ML20138J670
| ML20138J670 | |
| Person / Time | |
|---|---|
| Site: | 07000734 |
| Issue date: | 12/31/1985 |
| From: | GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER |
| To: | |
| Shared Package | |
| ML20138J665 | List: |
| References | |
| PROC-851231, NUDOCS 8512170605 | |
| Download: ML20138J670 (22) | |
Text
.
COPY NO.
PART II' SPECIFICATIONS VOLUME SNM-696 MATERIAL LICENSE RENE4AL GA TECNOLOGIES INC.
SAN DIEGO SITE 4
4
+
Submitted July 1981 l
Revision 1 November 1982 Revision 2, November 1983 Revision 3, April 1984 i
Revision 4. June 1984 Revision 5, April 1984 Revision 6 December 1985 U. S. Nuclear Regulatory Comerission Docket No.70-732 3
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TABLE OF CONTENTS 1.
MATERIAL LICENSE LIMITS II 1-1 2.
AUTHORIZED ACTIVITIES II 2-1 3
ORGANIZATION AND ADMINISTRATIVE PROCEDURES II 3-1 3.1 GENERAL II 3-1 3.2 RESPONSIBLE ORGANIZATIONS II 3-1 3.2.1 Operating Groups II 3-1 3.2.2 Quality Assurance & Compliance Division (QACD)
II 3-2 3.2.3 Criticality and Radiation Safety Ccamittee (CRSC).
II 3-5 3.3 POSITION QUALIFICATIONS & TRAINING II 3-6 3.3.1. Facility Managers II 3-6 3.3.2 QACD.
II 3-6 3.3.3 CRSC.
II 3-8 3.3.4 Independent Nuclear Safety Reviewers II 3-8 3.3.5 Training II 3-9 3.4 WORK AUTHORIZATIONS II 3-10 3.4.1 WA Procedure II 3-10 3.4.2 Criteria for WA Approval II 3-12 3.5 RADIOLOGICAL WORK PERMIT II 3-13 3.6 INTERNAL INSPECTION AND AUDIT.
II 3-13 3.6.1 Inspections'and Reviews II 3-13 3.6.2 Audits II 3-14 3.7 OPERATING POLICIES AND PROCEDURES II 3-14 3.7.1 General.
II 3-14 3.7.2 Activities Requiring Procedures.
II 3-14 3.7.3 Unusual Events II 3-15 4
RADIOLOGICAL SAFETY.
II 4-1 4.1 PERSONNEL EXPOSURE CONTROL.
II 4-1 4.1.1 Controlled Access II 4-1 4.1.2 Work Places II 4-1
'4.1.3 Personnel Monitoring II 4-4 4.1.4 Surveillance-II'4-6 4.1.5 Sealed Plutonium Source Leak Testing II 4-9 License No.
SNM-696 License Amendment No.
Page
' Revision No.
6 Date 12/85 Released By II i
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3.-
ORGANIZATION AND' ADMINISTRATIVE' PROCEDURES F
3.1 GENERAL
]
This section describes the organizations, ' positions, and administrative
' procedures utilized to control the use of special nuclear material (see Fig.
II 3.1-1).
i l
The-licensee may change organizational responsibilities, reporting loca-t j
tiens and names providing such changes do not adversely affect the implementa-i tion of license conditions and are reported to the NRC within 60 days after
_the change has been made.
3.2 RESPONSIBLE-ORGANIZATIONS i
3.2.1 Operating Groups i
j All-operating groups are required by company policy to conduct their
}
respective activities within federal, state, and local rules and regulations, license criteria, and company policy, criteria and established practices.
Such policy requires. operating groups to conduct their operations so that radiation exposures to employees and the general public are as low as l
i reasonably achievable.
I The responsibility for safe operation and control of activities in a
}
specific SNM cr restricted area and for the safety of the environs as in-fluenced by the activities conducted therein shall be vested in the manager of each facility er his or her designee. The manager or designee shall ensure that the conduct of activities within the. area is in compliance with all ap-I plicable criteria, rules and practices as set forth 'in Work Authorizations
}
issued under this license implementing the Commission's regulations. By con-
..nuous supervision, the manager can take any corrective action necessary to 7
assure license compliance.
