ML20235Q050
| ML20235Q050 | |
| Person / Time | |
|---|---|
| Site: | 07001113 |
| Issue date: | 02/06/1989 |
| From: | Winslow T GENERAL ELECTRIC CO. |
| To: | Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 25170, NUDOCS 8903020476 | |
| Download: ML20235Q050 (69) | |
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RETURN TO 396w r/6-///3 k
GE Nuclear Energy
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Mr.
L. C. Rous 1
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U.S. Nuclear Regulatory Commission 3
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Dear Mr. Rouse:
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Reference:
NRC License SNM-1097, Docket #70-1113
Subject:
LICENSE AMENDMENT REQUEST (REVISION #22)
GE Nuclear Fuel and Components Manufacturing hereby submits a request to revise Part I and Part II of NRC Material License SNM-1097. to this letter describes the revisions made and Attachment 2 is the revised pages.
Chapter 2 is submitted in its entirety since the changes affected the numbering sequence for most of the pages.
Chapter 8 has been updated to reflect the latest Radiological Contingency and Emergency Plan issuance.
Chapter 11 has been updated to describe the current organizational structure and is also submitted in its entirety.
Pursuant to 10 CFR 170.31, a GE check for $150 for processing this U
amendment request will be forwarded under a separate cover.
If you have any questions regarding this matter, please contact me on (919) 675-5461.
Very truly yours, GE NUCLEAR ENERGY T.
Preston Winslow, Manager Licensing & Nuclear Materials Management Lo;;. _.. -..((lN~~ b - -----
Remitter._
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Mr. L. C. Rouse February 6, 1989 Page 1 of 1 ATTACHMENT 1 DESCRIPTION OF REVISIONS Page(s)
Description 8-12 Revised to change the " Effective Date" column to read " Application Date."
This change more accurately reflects what the date represents.
9 Revised to reflect revision to Chapter 8.
10 Revised to reflect changes made to Chapter 11.
I-2.1 -
Revised to include the facility manager's 2.26 responsibilities (Section 2.2.1.1), change " Nuclear
~(Radiation) Safety Function" to " Radiation Safety Function" (Section 2.2.1.4), qualifications (Section I-8.1 2.5.1), and other minor editorial changes.
Revised to reflect Revision 7, dated 12/1/88, to the GE-Wilmington Radiological Contingency & Emergency II-11.1 -
Plan.
11.33 Revised to describe the current organizational structure.
Note:
All changes are noted with an asterisk on the right side of the page corresponding with the line changed.
4 ^
Mr.
L. C.
Rouse February 6, 1.'89 Page 1 of 1 ATTACHMENT 2 REVISION 22 DATED 2/6/89 TO PARTS I AND II OF NRC LICENSE SNM-1097, DOCKET # 70-1113 F
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REVISIONS BY PAGE
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u Application
- Application
- Application *
'Page Date Page Date' Page Date TABLE OF CONTENTS I-1.21 5/16/88 I-3.3 10/23/87 I-1.22 I-3.4-1 10/23/87 I-1.23 I-3.5 2
I-1.24 I-3.6' 10/23/87.
3 I-3.7 4
I-3.8 5
I-3.9 6
CHAPTER 2 I-3.10 7-I-3.11 8-2/06/89 I-2.1 2/06/89
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I-3.12 9
I-2.2 I-3.13 I-2.3 I-3.14 10 I-2.4 I-3.15 11 I-2.5 I-3.16.
12 I-2.6 I-3.17 I-2.7 I-3.18 I-3.19 I-2.8
'PART I I-2.9 I-3.20 I-3.21 I-2.10 I-2.11 I-3.22 I-3.23 CHAPTER 1 I-2.12
-O I-1.1 I-2.13 I-3.24 5/16/88 I-2.14 I-3.25 I-3.26 I-1.2 I-2.15 I-1.3 I-2.16 I-3.27-I-3.28 I-1.4 I-2.17 I-1.5 I-2.18 I-2.19 I-1.6 I-1.7 I-2.20 CHAPTER 4 I-1.8 I-2.21 I-1.9
.I-2.22 I-4.1-10/23/87 I-1.10 I-2.23 I-1.11' I-2.24 I-4.2 I-4.3 I-1.12-I-2.25 I-4.4 I-1.13 I-2.26 I-1.14 I-4.5 I-1.15 I-4.6 I-1.16 I-4.7 I-1.17 CHAPTER 3 I-4.8 I-1.18 I-4.9 I-1.19 I-3.1 10/23/87 I-4.10 I-1.20 I-3.2 I-4.11 I
LICENSE SNM-1097 DATE 2/06/89 Page DOCKET 70-1113 REVISION 22 O
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1 6-REVISIONS BY PAGE Application
- Application
- Application * '
Page Date Page Date Page-Date I-4.12 10/23/87 I-5.22-10/23/87.
I-4.13 I-5.23 I-4.14 I-5.24 I-4.15 I-5.25 I-4.16 I-5.26
.I-4.17 I-5.27 I-4.18 I-5.28 I-4 ~.19 I-5.29 I-4.20 I-5.30
.I-4'.21~
I-5.31 I-4.22 I-4.23 I-4.24 I-4.25 CHAPTER 6 I-6.1 10/23/87 I-6.2 CHAPTER 5 I-6.3 5/16/88 I-6.4 I-5.1
'10/23/87 I-6.5 I-5.2 I-6.6 I-5.3 I-5.4 I-5.5 I-5.6 5/16/88 CHAPTER 7 I-5.7 10/23/87 I-5.8 I-7.1 10/23/87 I-5.9 I-5.10 I-5.11 I-5.12 CHAPTER 8 I-5.13 I-5.14 I-8.1 2/06/89 1
F I-5.15 I-5.16 I-5.17 I-5.18 I-0.19 I-5.20 I-5.21 LICENSE.
SNM-1097 DATE 2/06/89 Page DOCKET 70-1113 REVISION 22 -
f.4 1
REVISIONS BY PAGE Application
- Application
- Application
- 4 Page-Date Page Date Page Date i
II-10.22 7/25/83 II-11.15 2/06/89 PART II II-10.23 II-11.16 II-10.24 II-11.17 II-10.25 II-11.18 CHAPTER 9 II-10.26 II-11.19 II-10.27 II-11.20 II-9.1 7/25/83 II-10.28 II-11.21 II-9.2 II-10.29 II-11.22
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- II-9.3 II-10.30 II-11.23 II-9,4 II-10.31 II-11.24 II-9.5 II-10.32 II-11.25 II-9.6 II-10.33 II-11.26 II-9.7 II-10.34 II-11.27 II-9.8 II-10.35 II-11.28 II-10.36 II-11.29 II-10.37 II-11.30 II-10.38 II-11.31 CHAPTER 10 II-10.39 II-11.32 II-10.40 II-11.33 O
II-10.1 7/25/83 II-10.41 d
II-10.2 II-10.42 II-10.3 II-10.4 CHAPTER 12
'II-10.5 II-10.6 CHAPTER 11 II-12.1 7/25/83 II-12.2 II-10.7 II-11.1 2/06/89 II-12.3 II-10.8 II-12.4 II-10.9 II-11,2 II-10.10 II-11.3 II-12.5 II-12.6 II-10.11 II-11.4 II-12.7 II-10.12 II-11.5 II-10.13 II-11.6 II-12.8 II-12.9 II-10.14 II-11.7 II-12.10 II-10.15 II-11.8 II-10.16 II-11.9 II-12.11 II-12.12 II-10.17 II-11.10 II-12.13 II-10.18 II-11.11 II-10.19 II-11.12 II-12.14 II-10.20 II-11.13 II-12.15 II-12.16 II-10.21 II-11.14 LICENSE SNM-1097 DATE 2/06/89 Page DOCKET 70-1113 REVISION 22 O
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v REVISIONS BY PAGE O-Application
- Application *-
Application
- Page Date Page Date
_P_ age Date' II-12.17 7/25/83 II-13.35 7/25/83 II-13.77-7/25/83 II-12.18 II-13.36 II-13.78 II-13.37 II-13.79-II-12.19 II-13.38 II-13.80-II-13.39 II-13.81 II-13.40 II-13.82 CHAPTER 13 II-13.41 II-13.83 II-13.42 II-13.84 II-13.1 7/25/83 II-13.43 II-13.35-II-13.2 II-13.44 II-13.86 II-13.-3 II-13.45' II-13.87 II-13.4 II-13.46 II-13.88~
~II-13.5 II-13.47 II-13.89
'II-13.6 II-13.48 II-13.90 II-13.7' II-13.49 II-13.91 II-13.8 II-13.50 II-13.9.
