ML20147B725
| ML20147B725 | |
| Person / Time | |
|---|---|
| Site: | 07000754 |
| Issue date: | 11/07/1978 |
| From: | Cunningham G GENERAL ELECTRIC CO. |
| To: | Kratzke R NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| NUDOCS 7812180018 | |
| Download: ML20147B725 (9) | |
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ENGINEERING
- \\ \\3 OENERAL ELECTRIC (COMPANY, P.d. BOX 460. PLEAsANTON, CALIFORNIA 94566 DIVISION November 7, 1978 e
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Fuel Reprocessing and Recycle Branch Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Comission Washington, D.
C., 20555 Attention:
R. T. Kratzke
Reference:
-1) License SNM-960, Docket 70-754
- 2) Application for Renewal of License SNM-960, 8/20/71
Dear Mr. Kratzke:
Enclosed is a revision of Section 10.0 to the proposed Appendix A to License SNM-90 0.
The changes contained in this revision resulted from discussions with you and Mr. Gordon during your visit to the site on September 5 to September 7, 1978.
The paragraph on records (10.8) has not been revised pending completion of a study on quality assurance records control.
Also enclosed is a revised Addendum A to 'Section 2.0 of the safety deconstration-for the renewal of SNM-960. This revision reflects recant personnel changes.
Sincerely, d.C L P
G. E. Cunningham Sr. Licensing Engineer vec Encl.
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- 10. QUALITY ASSURANCE 19.1 SCOPE A quality assurance program shall be provided to assure compliance with requirements of 10CFR70.22(f) for the plutonium processing facility. This program shall be applicable to the
- design, fabrication, procurement, construction,
- testing, operation, and decommissioning of designated structures, systems, and components of the plutonium processing facility which prevent or mitigate the consequences of postulated accidents that could cause undue risk to the health and safety of the public.
The specific facility covered by this plan is the plutonium processing laboratory located in the Building 102 basement and the exhaust ventilation system associated with that faci'ity.
10.2 ORGANIZATION The quality assurance component is defined as that component of the Nuclear Energy Operations with designated responsibility to generate and ensure implementation of the quality assurance program (see Section 4.3).
10.2.i Functions. The functions of the quality assurance component shall exclude direct responsibility for operations involving plutonium processing.
The quality assurance component shall be responsible for generating the quality assurance program, providing advise on quality assurance, testing, and inspection to operating management, and performing necessary audits to ensure implementation of the quality assurance program.
10.2.2 The minimum qualifications of personnel assigned functional responsibilities in the quality assurance component shall be:
1.
Manager. B.S. degree or equivalent qualifications plus five years experience in managerial or project type assignments involving a combination of such fields as engineering, manufacturing, and quality assurance.
2.
Insoection Suoervisor.
B.S. degree plus three years experience in quality control or five years experience in quality control.
10.3 QUALITY ASSURANCE PROGRAM The program shall describe the means for controlling activities affecting the quality of safety related structures, systems and components of the plutonium processing facility.
The program shall be implemented on a graded approach and provides control over activities affecting quality to an extent consistent with their importance to safety.
The program shall provide for indoctrination and training of personnel performing activities affecting quality in order to provide assurance that appropriate proficiency is achieved and maintained.
New - or modifications to existing - safety related structures, systems, and components subject to the quailty assurance program are identified as:
1.
The structure wKcn houses the plutonium processing facility (specifically the walls, ceiling, and floor of the basement plutonium processing laboratory).
License No.
SNM-060 Docket No.
70 -754 Sect. No.
Page 10-1 Date Amends Sect.(s)
2.
The exhaust ventilation system associated with the f acility.
3.
The HEPA filters and associated connecting lines between the components of the ventilation exhaust system for the f acility.
The program shall include provisions for: design control; control of procurement and other documents; control of purchased materials, equipment, and services including supplier qualification requirements; the identification, inventory, and traceability of raw materials, ir> process materials, and finished components; and audits and inspections.
10A PROCEDURES Organizations performing quality related activities within the scope of the quality assurance program are responsible for establishment and maintenance of documented and approved systems and procedures for the performance of that work.
Changes in procedures shall be approved by the same function that authorized their issuance and use unless otherwise specified within the document or b'y governing standard operating procedures.
10J INSPECTION, TEST, OPERATING STATUS, AND CALIBRATION The inspection, test, and operating status shall be indicated by the use of markings such as stamps, tags, labels, routing cards, or other suitable means. The method utilized shall be in accordance with written procedures.
Each organization component or supplier responsible for measuring quality parameters shall be responsible for the inventory, identification, and calibration of all measuring and test equipment used for such inspections.
Jdeasuring and test equipment shall be calibrated traceable to nationally recognized standards, if no national standards exist, the basis for calibration shall be documented. Only equipment which has been calibrated within the prescribed interval shall be used. Records shall be maintained or equipment suitably marked to indicate calibration status.
10.6 INSPECTION AND TESTING Inspection shall be performed for each work operation where it is necessary to assure quality and shall be performed to written plans or procedures. Inspection and approval points shall be identified as appropriate throughout design, fabrication, special processing and assembly. Inspection plans shall be incorporated into the detail planning documents of the performing components.
Tests shall be conducted in accordance with written procedures. Test results shall be documented and evaluated to assure that test requirements have been satisfied.
Modification, repair, or replacement of items performed subsequent to final inspection shall require reinspection or testing as appropriate for reacceptance.
The quality assurance component shall audit the inspection and testing system, as necessary to assure compliance with the appropriate procedures.
10.7 DESIGN CONTROL Design reviews, alternate calculations, or prototype qualification tests shall be required for all new design or for ignificant changes to existing designs. Reviewers shall have no direct responsibility for the initial design.
License No.
SNM-960 Docket No.70-754 Sect. No.
Fage 10-2 Date Amends Sect.(s)
s 10.8 ~ DOCUMENT CONTROL Each organization performing work within the scope of the quality assurance program shall establish a document control system to assure proper review, approval, distribution, and control of documents and their revisions.
Procurement documents shall - be reviewed and approved by the quailty assurance component prior to submittal to the purchasing component.
10.9 CONTROL OF PURCHASED MATERIAL -
Upon receipt of purchased material. receiving inspection - shall be performed for conformance to the requirements of the procurement documents.
Storage areas shall be provided that provide adequate protection for materials and equipment. Materials shall t;e handled and stored in accordance with procedures and/or Instructions estabilshed to prevent loss or damage.
Items found to deviate from soecifications shall be identified, segregated (where practicaD, and described in a deviation /nonconformance report. Disposition of such items shall be documented.
10.10 CONTROL OF SPECIAL PROCESSES Special processes shall be accomplished under controlled conditions in accordance with applicable codes, standards, specifications, or other engineering criteria using appropriately qualified personnel and procedures.
10.11 CORRECTIVE ACTION 4
Corrective actions shall be identified, documented, and implemented in a manner appropriate to the cause and importance of the deficient condition. Necessary followup on committed corrective action shall be performed and documented.
10.12 AUDITS The quality assurance component shall conduct audits in accordance with established procedures and/or checklists to verify compliance with the various elements of this quality assurance program. Audits shall be conducted commensurate with the importance to safety or work history of the item or activity. Audit persorniel shall be independent of any direct. responsibility for performance of the activities which they audit.
Audit reports and corrective action requests shall be documented and distributed to responsible management for resolution. Necessary followup action shall be taken to confirm proper implementation of the corrective action.
10.13 RECORDS Quality assurance' documents are retained by the performing organization and/or' by the quality assurance component.
Duplicate records shall be maintained, one copy at two different locations, to provide for replacement in the event of loss or damage to one' set.
License No.
SNM-960 Docket No.70-754 Sect. No.
Page 10-3 Date Amends Sect.(s) r e
e e
r ADDENDUM A TO SECTION 2.0 PERSONNEL RESUMES License No.
SNM-960 Docket No.70-754 Sect. No. 2.0 Addendum A Page 2-1 A
' Date 5-13-77 Amends Sect.(s)
ADDENDUM A TO SECTION 2.0 RESUMES OF KEY MANAGERIAL AND SAFETY PERSONNEL A.1 R. W. Darmitzel, Manager-Irradiation Processing Product Operation; B.S., Chemical Engineering, University of New Mexco,1958.
Mr. Darmitzel joined the General Electric Company, Vallecitos Nuclear Center (VNC), in 1959 as an engineer responsible for the planning and performance of the post-irradiation examination of nuclear fuel materials. In 1966, Mr. Darmitzel became Manager, Isotope Production and Development, in which capacity he was responsible for the production of radioisotope products and the development of new radioisotope products, particularly for use in the field of nuclear medicine.
This position required interaction with such regulatory agencies as the Food and Drug Administration, the Atomic Energy Commission, and the Department of Transportation. Mr. Darmitzel was active in the Atomic Industrial Forum and the American National Standards Institute.
From 1970 to 1975, Mr. Darmitzel became Manager, Radioactive Products and Services, and was responsible for both radioisotope production and the post-irradiation examination of reactor components in support of the Nuclear Energy Division's reactor development programs.
In 1975, Mr. Darmitzel assumed the position of Manager, IPPO. He is responsible for the operation of the radioisotope production and post-irradiation examination facilities, the operation of two nuclear reacturs, and their support functions including Nuclear Safety.
Mr. Darmitzel has been designated by the, General Managers of the General Electric Divisions represented at VNC as the manager responsible for Nuclear Safety for the entire site.
A.2 E. F. Kurtz, Manager-Advanced Fuels Laboratory; B.S., Ceramics, Pennsylvania State University,1947.
Mr. Kurtz joined General Electric at the Hanford Atomic Power Operation, Richland, Washington, in 1947. During his 14 years at HAPO, Mr. Kurtz was involved in the design, development, and demonstration of equipment and systems to remove radioactive gases and particulates from gaseous effluents and the design, development, and construction of equipment and systems for a plutonium recovery f acility. Mr. Kurtz also served as a team leader for the design and construction of prototype production equipment and for the evaluation and establishment of new processes and equipment for plutonium weapons fabrication.
, In 1962, Mr. Kurtz transferred to VNC where he was a team leader responsible for the design, startup, and operation of the Plutonium Laboratory. Since 1973, as Manager, Plutonium Laboratory, and Manager, Advanced Fuels Laboratory, Mr. Kurtz has been responsible for the over-all plutonium and mixed oxide fuel fabrication campaigns, the development of process technology, the performance of conceptual design studies, and special fuel development projects.
A.3 W. H. Reas, Manager, Nuclear Processes Development; B.S., Chemistry, University of California at Berkeley,1943; Ph.D., Chemistry, University of California at Berkeley, 1948.
Dr. Reas joined General Electric at the Hanford Atomic Power Operation, Richland, Washington, in 1948. During his 16 years at HAPO, Dr. Reas' responsibilities included:
research in the areas of basic plutonium chemistry and processes for the preparation of License No.
SNM-960 Docket No.
70 - 754 Sect. No.
Page 2-2A Data A nends Sect.(s)
plutonium metal; management of technical groups in the areas of plutonium production process improvement studies and research into the physical properties in plutonium metal systems; project management for the design, construction, and operation of a solvent extraction plant for the recovery of plutonium; and management of technical groups concerned with the reprocessing of irradiated reactor fuels, the chemistry of actinide elements, waste disposal, radiological and nuclear safety, equipment deve.opment, and pilot plant operations.
In 1964, Dr. Reas was assigned to VNC with managerial responsibility for the definition and execution of research and development programs for the chemical reprocessing of reactor fuels.
From 1967 to 1973, he was manager of a technical research and development group supporting boiling water reactors with emphasis on nuclear chemistry, reactor chemistry, reactor processes, and metallurgical and ceramics processing. Since 1973, Dr. Reas has been manager of a technical group supporting boiling water reactor program-related activities in the areas of chemical reprocessing, fuels development, nuclear materials property studies, and waste treatment studies.
A.4 R.
A. Moschner, Acting Manager, Nuclear Safety and Quality Assurance; B. S.,
Engineering, St. Louis Univrsity,1958.
Mr. Moschner joined the General Electric Company in 1966 following employment with the Martin Company and Pan American Airways where his assignments included the development of preventative maintenance programs and engineering work on the Gemini program.
From 1966 to 1974 Mr. Moschner was assigned to several General Electric facilities. His work was previously associated with logistics management information systems and various aspects of quality assurance programs.
In 1974 Mr. Moschner became Supervisor, Nuclear Materials Management, at General Electrics reactor fuel fabrication facility at Wilmington, N.C.
His duties included the definition and maintenance of safeguards and SNM accountability measurements systems for the f acility.
Mr. Moschner joined the Vallecitos Nuclear Center in 1976 as the Manager, Safeguards. In addition to duties similar to those performed at Wilmington, he assumed responsibility for an extensive security force and physical protection system.
In March 1973, he was appointed Acting Manager, NS&QA. In this position, he is responsible for the nuclear safety, nuclear materials safeguards, and licensing activities for the VNC site.
Mr.
Moschner is also responsible for quality assurance for License SNM-960 functions.
l Mr. Moschner is a registered professional engineer in the State of California.
A.5 P. S. Webb, Manager Radiological and Environmental Protection, B.S., Mathematics and Biology, Texas Tech University,1967; M.S., Biophysics (Health Physics), Texas A&M University,1970.
Mr. Webb joined the General Electric Company in 1970 as a radiological engineer in the Nuclear Safety Technology unit. Mr. Webb's duties included radiological engineering for two site reactors, radioisotope production f acilities, irradiated fuel examination f acilities, and a mixed oxide fuels laboratory.
In July 1973, Mr. Webb was appointed to his present position. He is responsible for establishing radiation protection standards and practices for VNC and the supervision of health physics specialists and technicians assigned to radiation monitoring. Mr. Webo is License No.
SN M-960 Cocket No.70-754 Sect. No.
Page 2-3A Date Amends Sect.(s)
l also responsible for maintaining the site internal and external dosimetry programs and the site environmental protection program.
A.6 W. H. King, Manager, Nuclear Safety Technology; B.S., Chemistry, University of Missouri,1953.
Mr. King joined General Electric at its Vallecitos Nuclear Center in 1959 as a Radiological Engineer with responsibilities both at VNC and the San Jose f acilities. In this capacity, he participated in the design and development of nealth physics and related methods and procedures including complete radiation, beryllium, and other health monitoring systems.
He has been responsible for the conduct of specific technical investigations related to radiation and toxic chemical hazards including problems involving shielding, ventilation, waste processing and disposal, dosimetry, instrumentation and calibrations, environmental parameters, studies relative to the toxicity of various chemicals on biological systems and the movement of radioactivity in humans.
During this period, Mr. King established numerous training programs and authored or co-authored several publications relative to dosimetry, instrumentation, calibrations, scurces, and considerations of various isotopes in the biosphere.
In 1966, Mr. King transferred to Systems Engineering at the VNC site where he participated in the design,6evelopment and testing of engineered safeguards for reactor and laboratory systems as well as developing and placing into operation complete monitoring systems for criticality detection and site effluent control.
Following this assignment, Mr. King spent approximately one year in Technical Marketing at VNC and then became the Licensing Administrator for the VNC site.
In 1970, Mr. King was appointed Manager, Nuclear Safety Technology, in the site nuclear safety organization.
In this capacity Mr. King has managed the technical personnel responsible for site radiation, criticality, and reactor safety.
A.7 G.
E.
Cunningham, Senior Licensing Engineer; B.S.,
Physics, Louisiana State University,1958.
In 1958, Mr. Cunningham joined tne General Electric Company in Richland, Washington, under the Technical Graduate Rotational Training Program. From 1960 to 1966, while with General Electric in Richland, he was an engineer in the health physics group becoming responsible for all technical aspects of health physics for a chemical reprocessing facility.
His responsibilities included exposure records, development of administrative anci technical procedures, developing bioassay schedules, liaison work with other site components and with the Atomic Energy Commission, dosimetry studies, and environmental surveillance.
From 1966 to 1967, Mr. Cunningham was employed by Isochem, Incorporated, Richland, Washington. His work chiefly involved an investigation into the merits of Cobalt-60 and Cesium-137 for commercial irradiation application.
In 1967, _Mr. Cunningham joined General Electric at VNC as a Criticality Specialist, providing criticality work and consultation for other General Electric sites and provides 1
backup capabilities for site health physics.
In 1971, Mr. Cunningham became responsible for licensing and liaison activities between VNC and the various regulatory agencies.
License No.
$NM-960 Docket No.70-754 Sect. No.
Page 2-4A Date Amends Sect.(s)
\\
l
a From March 1975 to October 1975, Mr. Cunningham assumed the additional responsibility for the establishment of the VNC Physical Security and SNM Accountability Program.
Since October 1975, he has reassumed his duties as the site licensing administrator.
Mr. Cunningham is a Certified Health Physicist and a past member of the Board of Examiners of the American Board of Health Physics.
A.8 W. R. Lloyd, Senior Engineer; B.S., Mechanical Engineering, Stanford University, 1955; M.S., Mechanical, Engineering, Stanford University,1956.
In 1956, Mr. Lloyd was employed at Servomechanisms, Incorporated, as an engineer with prime responsibility for the design and development of electromechanical transducers for aircraf t control systems.
In 1957, he joined the General Electric Company at the Flight Propulsion Laboratory Department in Cincinnati, Ohio, as a design engineer responsible for the preliminary design of a closed cycle nuclear turboprop engine. In 1960, he was appointed Heat Transfer Research Engineer, alkali metal heat transfer research, where he contributed to the design and construction of one boiler and two condenser test sections for a high temperature, two loop alkall-metal system.
Mr. Lloyd joined the Allison Division of General Motors Corporation in 1963 as a Senior Research engineer with prime responsibility in the area of NaK-Argon twophase flow investigation.
In 1966, Mr. Lloyd joined the General Electric Company Nuclear Thermionic Power Operation at VNC as an engineer. His prime duties in this position were the heat transfer, i
hydraulic, and stress analyses of core and system components, and the definition of certain fuel venting system design criteria for these plants.
Mr. Lloyd began his present assignment as engineer in Nuclear Safety in 1970. Prime duties involve the review of experiments prior to irradiation in the site test and research reactors, risk evaluation of certain business ventures and customer proposais, and technical analysis of special problems in the operation of the reactors.
In 1975, Mr. Lloyd was appointed criticality analyst for the VNC site. In this capacity, Mr. Lloyd is responsible for specifying certain features in nuclear fuel processing, storage and on-site transportation so that all operations are safe from criticality viewpoint. Such operations include co-precipitation of mixed oxide powders from plutonium nitrate and uranyi nitrate, fabrication of ceramic oeilets from these powders, and processing to ebtain fission product molybdenum from dissolutions of uranium-aluminum alloy fuel.
A.9 3. S. Kemper, Specialist, Industrial Safety and Fire Prevention.
From 1937 to 1957, Mr. Kemper served in the U. S. Navy. Among his assignments were Chief Engineer for ships to 14,000 tons and safety and maintenance officer. In 1957, Mr.
Kemper joined Westinghouse Electric at Idaho Falls, Idaho, and as a technical compliance inspector his duties included gamma radiography. He also served as a chief reactor plant operator for duel pressurized nuclear reactors and the associated marine propulsion prototype, and he developed the curriculum for and supervised the activities of instructors engaged in the qualification of reactor operators.
In 1964, Mr. Kemper joined General Electric at VNC where he was responsible for maintenance, repair, and minor modifications to the mechanical equipment and fluid systems of a prototype boiling water power reactor. From 1964 to 1966, he served in License No.
SNM-960 Docket No.
7n-754 Sect. No.
Page 2-5A Date Amends Sect.(s)
.