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1 License No.
SNM-696 License Amendment No.
Page Revision No.
6 Date -12/85 Released By II 3-1
3.2.2 Compliance Functions The functions responsible for assuring compliance with applicable license requirements and centrolling the radiological and nuclear safety and safe-guards of licensed material are: Nuclear Safety, Licensing and Nuclear Mater-ial Control, Nuclear Material Accountability, Statistics & Measurement Con-trol, Security, and Health Physics.
The corporation's Secretary, and the Director of Human Resources will es-tablish the necessary policies of operation, cause them to be published in company-wide guides and manuals, and coordinate related activities with oper-ating groups to. assure compliance with related policies, procedures, regula-tions and license conditions.
The Nuclear Safety and the Licensing and Nuclear Material Centrol (LNMC) functions repcrt to the corporation's Secretary.
Included in LNMC are the Nuclear Material Accountability ar.d the Statistics & Measurement Control functions. The Security and Health Physics & Safety Services functions report to the Director of Human Resources. However, matters regarding the establish-ment and the implementation of company policies and procedures to ensure con-formance with governmental requirements as stipulated in regulations, permits and licenses which involve Security and Health Physics are also subject t,o coordination with, and review and approval by (and in urgent situations, if necessary, direction by) the Secretary or his designee.
The managers of each of the above functions are responsible for reporting to the Secretary all matters important to the company's effectiveness in ful-filling its license commitments, and the Secretary is vested with the respon-sibility and the authority to coordinate and act as the focal point of the company's management with respect to all such matters. Thus, each of the managers of these functions has direct access to the highest level of author-ity in reporting such matters to the Secretary, the Secretary reports directly to the president. See figure II 3.1-1.
License No.
SNM-696 License Amendment No.
Page Revision No.
6 Date 12/85 Released By II 3-2
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The compliance functions are described below and are headed by managers or supervisors which are synonymous titles for signifying the responsible person.
3.2.2.1 Health Physics q
This function assures compliance with Title 10 Code of Federal Regula-l tions, Parts 19 and 20 and license-imposed radiological safety requirements.
This function provides a review and approval function for radiological sofety of proposed activities involving SNM, an ongoing monitoring of SNM activities, and provides services such as personnel monitoring, dose rate measurement, ra-dioactive material detection and assay, air and water sampling and environmen-l tal monitoring. Health Physics maintains a manual entitled " Radio 3ogical Safety Guide," implementing the procedural requirements for radiological safety and approves the content of training programs in radiological safety.
The major responsibilities of the Health Physics Technicians are to conduct routine, special and emergency radiological surveys on all operations, equipment, facilities and personnel in any controlled area and to provide advisory and menitoring services in radiological and nuclear safety.
3.2.2.2 Nuclear Safety-This function assures nuclear criticality safety.
This function pro-vides review and approval, for nuclear safety purposes, of proposed SNM activities, reviews proposed changes in processes, equipment, and procedures, and performs frequent inspection and monitoring to assure adequate implemen-tation of nuclear safety controls. This function approves for adequacy all determinations of criticality limits and provides and/or obtains independent j
verification thereof as well as approves the content of training programs in nuclear criticality safety.
I License No.
SNM-696 License Amendment No.
Page Reviston No.
6 Date 12/85 Released By II 3-3
3.2.2.3 Licensing and Nuclear Material Control (LNMC) l This function administers licenses and reviews and approves all Work l
Authori::ations (WA) involving SNM for compliance to applicable regulation and license conditions. 'Ihis function provides interpretation of licenses and regulations, determines the need for licensing actions, coordinates the prep-aration and processing of applications, disseminates license requirements to operating organizations, and maintains or oversees maintenance of master lic-ense records to permit independent review by NRC or GA audit functions.
In addition, this function supervises and is responsible for the overall plan-ning, coordination, and administration of the special nuclear material meas-urement control.and accounting functions.
3.2.2.4 Nuclear Materials Accountability (NMA) l This function assures compliance with SNM custody and control regula-tiens, rules and practices. This function implements the program for ac-countability, custody and control of special nuclear material.
NMA maintains a manual of SNM accounting control procedures.
NMA assures compliance with safeguards material control and accountability regulations and license conditions.
3.2.2.5 statistics & Measurement Control (SvC)
~his function is responsible for implementing the measurement control progra= as it relates to SNM control and accountability. This function as-sures SNM measurement quality by monitoring and evaluating applicable infor-mation, practices and procedures. This function is also responsible for maintaining a SNM Measurements & Statistical Control Manual setting forth the procedures for implementation of measurements, measurement control and sta-tistical control requirements, and implements the program for furnishing measurement and statistical information for inventories, receipts, and shipments.
License No.
SNM-696 License Amendment No.
Page i
3.2.2.6 Security l
This function provides security measures to prevent unauthorized access l
to special nuclear material and to provide appropriate industrial security.
The security function is responsible for assuring compliance with Security regulations and license conditions. This includes maintaining a force of guards who carry out the required guard orders established by the Manager of Security or his designee. The security functions include the following:
(1) maintenance of a Security Office, (2) responsibility for the physical protec-tion of controlled areas, protected areas, vital areas, and material access areas, as required (3) provision for monitoring the fire and intrusion alarms and related communication systems, (4) implementation of security inspection procedures, and (5) assuring adequate physical protection of classified in-l
' formation.
3 2.3 Criticality and Radiation Safety Committee (CRSC) 4 j
The CRSC reports to the office of the President via a designated vice-president. Committee members who have diverse expertise and qualifications prescribed in Section 3.3.3, are appointed by the company's Executive Com-mittee.
A written policy statement establishes committee and member respon-sibilities.
As a minimum, the committee: (1) acts in a radiological safety advisory capacity; (2) reviews policies and criteria ' established for safety of SNM operations; (3) provides second level of review for nuclear safety analy-sis; and (4) audits work involving radioactive materials for conformance to and effectiveness of applicable procedures and practices including a review to determine how exposures might be reduced to meet ALARA. All results of CRSC meetings will be documented.
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I License No.
SNM-696 License Amendment No.
Page I
Revision No.
6 Date 12/85,
Released By II 3-5
3.3 POSITION QUALIFICATIONS * & TRAINING 3.3.1 Facility Managers A Facility Manager shall have demonstrated his/her proficiency in activ-ities relevant to the functions assigned, as defined in paragraph 3.2.1.
Dem-onstration of this proficiency shall be based on the manager's qualifications which shall include an accredited four-year college degree, a minimum of two years applicable work experience and/or training in nuclear activities, and 4
knowledge of the licensee's radiation protection program.
3.3.2 Compliance Functions I
t The Corporation Secretary and the Director of Human Resources will be re-sponsible for assuring compliance with applicable licensing requirements and controlling the radiological and nuclear safety and safeguards of licensed material, as generally defined in Paragraph 3.2.2.
Incumbents must have a 4.
minimum of five years of nuclear industry management experience of a high level general management nature.
The Manager of Health Physics shall have demonstrated his/her proficiency I
in nuclear health physics activities, and the evaluation of potential radio-j logical hazards, such as defined in paragraph 3.2.2'.1.
Demonstration of this j
proficiency shall be based on the manager's qualifications which shall include I
an accredited four-year college degree in the physical sciences, biological f
sciences, or other related field and a =inimum of two years experience in
)
phases of nuclear health physics relating to GA licensed activities and the evaluation of potential radiological hazards therefrom, or equivalent work experience or trainin3
'A two-year degree plus five years of directly applicable experience or a high school diploma (or equivalent) plus 10 years of directly applicable experience 1
may be considered equivalent to an accredited 'four-year college degree and appropriate work experience, subject to a determination by the Secretary and the Director of Human Resources that proficiency has been demonstrated. A
-master's or doctor's degree' in science or engineering from an accredited col-lege is considered equivalent to two years of applicable experience.
License No.
SNM-696 License Amendment No.
Page.
1 Revision No.
6 Date 12/85 Released By II 3-6
The Manager, Nuclear Safety shall have demonstrated hits her proficiency in activities of nuclear safety and outside reactor criticality safety, such as defined in paragraph 3.2.2.2.
Demonstration of this proficiency shall be based on the manager's qualifications which shall include an accredited four-year college degree in science, engineering or other related field and a min-imum of two years experience and/or training in nuclear safety activities re-lated to nuclear fuel fabrication operations, or one year of such experience and/or training plus two years of other nuclear safety experience and/or training.
The Manager, Licensing and Nuclear Material Control shall have demon-strated his/her. proficiency in activities relevant to the functions assigned, 1
as defined in Paragraph 3.2.2.3 Demonstration of this proficiency shall be based on the manager's qualifications which shall include an accredited four-year college degree in a relevant field and a minimum of two years applicable work experience and/or training in nuclear facility activities.
The Manager, Nuclear Materials Accountability shall have demonstrated his/her proficiency in activities relevant to the functions assigned, as de-fined in Paragraph 3.2.2.4 Demonstration of this proficiency shall be based on the manager's qualifications which shall include an accredited four-year college degree in a relevant' field and a minimum of two years applicable work experience and/or training in nuclear material accountability and control activities.
The Manager, Statistics and Measurement Control shall have demonstrated his/her proficiency in activities relevant to the functions assigned, as defined in paragraph 3.2.2.5.
Demonstration of this proficiency shall be
)
based on the manager's qualifications wiich shall include an accredited four-year college degree in science, engineering or other related field and a minimum of two years applicable work experience and/or training in quality assurance / control, statistics, nuclear measurements, or related activities.
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SNM-696 License Amendment No.
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The Manager, Security, shall have demonstrated his/her proficiency in activities relevant to the functions assigned, as defined in paragraph 3.2.2.6.
Demonstration of this proficiency shall be based on the manager's qualifications which shall include an accredited four-year degree and a minimum of two years applicable work experience and/or training in managing or i
implementing security programs in the nuclear industry.
A Health Physics Technician shall have demonstrated his/her proficiency in activities relevant to the functions assigned, as described in Section 3.2.2.1.
Demonstration of this proficiency shall be based on the technician's qualifications which shall include a high school diploma or equivalent, and a minimum of two years applicable work experience and/or training related to nuclear activities, including at least three (3) weeks of specific on the job i
training.
1 3.3.3' CRSC s
Members of the committee shall have expertise in their special fields.
Such expertise shall, as a minimum for technical members, require an accredi-ted college degree or equivalent training in a field appropriate to their specialties and a minimum of two years related experience. For nontechnical l
members, a minimum of three years experience in an appropriate field is re-i quired.
i The fields of specialty shall include.as a minimum, disciplines from nue-lear physics, reactor physics, health physics, chemistry and statistics. A member may represent more than one field of specialty.
1 3.3.4 Independent Nuclear Safety Reviewers Employees performing independent nuclear safety analysis and review shall have similar qttalifications to those specified in Section 3.3.2 for the Mana-I ger, Nuclear Safety. Each of the parties may have their relevant experience i
License No. SNM-696 License Amendment No.
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in a different specific phase, but this will allow broader expertise to be utilized.
In each case individuals shall have their qualifications reviewed and approved by the Manager of the reviewing organization, Nuclecr Safety or the Chairman, CRSC.
3.3.5 Training Authorized Users - Employees who handle SNM other than under the direct supervision of another trained individual, must have satisfactorily completed the Radiological Safety Course which includes the following topics: ALARA practices, an ir.troduction to 10 CFR 19 and 10 CFR 20, radiological instrumen-tation and controls, decontamination procedures, fire protection and emergency procedures. General subjects such as the nature and sources of radiation, units, methods of controlling contamination, interactions of radiation and matter, biological effects of radiation, use of monitoring equipment, prin-ciples of nuclear criticality safety and risks from occupational radiation exposure are also covered. The course is presented by lectures and demon-strations including the use of selected audiovisual aids.
The understanding of the employees and the effectiveness of the training course are evaluated with an examination given at the end of the course. Em-playees are required to pass the written examination with a grade of 70 per-cent before being allowed to handle radioactive material without direct super-vision. The exam includes radiological practices and nuclear safety princi-ples.
The Manager, Health Physics, or other qualified designee is responsible for the radiological safety training course content.
Retraining - Retraining on selected subjects will be done annually. Sub-jects will include both radiological and nuclear safety controls.
The under-standing of the employees and the program's effectiveness will be evaluated with an examination which must be satisfactorily completed with a score of 70 percent.
Records of the training will be kept which will include the date held, subject matter covered, attendees, instruction and test results.
The Manager, Health Physics or other qualified designee is responsible for this training.
License No.
. License Amendment No.
Page n-rt, tan nn, A
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Health Physics Technician Training - All Health Physics Technicians shall successfully complete the Radiological Safety Course described above and re-i ceive on-the-job training.
Additional Nuclear Safety Training shall be given to enable them to do nuclear safety monitoring on a " continuous basis" in areas where more than 500 grams of U-235 is handled., Training will include tcpics such as characteristics of criticality, principles of nuclear safety, specific SNM station limits and justifying criteria and details of postulated criticality accidents.
Records of training include the date held, subject matter covered, at l
tendees, instructor and test results.
Such records will be kept for two (2) years or longer if so required by Part 19 or 20.
3.4 WORK AUTHORIZATIONS Any operating group desiring to initiate new work or to make changes in previously approved work involving special nuclear material subject to this license may do so only upon receipt of proper authorization. Procedural re-quirements and instructions for obtaining Work Authorizations (WA) are to be maintained in current form in the Radiological Safety Guide. The basic pro-cedure for obtaining approval of a Work Authorization is described in section 3.4.1 and is shown schematically in Figure II 3.4.1.
Changes to this proced-ure require review and approval by the Manager of Licensing & Nuclear Material Control, the Secretary, the Director of Human Resources, and the Chairman of CRSC, or their designees.
All such changes must be within limitations of this license.
The criteria for WA approval are contained in Section 3.4.2.
3.4.1 Procedure for Approval of Work Authorizations 1.
The operating group desiring to do the work shall prepare a Work Au-thorization (WA) request identifying the proposed work and quantity and form of SNM to be used as well as drafts of the necessary safety related procedures, equipment features, and process characteristics.
License No.
SNM-696 License Amendment No.
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The WA shall be approved in writing by the applicable manager who t
must assert that all license and company criteria and procedures for radiological safety, criticality, material accountability and con-trol, and physical protection requirements will be met.
Also, he must assert that other applicable safety related features of the work, such as structural integrity, potential of fire or explosion and the like, are adequately considered and suitable provisions have been incorporated.
The approved WA and backup information shall then be forwarded to Health Physics.
l 2.
The WA and appropriate safety related information shall be approved in writing by Health Physics, Nuclear Safety, Nuclear Materials Ao-countability, and Licensing & Nuclear Material Control.
In add-ition, the request shall be sent to (1) Security for approval if physical protection requirements for the area are to be modified, and (2) CRSC for approval if the WA is for new or changed work involving new or revised nuclear safety analysis and involves a quantity of SNM greater than 350 sm of U-235, 200 se of U-233, 200 gm of encapsulated plutonium, or any quantity of unencapsulated plutonium of any isotope.
If a license modification is required, Licensing & Nuclear Material Control shall make the determination and take appropriate action with governmental regulatory author-ities. Any reviewer shall seek outside e' pertise as deemed x
necessary.
3.
After the WA has been approved in writing, authorization shall be deemed granted.
Authorization shall include any special conditions required by the license and such other conditions as the reviewers deem necessary.
4 4
The originating department shall revise, where appropriate, the operating procedures and practices before implementing requested work.
The current version of Work Authorization and the approved procedures will be available in or near the applicable work area.
1 License No.
SNM-696 License Amendment No.
Page naut, ton tro, 6
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5.
All SNM Work Authorizations will be re-reviewed and approvals updated at least every three years.
6.
Work Authorization records including supporting criticality analysis shall be retained for at least six months following the expiration date of the authorization.
3.4.2 CRITERIA FOR WA APPROVAL Evaluation of each request for WA approval shall include but not be limited to the following determinations by the manager. or designee, of the respective responsible compliance functions:
1.
That the proposed work is within currently authorized license limits.
2.
That radiological safety is properly assured. his includes a review of operational methods to attain "as low as reasonably achievable" radiation exposures.
3.
That criticality safety has been reviewed and adequate provisions j
are incorporated.
4 nat new or revised nuclear safety analysis has been separately verified by two independent parties. Analysis of solid angles of interaction require verification by a single independent party.
I 5.
Bat proper SNM accountability control is pruvided.
6.
That proper material protection for SNM is provided and that ap-plicable limits and regulations are observed.
i 7.
That an assessment of the effluents has been performed and proper provisions for control exist.
License No.
SNM-696 License Amendment No.
Page Ra'stston Mo.
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Ra1.a1mf 5 II 1-12
T 8.
That industrial safety practices and procedures are considered as they relate to radiological and nuclear safety.
3.5 RADIOLOGICAL WORK PERMIT The Radiological Work Permit (RWP) is intended primarily for authori-zation of temporarily assigned GA employees who are not on a Work Authori-zation, or outside contractors or sub' contractor personnel who will perform limited or routine work in a Controlled Area, but whose exposure to possible radiation or contamination is incidental to their function.
3.6 INTERNAL INSPECTION AND AUDIT 3.6.1 Inspections and Reviews Inspections and reviews of activities involving materials subject to this license are perfor=ed by Health Physics, Nuclear Safety, Nuclear Materials Accountability, and Security. A Health Physics quarterly inspection
- of the l
SNM activities subject to this license shall be made by the Manager, Health Physics or qualified designee. The Manager, Nuclear Safety, or his designee performs criticality inspections
- of all areas possessing SNM as follows: at least once annually for all areas and at least quarterly for areas possessing more than 500 g of fissile SNM. The NMA inspections and reviews are conducted in accordance with requirements of the license Safeguards Amendment SG-1 and the approved FNMC Plan. Security conducts tests and inspections as required by the license Safeguards Amendment SG-1 and approved security plans. Find-ings as a result of inspections shall be reported in writing to the facility manager, the Directors of the operating division, the Secretary, the Director of Human Resources, and the Chairman of CRSC.
The Secretary or his designee shall follow up and assure that necessary corrective actions are taken.
'These shall be conducted according to a written plan which will include, but not limited to, the scope of identified discrepancies, unusual events, corree-tive actions, review of operations involving any substantially new activity.
l License No.
SNM-696 License Amendment No.
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3.6.2 Audits Audits
- are performed by the CRSC at least once each calendar year with l
no interval over 15 months for areas containing more than 500 gm of SNM to verify that work is being done in compliance with approved plans and pro-cedures. Such audits are reported in writing to the responsible management, the audited organization, the Secretary, and the Director of Human Resources.
Copies of the audit reports will be forwarded to the affected Vice Presidents.
The Secretary or his designee shall follow up problem areas and implement needed corrective action.
3.7 OPERATING POLICIES AND PROCEDURES 3.7.1 General Policies applicable to work with materials subject to this license shall 1
be approved by the Secretary and the Director of Human Resources, or their designees, and as applicable, receive prior review by CRSC. Design criteria applicable to work with materials subject to this license shall be approved by the Manager, Licensing & Nuclear Material Control, and the Manager, Nuclear Safety, or their designees, and as applicable receive prior review by CRSC.
Any operating department may'have additional and more stringent criteria or procedures providing such procedures are within approved policies and cri-teria.
3.7.2 Activities Recuiring Procedures Procedures are required for all activities in which materials subject to this license are physically handled, stored and chemically or physically changed.
'These shall be conducted according to a written plan which will include, but not limited to, the scope of identified discrepancies, unusual events, correc-tive actions, review of operations involving any substantially new activity.
License No.
SNM-696 License Amendment No.
Page Revision No.
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3.7.3 Unusual Events Any unusual event which significantly threatens or lessens the effective-ness of radiological or health safety provisions of the license will be in-vestigated and reported to the Secretary, the Director of Human Resources, and the applicable vice presidents.
The Secretary, and the Director of Human Re-sources are responsible for conducting an investigation and documenting the corrective action or reports resulting therefrom in the respective areas for which they are responsible.
All such documents or reports shall be subject to review and approval by the Secretary, or his designee.
NRC shall be notified in accordance with requirements of 10 CFR 19, 20, 21, 70 or 73 5
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PRESI I
VIA VICE P1 SECRETARY EXECUTIVE FINAN COMMITTEE ADMINIS STANDING OIRE COMMITTEES
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- 4. PilYSICAL PROTECTION
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l-Mr. Meldon H. Merrill. Manager. Nuclear Safety B.S., Mechanical Engineering, University of California, Berkeley, 1958.
N.S., Nuclear Engineering, University of Washington,1960.
Registered Professional Engineer (Nuclear), California.
Mr. Merrill joined GA Technologies in 1960 and has worked for 25 years in the field of reactor physics.
From 1960 through 1967, he was assigned to the Nuclear Analysis Group on the Peach Bottom ETGR Project.
His work on Peach Bottom physics design and analysis included preliminary design, safety analysis for preliminary and final hazards reports, analy-sis of critical experiments, design of test elements for the second core, l
planning of startup and rise-to-power physics experiment programs, and i
performing and analyzing experiments at the site.
The safety analysis included out-of-core criticality calculation for stored fuel elements.
From 1967 to 1969, he worked on HTGR fuel cycle analysis in the com-pany's European office. From 1970 to 1973, he was in charge of reactor physics for the Thermionic Reactor Project.
In 1972, he directed nuclear safety analysis for criticality of spent LWR fuel at the Barnwell repro-cessing plant built by GA and Allied Chemical.
From May 1973 to December 1973, he was assigned as Liaison Repre-sentative at the CEA Laboratories in Saclay, France, as part of a joint GA-CEA research program on ETGR fuel. This principally involved HTGR fuel manufacturing based on GA's fuel technology (process specifications and equipment), fuel irradiation, testing and core design verification tests carried out by the French CEA. He subsequently returned to San Diego and directed GA's portion of this program as Manager, Foreign Fuel Progr ams.
In the course of five years spent on these assignments, he f
ccnducted numerous escorts of French visitors through GA's fuel manu-facturing plant during the time much of the newer equipment was being installed. Similarly, he escorted GA visitors through the French CEA's l
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versions of the same process equipment, and he translated many documents related to HTGR fuel process technology. Be thus has intimate familiar-
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ity with the HTGR fuel manufacturing processes, equipment and procedures, and associated nuclear safety considerations.
From 1977 on, he has worked on proliferation-resistant fuel cycles for the n'TGR and the HTGR version of the New Production Reacter, includ-ing out-of-core criticality analysis for the latter, which has unusually heavy fuel loadings. Other assignments in this period included on-site startup physics experiments at the Fort St. Vrain HTGR and FSAR prepar-ation for an LWR plant at Bechtel Corporation. Most recently, he has been responsible for reactor physics and shielding for a thermionic space reactor under the SP-100 program including out-of-core criticality analy-sis for re-entry and launch abort situations involving water flooding, compaction and dispersal.
Mr. Merrill also has had extensive experience with reactor kinetics, including development of a coupled point kinetics-heat transfer computer code used for HTGR, GCFR, and TRIGA analysis, participation in develop-ment and testing of a space-dependent kinetics code and co-authorship (with H.B. Stewart) of a chapter " Kinetics of Solid-Moderated Reactors" for the AEC-sponscred book, "The Technology of Nuclear Reacter Safety" (MIT Press,1964).
In 1973, he wrote a Licensing Topical report on nuclear analysis methods in use at GA Technologists.
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