II-13.51
-II-13.10 II-13.52 II-13.11 II-13.53 CHAPTER 14 II-13.12 II-13.54 II-13.13 II-13.55 II-14.1 7/25/83 II-13.14 II-13.56 II-13.15 II-13.57 II-13.16 II-13.58 II-13.17 II-13.59 CHAPTER 15 II-13.18 II-13.60 II-15.1 9/30/83 II-13.19 II-13.61 II-15.2 II-13.20 II-13.62 II-15.3 II-13.21 II-13.63 II-15.4 II-13.22 II-13.64 II-15.5 II-13.23 II-13.65 II-15.6 II-13.24 II-13.66 II-15.7 II-13.25 II-13.67 II-15.8 II-13.26 II-13.68 II-15.9 II-13.27 II-13.69 II-15.10 II-13.28 II-13.70 II-15.11 II-13.29 II-13.71 II-15.12 II-13.30 II-13.72 II-15.13 II-13.31.
II-13.73 II-15.14 II-13.32 II-13.74 II-15.15 II-13.33 II-13.75 II-15.16 II-13.34 II-13.76 II-15.17 1
LICENSE SNM-1097 DATE 2/06/89 Page DOCKET 70-1113 REVISION 22 _ - - -
4 REVISIONS BY.PAGE
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Application *
- Application
- Application
- Page Date Page Date Page Date II-15.18 9/30/83 II-16.8.
9/30/83-II-16.50 9/30/83 II-15.19 II-16.9 II-16.51 L
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-II-15.20-II-16.10-II-16.52 II-15.21' II-16.11-II-16.53 II-15.22
'II-16.12 II-16.54 II-15.23 II-16.13 II-16.55 II-15.24-II-16.14-II-16.56~
II-15.25 II-16.15
.II-16.57 II-15.26 II-16.16 II-16.58 II-15.27 II-16.17 II-16.59 II-15.28.
II-16.18 II-16.60 II-15.29 II-16.19 II-16.61 II-15.30 II-16.20 II-16.62 II-15.31 II-16.21 II-16,63 II-15.32
-II-16.22 II-16.64 II-15.33 II-16.23 II-16.65 II-15.34 II-16.24 II-16.66 II-15.35 II-16.25 II-16.67 II-15.36 II-16.26 II-16.68 II-15.37 II-16.27 II-16.69 II-15.38 II-16.28 II-16.70 O
II-15.39 II-16.29 II-16.71 II-15.40 II-16.30 II-16.72 II-15.41 II-16.31 II-16.73 II-15.42 II-16.32.
II-15.43 II-16.33 II-15.44-II-16.34 II-15.45 II-16.35 CHAPTER 17 II-15.46 II-16.36 II-17.1 7/25/83 II-15.47 II-16.37 II-16.38 II-16.39 II-16.40 CHAPTER 16 II-16.41 II-16.42 II-16.1 9/30/83 II-16.43 II-16.2 II-16.44 II-16.3 II-16.45 II-16.4 II-16.46 II-16.5 II-16.47 II-16.6 II-16.48 II-16.7 II-16.49 LICENSE SNM-1097 DATE 2/06/89 Page DOCKET 70-1113 REVISION 22 O
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CHAPTER 2 GENERAL ORGANIZATIONAL =& ADMINISTRATIVE REQUIREMENTS.
2.1 POLICY' The GE-W11mington' policy is to maintain a safe work 1
place for its employees and to assure operational compliance within the terms and conditions of special nuclear materials licenses and applicable NRC i
t regulations.
i The GE-Wilmington facility manager or his delegate, has I
the overall responsibility for safety and compliance to-f this policy.
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l In particular, GE-Wilmington has established the l
'.O princ191e of xeepino red 1etion exposures to emp1ovees and the general public as low as reasonably achievable (ALARA).
2.2 ORGANIZATIONAL RESPONSIBILITY & AUTHORITY 2.2.1 Key Positions with Safety Related Responsibilities I
2.2.1.1 Facility Manager The facility manager is the individual who has overall responsibility for safety and activities conducted at LICENSE SNM-1097 DATE 02/06/89 Page DOCKET 70-1113 REVISION 22 I-2.1 O-
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4 the GE-Wilmington facility.
He directs all operations q( j personally, by procedure, or through other management personnel.
His activities are performed in accordance with GE policies, procedures, and management directives.
The facility manager provides for safety and control of operations and protection of the environment by delegating and assigning responsibility to qualified Area Managers.
2.2.1.2 Area Manager The Area Manager is the designated individual in management who is responsible to ensure that all activities necessary for safe operations and protection t
of the environment are conducted properly within his designated area of the plant in which uranium materials are processed, handled or stored.
The responsibility of safe operation and control of activities in the area
()
and for the safety of the environs as influenced by the activities conducted therein is assigned to the Area Manager.
He shall assure approved written operating procedures are used which incorporate radiation and criticality safety controls and limits commensurate with the particular operations involved.
2.2.1.3 Criticality Safety Function The criticality safety function is administratively independent of production responsibilities.
The criticality safety function is the function of GE-Wilmington with designated responsibility for providing I
LICENSE SNM-1097 DATE 02/06/89 Page DOCKET 70-1113 REVISION 22 i
I-2.2 L____._____.___
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1s authoritative professional advice and counsel to Area (o
Managers on matters of control against accidental
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criticality.
These functions include at least the following:
Establishment of a criticality safety control program including criteria, procedures and
- training, 1
Analysis and approval of proposed changes in process conditions and processing equipment involving criticality safety, Measurement of the effectiveness of the criticality control program.
Measurement of the effectiveness of the criticality control program is determined through audit programs to
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assure that nuclear safety criteria are met for the protection of employees, the public and the environment.
2.2.1.4 Radiation Safety Function The radiation safety function is administrative 1y independent of production responsibilities.
The radiation safety function provides authoritative professional advice and counsel to Area Managers on matters of radiation safety and measures the effectiveness of the radiation safety program.
The LICENSE SNM-1097 DATE 02/06/89 Page f^3 DOCKET 70-1113 REVISION 22 I-2.3
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radiation safety function has the responsibility of
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establishing and maintaining the radiation safety program necessary to ensure the protection of employees at GE-Wilmington and the community.
The manager of the radiation safety function shall review and approve the radiation safety progran which shall include at least the following:
Establish the radiation protection and radiation monitoring program, Establish the radiation protection criteria, procedures and training programs to control contamination and exposure to individuals, Evaluation of radiation exposures of employees and visitors and maintenance of related records, o
Emergency planning,
't j Evaluate the integrity and reliability of radiation detection instruments.
Establishment of special conditions for the use of l
laboratory samples containing plutonium and the maintenance of appropriate records, Analysis and approval of proposed changes in process conditions and processing equipment involving radiological safety.
LICENSE SNM-1097 DATE 02/06/89 Page o
DOCKET 70-1113 REVISION 22 I-2.4 i) n 1
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l 2.2.1.5 Radiation Protection Function l
'%.J The radiation protection function is administratively independent of production responsibilities and has the authority to recommend the immediate shutdown of an operation believed to threaten the health and safety of employees or the public.
It is the function designated the responsibility to obtain data relative to radiation exposures of employees and visitors, and to provide operational support to department functions requiring radiation monitoring services.
Radiation protection responsibilities shall include at least the following:
Conduct of radiation monitoring programs, Administration of radiation work permit (RWP) covering nuclear safety requirements,
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Measurements of airborne uranium concentration, contamination levels and external radiation levels, Evaluation of the operational integrity and e
reliability of radiation detection instruments.
Activities are conducted in accordance with approved written procedures.
2.2.1.6 Environmental Protection Function The environmental protection function is administra-tively independel.': of production responsibilities.
It LICENSE SNM-1097 DATE 02/06/89 Page es DOCKET 70-1113 REVISION 22 I-2.5 b
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is defined as that function of GE-Wilmington with
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designated responsibility to include at least the following:
Identification of environmental requirements of federal, state and local regulations governing the department's operation, Establishment of systems and methods to measure and document adherence to regulatory environmental requirements and license conditions, Evaluation and approval of new, existing or revised equipment, processes and procedures involving environmental protection, Assurance of proper federal and state permits, licenses and registrations for non-radiological
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discharges from the facilities.
2.2.1.7 Regulatory Compliance Function The regulatory compliance function is administratively independent of production responsibilities but has the authority to require the shutdown of any process or facility when the Area Manager has not assured or,.
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maintained controls for nuclear safety..T*cli'Ehe function designated to establi.st'17diation safety, criticality safety rnd" environmental protection programs to ensure -cop'liance with federal, state and local m
regulations and laws governing operation of a nuclear LICENSE SNM-1097 DATE 02/06/89 Page es DOCKET 70-1113 REVISION 22 I-2.6 O
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facility.
These programs are designed to ensure the (O) health and safety of employees and the public as well as protection of the environment.
The managers of the criticality safety, the radiation safety, the radiation protection, and environmental protection functions report to the manager of regulatory compliance function.
2.3 SAFETY REVIEW COMMITTEE 2.3.1 Wilmington Safety Review Committee (WSRC) l The functions of the safety review committee shall include responsibility for the following:
1 An annual ALARA review which considers the I
following:
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Programs and projects undertaken by the radiation safety function and the operational radiation safety committee.
Performance including, but not limited to, trends in airborne concentrations of radioactivity, personnel exposures and environmental monitoring results.
Programs for improving the effectiveness of equipment used for effluent and exposure control.
LICENSE SNM-1097 DATE 02/06/89 Page DOCKET 70-1113 REVISION 22 I-2.7
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e-Review of nuclear ~and industrial safety practices
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i( 'J applied to major changes ' made or proposed in authorized plant activities,
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Professional advice-and counsel on criticality and radiation safety issues.
The committee shall consist of at least five senior members of the GE-W1ington technical staff, appointed l
by the GE-Wilmington ac'ility manager and shall include competence in the scientific and engineering disciplines.
Senior' embers of management shall also serve on the committee upon the request of the GE-Wilmington. facility manager.
The committee is responsible to the GE-Wilmington facility. manager.
Its proceedings, findings and recommendations shall be reported in writing to the
()
GE-Wilmington facility manager and to the section level managers responsible for operations which have been reviewed by the committee.
Such reports shall be retained for at least two years.
The committee shall hold at least four meetings each calendar year with a maximum interval of 180 days between any two consecutive meetings.
2.3.2 operational Radiation Safety Committee The objective of the operational Radiation Safety Committee is to improve fuel manufacturing operations so l
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as to affect. visible' improvements in employee I
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radiologicalfexposures and potential health / safety hazards.
i The Committee meets monthly to maintain a continual l
awareness'of the status of containment projects, performance' measurement and trends, and the current shop.
operations radiation safety conditions.
The. maximum-intervals between meetings shall not enceed 60 days.
A written report of.each operational Radiation Safety Committee meeting shall be forwarded to cognizant Area-Managers and the manager of the regulatory compliance function.
The report shall be forwarded within 15 working days of the meeting.
Records of the committee proceedings shall be maintained for.two years.
The Committee shall consist of engineering, shop
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operations, maintenance, radiation safety function, radiation protection function and quality control management or-senior contributors.
2.4 APPROVAL AUTHORITY FOR PERSONNEL SELECTIONS The assignment of individuals to Area Manager, criticality safety and radiation safety functional positions identified in Section 2.2 shall be approved by management at the second organizational level above the position to be staffed.
i LICENSE SNM-1097 DATE 02/06/89 Page DOCKET 70-1113 REVISION 22 I-2.9 1
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. Ass 1gnments-to all other safety-related staff positions h
shall be made within the normal administrative practices-of GE-Wilmington.
2.5 PERSONNEL EDUCATION & EXPERIENCE REQUIREMENTS 2.5.1' Facility Manager-The facility manager shall be an individual who is appointed by upper GE management as the overall manager of the GE-Wilmington facility.
This appointment reflects confidence of his ability as an effective programs and business manager.
He shall be knowledgeable of the criticality control and radiation protection program concepts as they apply to the overall safety of a nuclear facility.
O 2.5.2 Area Manager The minimum qualifications of an Area Manager shall be a BS degree from a college or university in a technical field and two years experience in nuclear fuel plant operation or a high school diploma with ten years experience in nuclear fuel plant operation.
Each Area Manager shall be knowledgeable of the criticality control procedures and the radiation safety program as they relate to their area of responsibility.
LICENSE SNM-1097 DATE 02/06/89 Page DOCKET 70-1113 REVISION 22 I-2.10 O
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Each Area Manager shall have proficiency in the
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application of criticality control procedures and be knowledgeable in the procedures applicable to the area under his management.
Each Area Manager shall have proficiency in the application of a radiation safety program as it relates to limitations and radiological controls for the kind of activities in his assigned radiation or radioactive materials area.
2.5.3 Criticality Safety Function / Radiation Safety Function Manager Criticality safety function / radiation safety function manager (s) shall hold a BS degree in science or engineering, and shall have at least five years of experience in a responsible position in the nuclear
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field such as engineering, physics or chemistry, at least three years of which shall have been in an j
activity which would develop an understanding of criticality problems and five years experience in assignments involving radiation safety.
The criticality safety function and the nuclear safety function responsibilities are currently vested with one manager.
2.5.3.1 Criticality Safety Function The criticality safety function is generally staffed by personnel of three different classifications (senior, LICENSE SNM-1097 DATE 02/06/89 Page DOCKET 70-1113 REVISION 22 I-2.11 I
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junior, trainee / technician).
A senior member holds a
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BS/BA degree in science or engineering with at least two years of experience in criticality safety work and an additional year of experience in either criticality safety or reactor engineering / physics.
A junior member holds a BS/BA degree in science or engineering with at least one year of experience establishing and monitoring criticality safety limits.
The trainee / technicians position is assigned to persons who have the potential to eventually meet the qualifications of at least a junior member.
The criticality safety function shall consist of not less than two technically trained personnel, one of whom must meet the qualifications of a senior member.
At least one of the personnel shall be based at GE-Wilmington.
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The senior member has authority and responsibility to conduct all activities defined in Section 2.2.1.3.
The junior member performs the activities identified in Section 2.2.1.3.
Criticality analyses and approval of proposed changes require an independent review by a senior member prior to being implemented.
The trainee / technician, under the direction of a senior or junior member, assists in the activities defined in Section 2.2.1.3 but has no authority for approval.
l 2.5.3.2 Radiation Safety Function Qualifications for radiation safety engineers or specialists assigned to the radiation safety function LICENSE SNM-1097 DATE 02/06/89 Page DOCKET 70-1113 REVISION 22 I-2.12
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shall vary depending upon position assignments and
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delegated responsibilities.
Such position assignments shall be made and/or approved by the manager of the radiation safety function and his manager.
Qualifications for a senior member of the radiation safety function include a master's degree in science or engineering with no less than three years of experience in general health physics; or a bachelor's degree in science or engineering with no less than five years of experience in general health physics or two years of health physics experience in a nuclear fuel fabrication plant; or certification in health physics.
2.5.4 Radiation Protection Function 2.5.4.1 Radiation Protection Manager
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The qualifications of the manager of the radiation protection function is a BS degree in a scientific field with two years of experience in assignments involving health physics or a high school diploma and eight years health physics experience.
2.5.4.2 Radiation Protection Supervisor 1
Qualifications of a radiation protection monitor and two years of experience as a radiation protection monitor, or at least five years of equivalent experience in the field of radiation protection.
i LICENSE SNM-1097 DATE 02/06/89 Page
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DOCKET 70-1113 REVISION 22 I-2.13 kJ l
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l 2.5.4.3 Radiation Protection Monitor r'T
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Qualifications of a radiation protection trainee plus at least six months experience.
Prior to being certified as a radiation protection monitor, successful completion of a GE training program is required.
This training includes both oral and written examinations covering radiological and criticality control procedures.
2.5.4.4 Radiation Protection Trainee A minimum of a high school education with twelve months monitoring experience or equivalent experience working with radioactive materials; or two years college or technical institute training with mathematics or science major and a minimum of four months monitoring experience or equivalent experience working with l
I radioactive materials.
O 2.5.5 Environmental Protection Manager l
The qualification of the manager of the environmental i
protection function is a BS degree in chemical or environmental engineering plus seven years of related experience or a BS degree in a non-technical field plus ten years of experience in chemical or environmental engineering.
2.5.6 Regulatory Compliance Manager The manager of regulatory compliance function must hold LICENSE SNM-1097 DATE 02/06/89 Page DOCKET 70-1113 REVISION 22 I-2.14
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a BS in science or engineering and have 8 years of
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management experience, of which 5 years must have been in a nuclear facility.
2.6' TRAINING Training policy requires that employees complete formal.
nuclear safety training prior to unescorted access in the controlled area.
The method for evaluating the understanding of employees includes passing an initial examination covering formal training contents..
Such training is performed by-instructors certified by the manager of the criticality safety and radiation safety functions.
Training program contents are reviewed at least every two years by the manager of the criticality safety and radiation safety functions to
()
ensure that training program contents are current and adequate.
Previously trained employees allowed unescorted access to the controlled area are retrained every two years.
The effectiveness of the training program will be measured.
2.7 OPERATING PROCEDURES - ADMINISTRATIVE CONTROLS Licensed material processing is conducted in accordance with properly issued procedures or instructions.
I LICENSE SNM-1097 DATE 02/06/89 Page DOCKET 70-1113 REVISION 22 I-2.15 O
2.7.1 Adopting & Issuing Procedures
~sb Area Managers shall assure preparation of written nuclear safety control procedures incorporating limitations established by the criticality and radiation safety functions.
They shall assure that these procedures are made readily available to operators and other concerned personnel through posting of limits, training programs and other appropriate written notifications.
The radiation protection program is designed to establish and maintain a comprehensive set of written instructions for radiation health and safety practices so as to maintain occupational radiation exposures at levels as low as reasonable achievable.
Such instructions are reviewed by the radiation safety function prior to issuance by appropriate managers.
()
Subsequent procedure review frequencies are as follows:
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0 l
l l
,o O
Reviewing &
- Approving Review Functional Document Frequency. Manager Operational (Process When.
Radiation Safety Requirement.
' changed 1
&. Criticality
& Operator Documents)
Safety Radiation Protection
' Annua 11y2 Radiation Safety (Nuclear Safety
& Criticality Instructions)
Safety Environmental Every 2 Environmental (Environmental Years 8 Protection Protection Instructions) 2The radiation safety and criticality safety portions of these operator procedures are reviewed and updated by the radiation safety and criticality safety functions when warranted based on process related facility change requests..
O
=^e== 117 e e ext=== i=terv 1 er 13 e=ta.
8Every 2 years means a maximum interval of 26 months.
Nuclear safety control procedures for workers in uranium processing areas are incorporated into the appropriate operating, maintenance and test procedures in place'for uranium processing operations.
i LICENSE-SNM-1097 DATE 02/06/89 Page DOCKET 70-1113 REVISION 22 I-2.17
- .O.
I 2.7.2 Changes in Safety-Rolated Procedures c>
1 Activities which do not involve a change in license l
conditions but which require procedures, facilities or equipment substantially different from those previously used are initiated only after the applicable conditions sta'ed below are met:
Cnc9ges which involve radiation hazards considerations are reviewed and evaluated, and approved in writing by the radiation safety
- function, Changes which involve a change in the parameters on which criticality safety was established are analyzed and approved in writing by the criticality safety function and documented by a written criticality analysis.
rm
(_)
2.7.3 Procedures for New or Changed Activities A request for nuclear safety (criticality and radiation safety) analysis is prepared in writing by, or at the direction of, an Area Manager for any proposed new activity or change in activity which may require a proposed change in criticality safety or radiological safety controls.
The changed activity will not be initiated until the nuclear safety analysis demonstrating safety of the activity has been completed, a preoperational inspection LICENSE SNM-1097 DATE 02/06/89 Page ew DOCKET 70-1113 REVISION 22 I-2.18 U
?
I L.. :
has~been conducted to verify that the installation isfin
( [-
accordance with the' nuclear safety analysis, and appropriate procedures and/or instructions are in
]
l place.-
1 i
The results o'f'these analyses are documented in' nuclear safety reviews and maintained for the period of time 1
L they remain applicable and in accordance with the records retention requirements of this license.
1 2.8 AUDITS & INSPECTIONS Written operating procedures are based on GE-Wilmington practices, applicable regulations and license conditions.
Audits are performed to assure that plant operations are conducted in accordance with the-operating procedures.
O.
2.8.1 Criticality Safety & Radiation Safety Internal Audits Quarterly (an interval not to exceed 100 days), senior l
members of the criticality safety and radiation safety functions conduct formal, scheduled safety audits of nuclear manufacturing and support areas in accordance with a procedure approved by the GE-Wilmington facility manager and in accordance with written procedures which have been approved by the manager of the radiation safety and criticality safety functions.
Such audits are performed to determine that actual operations conform to criticality and radiation safety l
requirements.
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)
1
f 4
e Audits are performed by criticality safety'and radiation
().
safety personnel under the direction of the manager of the criticality safety and radiation safety functions.
Personnel performing audits do not report to the production organization and have no direct responsibility for the function and area being audited.
l Violations of license conditions identified during quarterly audits for criticality safety and radiation safety shall be communicated within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to the Area Manager and to the manager of the regulatory compliance function.
Written notifications of such violations shall be provided to the Area Manager and the manager of the regulatory compliance function within 10 working days after the audit.
Corrective actions shall be documented in writing and approved by the Area Manager.
Weekly nuclear safety inspections of all nuclear
()
manufacturing and support areas are conducted in accordance with written procedures and guidance which have been reviewed and approved by the manager of the radiation safety and criticality safety functions, by persons having at least the qualifications of a radiation protection monitor as described in Section 2.5.4.3.
Violations of license conditions identified during weekly inspections are communicated within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to the Area Manager and the manager of the radiation protection function.
Written notification of such violations are provided by the manager of the radiation protection function to the Area Manager and the manager of regulatory compliance function within 10 working days.
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00CKET 70-1113 REVISION 22 I-2.20 V
4 Records of the instructions and procedures, persons
()
conducting the audits or inspections, violations of license conditions identified and corrective actions taken shall be maintained by the radiation safety function or the criticality safety function for a minimum period of 2 years.
9 Audit results in the form of corrective action items are reported to the GE-Wilmington facility manager and his staff for tracking until their closure.
2.8.2 Environmental Protection Internal Audits An audit schedule of the environmental protection program is developed by the environmental protection function on an annual basis.
Audits are conducted in accordance with a written procedure approved by the GE-Wilmington facility manager to ensure that
()
operational activities conform to documented environmental requirements.
Personnel under the direction of the manager of the environmental protection function, perform the environmental protection audits.
Personnel performing the audits do not report to the production organization and have no direct responsibility for the function and area being audited.
Apparent nonconformance is communicated to the Area Manager who is responsible for corrective action commitments jn accordance with documented procedures i
LICENSE SNM-1097 DATE 02/06/89 Page DOCKET 70-1113 REVISION 22 I-2.21
1 approved by the GE-Wilmington facility manager.
The A(,)
manager of the environmental protection function or his delegate is responsible for formal follow-up and closure of identified nonconformances.
Audit results in the form of corrective action items, are reported to the GE-Wilmington facility manager and his staff for tracking until their closure.
2.8.3 External Audits The GE-Wilmington criticality safety anu radiation safety programs are audited at a frequency of every two years by an appropriate function outside of the GE-Wilmington organization.
The audit team is composed of individuals whose audit qualifications are approved by the GE-Wilmington facility manager.
Audit results are reported in writing to the
()
GE-Wilmington facility manager, to the Area Manager, and to the manager of the criticality safety and radiation safety functions.
The criticality safety function, radiation safety function and/or Area Managers, as appropriate, take necessary response actions in accordance with documented corrective action commitments.
Audit results in the form of corrective action items are reported to the GE-Wilmington facility manager and his staff for tracking until their closure.
l l
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l L_____________________________
r 2.9 1 TVESTIGATION & REPORTING OF UNUSUAL OCCURRENCES O
l 2.9.1 Tn.;1 dent Classification All' unusual events which potentially threaten or lessen the effectiveness of health, safety or environmental protection are identified by the Area Manager and reported to the regulatory compliance function.
Each incident is considered in terms of its severity.
Table 2.1 provides general guidelines for use in classification.
2.9.2 Investigation of Unusual Incidents Each reported unusual incident is evaluated to determine the leve1~of investigation required.
These evaluations and investigations are conducted in accordance with approved procedures.
The-depth of the investigation-O depende upon the severity of the incident 1u terme of the levels of uranium released and/or the degree of potential for exposure of workers or the public.
2.10 RECORDS Records appropriate to criticality and radiation safety activities, occupational exposure of personnel to radiation, releases of radioactive materials to the environment, and other pertinent activities, are maintained in such a manner as to demonstrate compliance with license conditions and regulations.
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e
(
TABLE 2.1
[")
INCIDENT CLASSIFICATIONS CATEGORY CLASS I CLASS II CLASS III ONSITE Evidence of apparent Evidence of apparent o Death or disabling PERSONNEL exposure less than exposure less than injury as defined INJURY OR the regulatory five times the under appropriate EXPOSURE limits but greater regulatory limit but OSHA regulations.
than or equal to the greater than the administrative regulatory limits o Evidence of i
guides (internal or (internal or apparent exposure external) external) in excess of or egual to five times the regulatory limit (internal or external)
PROPERTY Damage or loss less Damage or loss DAMAGE than $200,000 but greater than or greater than or equal to $200,000 equal to $50,000 i
VIOLATIONS OF l
LICENSE OR REGULATORY LIMITS:
o Effluent Uranium Uranium Uranium concentra-concentration less concentration less concentration O-tion than permit criteria than 10 times permit greater than or limit for and regulatory criteria but greater equal to 10 times liquid, or limits, but greater than or equal to permit criteria for airborne than or equal to permit criteria for all three categories o In-plant administrative all three categories and in excess of airborne guide and in excess of 500 5,000 times the j
o Contamina-times the regulatory regulatory limit j
tion limit release both inside and outside of controlled area g
SHIPPING &
Damage to container Shipment received Breach of container RECEIVING in excess of externally in-transit offsite administrative contaminated in (loss of integrity guides with no loss excess of license or of container).
of container regulatory limits.
I integrity.
i LICENSE SNM-1097 DATE 02/06/89 Page DOCKET 70-1113 REVISION 22 I-2.24 O
i
t Records of criticality safety analyses are maintained in
,()
sufficient detail and form to permit independent review and audit of the method of calculation and results.
Such records are retained during the conduct of the activity and for six months following cessation of such activities to which they apply.
(Two years minimum.)
Records associated with personnel radiation exposures are generated and retained in such a manner as to comply with the relevant requirements of 10 CFR 20.
The following additional radiation protection records will be maintained for at least two years:
Records of safety review committee meetings, Survey of equipment for release to unrestricted
- areas,
(_)
Instrument calibration, Safety audits, Training and retraining, Radiation work permits, Surface contamination surveys, Concentrations of airborne radioactive material in the facility, Radiological safety analyses.
l l
LICENSE SNM-1097 DATE 02/06/89 Page l
O DOCKET 70-1113 REVISION 22 I-2.25 l
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I L_________________
j
I
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All records acsociated with the environmental protection
-()
activities described in Chapter 5 are generated and retained in such a manner as to comply with the relevant requirements of 10 CFR 20 and this license.
e l
i LICENSE SNM-1097 DATE 02/06/89 Page DOCKET 70-1113 REVISION 22 I-2.26
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t 4
CHAPTER 8
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RADIOLOGICAL CONTINGENCY AND EMERGENCY PLAN GE-Wilmington shall maintain a capability for handling emergencies in accordance with the Radiological Contingency & Emergency Plan, submitted to the NRC on August 27, 1981, and es revised in its entirety on December 1, 1988, in accordance with legulatory provisions.
GE-Wilmington will make no changes to the Plan which would decrease its effectiveness without prior approval of the NRC.
Changes, which do not decrease the effectiveness of the Plan, will be reported within six months of the change to the Chief, Fuel Cycle Safety Branch, Division of Industrial and Medical Nuclear
- Safety, U.S. Nuclear Regulatory Commission, Washington, D.C.
(A,/
20555.
The requirements of the Plan shall be implemented through approved written procedures maintained by GE-Wilmington.
LICENSE SNM-1097 DATE 02/06/89 Page DOCKET 70-1113 REVISION 22 I-8.1
Mr. McMahon joined General Electric in the GE Apprentice
()
Program in Lynn in 1954, graduating in 1958.
Following graduation from Tuf ts University in 1960, he joined the Manufacturing Training Program with assignments in Chicago, Hanford and Fort Wayne.
He joined LJED in Evendale, Ohio at a Test Engineer in 1963 where he held various assignments in manufacturing and quality control.
Since coming to GE-Wilmington in 1971, he has held the i
positions of Manager - Process Control, Manager -
Operational Quality, Manager - Fuels Quality, Manager -
Planning & Projects, and Manager - Equipment and Components Manufacturing.
He was appointed to his present position in 1984.
()
11.5.1.8 Manager - Technology & Automation J.
L. HARMON BS - Metallurgical Engineering Mr. Harmon joined the General Electric Company at the Knolls Atomic Power Laboratory in 1965.
He held the positions of Manager - Physical Metallurgy Laboratories, Manager - Core Manufacturing & Specification Analysis, Manager - Core Materials & Systems Test, and Manager -
Core Manufacturing Engineering.
Mr. Harmon had technical responsibility for product and manufacturing processes for all naval cores for which KAPL had prime LICENSE SNM-1097 DATE 2/06/89 Page DOCKET 70-1113 REVISION 22 II-11.29
E*
l contractor responsibility.
Management assignments 1()F included manufacturing process analysis and the development of manufacturing-specifications as well as material and systems testing evaluation.
In 1977, Mr. Harmon was appointed Manager -
Manufacturing Engineering, Components & Metals, for GE-
-Wilmington.
In this capacity,HMr. Harmon was l
responsible for all aspects of Manufacturing-Engineering in the manufacture of nuclear components and zircaloy metal working.
In 1981, he was appointed to his present-
. position as Manager - Technology & Automation.
In this position, he is responsible for directing the engineering and development efforts at GE-Wilmington.
11.6' TRAINING
(])
11.6.1 Training programs are established for the various types of job functions (such as production operator, radiation protection technician, contractor personnel, etc.),
commensurate with criticality safety and/or radiation safety responsibilities associated with each such position.
Visitors to the controlled area are trained in the formal training program or are escorted by trained personnel while in the controlled areas.
11.6.2 Area Managers ensure the completion of formal nuclear safety training prior to permitting unescorted access into the controlled areas.
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~
Training sessions covering radiation safety, radiation
,,(,)
protection and emergency procedures are conducted on a regular basis so as to cover new employees or those requiring annual retraining.
Topics covered in the training program include:
Notices, reports and instructions to workers.
Plant operational safety devices Practices designed to keep radiation exposures ALARA Methods of controlling radiation exposures Contamination control methods Use of monitoring equipment Emergency procedures and actions Nature and sources of radiation Interaction of radiation and matter Biological effects of radiation Use of personnel monitoring devices Principles of nuclear criticality safety dlk Risk to pregnant females Individuals attending these sessions must pass an c
initial examination covering the training contents so as to assure understanding and effectiveness of the training.
The effectiveness of the training programs is also evaluated by quarterly audits of operational areas and activities conducted by the radiation safety function and the criticality safety function.
Newly hired or transfert,d employees reporting for work prior to the next regularly scheduled monthly training LICENSE SNM-1097 DATE 2/06/89 Page
,o DOCKET 70-1113 REVISION 22 II-11.31
()
session must complete forma 1' interim nuclear safety (k-training prior to unescorted access into the controlled.
area-These individuals are then scheduled to attend the next monthly training session.
Formal interim nuclear safety training topics include:
Radiation protection practices Exposure monitoring devices Exposure units and limits Protective clothing Respiratory protection Personnel surveys Criticality safety Emergency actions Contractor employees who work in the controlled area, are not authorized to move or handle containers of special nuclear material.
Formal training for these
()
personnel'is designed to address the type of work they perform.
In addition to applicable radiation safety topics, training contents include-Radiation Work Permits, special bioassay sampling and special precautions for welding, cutting and grinding in the controlled areas.
These training programs are conducted by instructors certified by the manager of the radiation safety function or his delegate.
11.6.3 Individuals requiring unescorted access to the controlled area are scheduled annually for retraining.
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i
i Retraining for individuals is scheduled and reported by 1
-()
means of a computerized tracking system.
l 11.6.4 Contents of the formal nuclear safety training programs are reviewed at least every two years by the manager of the radiation safety function or his delegate to ensure that the programs are current and adequate.
11.6.5 Operational personnel are further instructed in the specific safety requirements of their work assignments by their immediate supervisor or his delegate during on-the-job training.
Employees must demonstrate understanding of work assignment requirements based on observations by his immediate supervisor or his delegate before working without direct supervision.
Changes to work station procedures, including safety requirements, are reviewed with operational personnel by em
(,)
their immediate supervisor or the supervisor's delegate.
11.6.6 In addition to the formal training programs, radiation safety topics are discussed and reviewed at least annually in roundtable safety meetings held by foremen or supervisors with their workers, and at unit or other component meetings held by managers with their employees.
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.. ^
CHAPTER 11.
ORGANIZATION-& PERSONNEL 11.l' FUNCTIONS General Electric's nuclear energy business, known as GE-Nuclear Energy, is headquartered in San Jose, California, with the manufacturing facility located-in Wilmington, North Caroline.
For the purpose of this document, the Wilmington facility, - currently known as Nuclear Fuel and Components Manufacturing, is identified as GE-Wilmington.
The manufacturing of nuclear fuel, automated nuclear inspection equipment, and reactor components is conducted at GE-Wilmington.
The main functions of GE-Wilmington are fuel production, fuel manufacturing engineering, components-O meaurecturiae. reau1etorv comp 11eace.
eterie18 91emt engineering and maintenance, quality assurance, and technology and automation.
The responsibilities of these organizational functions are described below.
I
-11.1.1 Fuel Production This function manufactures product in accordance with methods prescribed by support functions.
It is responsible for powder production, fabrication, bundle assembly, and the recovery of uranium from waste.
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l.
6 4
11.1.2 Fuel Manufacturing Engineering O
This function provides technical-direction on all manufacturing processes, manufacturing engineering direction for all operations, and support for ongoing process / equipment improvements.
11.1.3 Components Manufacturing This function manufactures fuel components in separate facilities not associated with the uranium manufacturing facility.
11.1.4 Regulatory Compliance This function' establishes radiation safety, criticality safety, and environmental protection programs to ensure compliance with outside regulatory agencies and to
()
protect the health and safety of employees and the public as well as protection of the environment.
The licensing and nuclear materials management function, and the industrial safety function are also within regulatory compliance.
The criticality safety function and radiation safety function are referred to as the nuclear safety engineering function.
11.1.5 Materials This function schedules production operations to assure delivery of products as required; procures direct and indirect materials; and provides receiving and shipping services.
LICENSE SNN-1097 DATE 2/06/89 Page DOCKET 70-1113 REVISION 22 II-11.2 O
I 11.1.6 Plant Engineering and Maintenance
,e3 V
This function provides maintenance and maintenance
(
engineering services for all the fuel manufacturing t
operTtions and support facilities.
It is also responsible for the maintenance and calibration of manufacturing and quality-related equipment and instruments.
11.1.7 Quality Assurance This function assures outgoing product quality via prescribed inspection, and analytical techniques, product specifications and operating procedures.
11.1.8 Technology and Automation This function provides special1 Led automated, state-of-(')
the-art manufacturing / inspection equipment and establishes the technical base for automation of fuel production and equipment manufacturing and for automation of quality assurance systems.
The technology and automation function also provides development and support for the business / manufacturing information systems.
11.2 ORGANIZATION CHART The current GE-Wilmington organization is shown in Figure 11.1 Functions of finance and employee l
LICENSE SNM-1097 DATE 2/06/89 Page DOCKET 70-1113 REVISION 22 II-11.3 p)
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t
E 7-3 -
l' relations are. located at GE-Wilmington, but'are L();
managed from the GE Nuclear Energy headquarters in San Jose, California.
11.3 ORGANIZATIONAL PROCEDURES GE Nuclear Energy has established policies for protection of employees, the public,.and the environs from potential industrial, radiation, and nuclear hazards which could occur because of activities conducted at GE Nuclear Energy plants.
GE Nuclear Energy policies are documented in Policies and Procedures (P&P's).
Responsibility for adherence to these policies at GE-Wilmington rests with the facility manager.
l GE-Wilmington instructions to implement the'GE Nuclear
(
Energy policies are called Practices and Procedures (P/P's), which clearly define functional i
responsibilities and authorities.
They also contain specific instructions to assure compliance with GE NIclear Energy and GE-Wilmington managerial guidelines.
P/P's require the approval of the GE-Wilmington facility manager prior to their issuance.
Functions within GE-Wilmington may prepare Section Administrative Routines.(SAR's) to govern the conduct of their personnel in accordance with higher level documentation.
SAR's require management approval prior to their issuance.
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FIGURE 11.1 GE-WILMINGTON ORGANIZATION GE NUCLEAR ENERGY (HEADQUARTERS IN SAN JOSE)
NUCLEAR FUEL & COMPONENTS MANUFACTURING FUEL COMPONENTS PRODUCTION
-MANUFACTURING j
FUEL MANUFACTURING REGULATORY ENGINEERING COMPLIANCE MATERIALS LICENSING & NUCLEAR MATERIALS MANAGEMENT PLANT ENGINEERING NUCLEAR SAFETY
& MAINTENANCE ENGINEERING-QUALITY ENVIRONMENTAL ASSURANCE PROTECTION &
INDUSTRIAL SAFETY TECHNOLOGY
& AUTOMATION RADIATION PROTECTION EMERGENCY PREPAREDNESS &
SECURITY FUEL MANUFACTURING EMPLOYEE &
COMMUNITY RELATIONS FINANCE LICENSE SNM-1097 DATE 2/06/89 Page DOCKET 70-1113 REVISION 22 II-11.5 O
11.3.1 Operating Level Instructions Proc 6ss Requirements & Operating Documents-(PROD's) are prepared by process engineering, radiation safety, criticality safety, and environmental protection function personnel to provide instructions to shop operating personnel.
11.3.2 Internal Audits Nuclear safety inspections are conducted daily by the radiation protection function in accordance with the instructions issued by the nuclear safety engineering function.
Additional safety audits are conducted by others including nuclear safety engineering tunction and licensing & nuclear materials management function based on audit plans developed quarterly.
O 11.2.3 Ex*.sne1 ^udite In-depth nuclear safety audits are conducted by personnel from functions external to GE-Wilmington.
The auditors may be from the GE Nuclear Energy quality assurance organization, with responsibility of operational overviews or from outside consulting engineering firms.
11.3.4 Investigation of Unusual Incidents Each reported unusual incident is evaluated to determine the level of investigation required.
The depth of the the investigation depends upon the severity of the LICENSE SNM-1097 DATE 2/06/89 Page DOCKET 70-1113 REVISION 22 II-11.6 O
l
- incident in terms of the levels of uranium released n()
and/or the degree of potential for exposure of workers or the public.
The approach to incident investigations including functional assignments, is shown schematically in Figure 11.2.
A summary of responsibility assignments is as follows:
11.3.4.1 The Area Manager for each area is responsible for protecting the workers, initiating actions to bring the incident under control, assuring that any injuries are treated, notifying appropriate regulatory compliance and company management, performing an initial documentation of the incident, participating in the formal I
investigation as required, and assuring required corrective actions are completed and documented.
1 11.3.4.2 The manager of the regulatory compliance function is responsible for establishing, maintaining, and
()
coordinating the program for investigation of radiological, criticality, chemical, nuclear material safeguards, security and environmental incidents.
The regulatory compliance manager also performs the duties of investigation team captain for Class II & III incidents.
11.3.4.3 The managers of environmental protection and industrial safety, nuclear safety engineering, and licensing and nuclear materials management functions, as applicable, have the responsibility of classifying incidents, assembling the appropriate investigation team, LICENSE SNM-1097 DATE 2/06/89 Page DOCKET 70-1113 REVISION 22 II-11.7 O
FIGURE 11,2 EVENT / INCIDENT INVESTIGATION MANAGERS -
ENVIRONMENTAL PROTECTION &
1 INDUSTRIAL SAFETY, LICENSING & NUCLEAR MANAGER -
MANAGER -
MATERIALS MANAGEMENT LICENSING &
I REGULATORY OR NUCLEAR SAFETY NUCLEAR MATERIALS AREA MANAGER COMPLIANCE ENGINEERING MANAGEMENT ASSURE PROPER ACTION TO CONTROL THE EVENT CONSULT WITH RC
-4 DECIDE NEED FOR
-9 CLASCIFY INCIDENT MANAGER REGARDING INVESTIGATION t-CLASS I, II OR III NEED FOR INVESTI-GATION AND IF EVENT IS AN INCIDENT NOTIFY OUTSIDE CLASS II & III CLASS I REGULATORY AGENCIES AS NOTIFY APPROPRIATE NECESSARY COMPANY MANAGEMENT m
ACT AS INVESTIGATION TEAM CAPTAIN
\\'
PARTICIPATE IN INVESTIGATION AS CONDUCT INVESTIGATION REQUIRED BY REGU-PARTICIPATE IN LATORY COMPLIANCE INVESTIGATION AS NECESSARY DOCUMENT FINDINGS ASSURE REQUIRED CORRECTIVE ACTIONS ARE COMPLETED AND FORWARD REPORT TO MANAGER-L6NMM l
DOCUMENTED l
MAINTAIN FILE ON l
- INCIDENT REPORTS AND REPORT STATUS i
ADVISE L&NMM OF 3
COMPLETION FOLLOWUP NOTIFI-CATION WITH REGULATORY AGENCIES 4
LICENSE SNM-1097 DATE 2/06/89 Page p
DOCKET 70-1113 REVISION 22 II-11.8 G
performing the duty of team captain for Class I
()
incidents, and documenting the incident.
11.3.4.4 The investigation team captain is responsible for assembling the appropriate investigation team, directing and coordinating the activities of the team members, and assuring the investigation report is generated.
11.3.4.5 The manager of the licensing and nuclear materials management function is responsible for assuring notification to outside regulatory agencies, as applicable, participating in the formal investigation, as necessary, maintaining the investigation reports, and distributing the incident report.
11.4 KEY FUNCTIONS
( /
Key personnel of the fuel manufacturing operation with responsibility for safe operation are the managers of the functions described in Section 11.1 and the managers of the functions described below.
Normal plant routines require written identification of a delegate when managers are unavailable to perform their duties.
The Radiological Contingency & Emergency Plan, discussed in Chapter 8, delineates responsible managers and lines of succession for handling site emergency situations.
LICENSE SNM-1097 DATE 2/06/89 Page
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DOCKET 70-1113 REVISION 22 II-11.9 1
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L _ _ _ _ _ _______
I 11.4.1' Facility Manager The facility manager is the individual who has overall responsibility for safety and activities conducted at the GE-Wilmington facility.
He directs all operations personally, by procedure, or through'other management personnel.
His activities are performed in accordance with GE policies, procedures, and management directives.
The facility manager provides.for' safety and control of operations and protection of the environment by delegating and assigning responsibility to qualified Area Managers.
11.4.2 Area Manager The Area' Manager is assigned responsibility for safe operation and control of activities in his designated
- area and for the safety of the environs as influenced by
()'
the activities conducted therein.
He shall establish written operating procedures incorporating radiation and i
criticality safety controls and limits commensurate with the particular operations involved.
11.4.3 Regulatory Compliance This function establishes the radiation safety, criticality safety, and environmental protection programs to ensure compliance with federal, state, and local regulations and laws governing operation of a nuclear facility.
These programs are designed to ensure the health and safety of employees and the public as LICENSE SNM-1097 DATE 2/06/89 Page DOCKET 70-1113 REVISION 22 II-11.10
. O h-am__
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_um_.:__:_.__
_.a_.-
_____m-
._m______m_ _ _ _... _ _ - _ _
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l well as protection of the environment. The managers of fw()
the criticality safety, the radiation safety, the l
radiation protection, the environmental protection and i
industrial safety, and the licensing & nuclear materials i
management functions report to the manager of the regulatory compliance function.
11.4.3.1 Nuclear Safety Engineering Management of the criticality safety and radiation safety functions described below is assigned to one individual.
11.4.3.1.1 Criticality Safety.
This function performs criticality analyses to establish safe batches, geometries, concentrations, and spacing of l
special nuclear materials and equipment.
It provides i
-s
(_)
authoritative, professional advice and counsel to Area Managers on matters of control against accidental criticality.
This function measures the effectiveness of the criticality control program by reviewing the application of methods and data to actual plant situations and approving new and/or changed facilities prior to operation.
It also conducts educational programs on criticality matters.
11.4.3.1.2 Radiation Safety This function establishes and maintains a radiological safety program, which includes formulation of radiation LICENSE SNM-1097 DATE 2/06/89 Page DOCKET 70-1113 REVISION 22 II-11.11
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protection criteria, definition of a' bioassay program,
([
analyses of existing systems, equipment and operations and recommendations for improvements therein. It conducts educational programs on radiological safety i
l matters and. maintains a personnel exposure records l
cystem.
l I
11.4.3.2 Radiation Protection This function administers the nuclear safety program at the operating level, including audits for conformance of 4
plant operations to criticality safety and radiation j
protection criteria.
It provides and implements a radiation monitoring program.
This function also provides assistance in employee training in the methods for minimizing radiation' exposure through proper work habits, and the use of radiation detection instruments, protective clothing, and respiratory protection
()
devices.
11.4.3.3
_ Environmental Protection & Industrial Safety This function operates as the official business interface for regulatory matters pertaining to non-radiological environmental concerns.
It procures and administers federal, state and local permits for non-radiological activities, and interprets and determines application of federal, state and local.
regulations applicable to environmental concerns.
It also establishes and administer the environmental protection program, and provides advice and counsel to i
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v Area Managers on matters of minimizing the environmental
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effects of plant operation.
This function also manages the industrial safety program for the facility.
11.4.3.4 Licensing & Nuclear Materials Management This function operates as the official business interface for all regulatory matters pertaining to nuclear safety concerns.
It procures and administers NRC and Agreement State licenses, and determines and communicates application of NRC, state and local government regulations.
It also provides advice and counsel to GE-Wilmington components and their customers on regulatory matters.
11.5 EDUCATION & EXPERIENCE OF KEY PERSONNEL
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11.5.1 Manager - Nuclear Fuel & Components Manufacturing (GE-Wilmington facility manager)
E. A.
LEES AA - Engineering BS - Metallurgical Engineering MS - Materials Science Mr. Lees joined the General Electric Company in 1958 as l
a member of the Engineering Training Program.
During the next two years, he participated in nuclear fuel development programs at the Vallecitos Nuclear Center, Hanford Atomic Laboratories and the Atomic Power s
Equipment Department in San Jose, California.
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1 Mr. Lees was appointed Manager, Fuels Development l
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( )l Laboratory in 1964 ind was responsible for all the
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fabrication facilities devoted to fuel and materials development programs.
In 1968, Mr. Lees was assigned to the position of Manager, Oyster Creek Pressure Vessel Repair Program.
In this position, he was responsible for the rework of the reactor pressure vessel at the Oyster Creek Site.
In 1969, in the position of Manager of Engineering, Japan Nuclear Fuel Company, Mr. Lees was responsible for the design, construction and start-up of a nuclear fuel joint venture company near Yokohama, Japan.
In 1971, he was appointed Manager, Department of Engineering, Japan I
Nuclear Fuel Company, with responsibility for JNF manufacturing, engineering, construction, and nuclear safety and licensing.
O In 1972, Mr. Lees was assigned to GE-Wilmington where he has held various managerial positions related to fuel manufacturing operations and quality assurance.
Mr. Lees was appointed to his current position as Manager, Nuclear Fuel and Components Manufacturing, in August, 1984.
In this position, he is responsible for the direction of activities associated with the manufacture of nuclear fuel and components for commercial power reactors.
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11.5.1.1 _ Manager - Fuel' Production O.
B.
F. BENTLEY BS -- Ceramic Engineering Mr. Bentley joined General Electric in June 1965 as a member of the Manufacturing Management Program.
During the three-year program, he held positions in Manufacturing Engineering, Quality Control, Materials and Shop Operations in the Semi-Conductor Diamonds Operations, Metallurgical Products and Neutron Levices Departments.
In 1968, Mr. Bentley was appointed a Methods & Work i
Measurements Specialist at Neutron Devices Department (NDD) with responsibility for standards introduction into a plant that had not previously had standards.
In 1970, he was appointed Manufacturing Engineer at NDD
()
with responsibility for assembly, brazing, chemical cleaning and etching.
In 1972, he was appointed Manufacturing Engineer for GE-Wilmington with responsibilities for the Gadolinia Shop.
In 1973, he was appointed shift Process Control Engineer for the Fuel Manufacturing Operation.
This was followed by a Senior Process Control Engineer and Supervisor -
Certification & Release.
In 1976, he was appointed Manager, Powder Production Unit with responsibilities for uranium powder production.
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In 1978, he was promoted to Manager, Fuel Chemical.
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Operation with overal1' operations responsibilities for the powder production and waste treatment facilities.
In 1986, Mr. Bentley became Manager - Fuel Production and the scope of his activities increased to include management of all fuel manufacturing production employees.
11.5.1.2 Manager - Fuel Manufacturing Engineering R. G.
PATTERSON BS - Industrial Engineering Mr. Patterson joined General Electric in 1967 as a member of the Manufacturing Management Program.
Program assignments included activities at Evandale,-Ohio, and Decatur, Illinois.
He joined GE-Wilmington in 1971 as a Process Control Engineer in the nuclear fuel operation.
Subsequently, he was promoted to positions of Manager - Certification
& Release, