART II - SAFETY DEMONSTRATION REY.
20 At Large:
Manager, Operations-Richland Manager, Safety, Security and Licensing Manager, Quality Assurance Manager, Plant Operations Manager, Materials & Scheduling Manager, Equipment Development & Methods Engineering Manager, Process Support Engineering Responsible Operations Manager Startup Coordinator (usually Project Engineer)_
Startup Council concurrence is required for system operation;
)
however, final authority for approving actual startup rests with the responsible Operations Manager.
11.6.6.2 Acceptance Test If an acceptance test is required prior to turnover of the facility, system, or equipment tc' the operating group, acceptance of the work is accomplished via an Acceptance Test Procedure (ATP).
The ATP is signed off prior to performance by the responsible Engineer, the Manager, Plant Mdntenance, the Supervisor, Radiation and Industrial
- Safety, the responsible engineer's manager, and the Manager, Operations-Richland.
Final acceptance is then documented by signatures of the responsible engineer, his/her manager, the Manager, Plant Maintenance, and the i
affected Onerations manager.
i 11.6.7 Records The ECN record file is maintained by the Design and Drafting Clerk.
Included in completed files are the original ECN's, a set of detailed drawings, specifications, applicable excavation and penetration permits, copy of any Criticality Safety Evaluation requests, and the completed ATP.
Copies of safety, hazard, and criticality safety analysis are maintained by the Project Engineer and/or the persor. performing the analysis.
j 11.6.8 Procedure Chances The ECN procedure is prepared and maintained by the Manager, Equipment and Maintenance Engineering.
It is periodically reviewed for effectiveness, and revised as necessary.
AMENDMENT APPUCATION DATE PAGE NO.:
ANF-3830 OSI A (S/88)
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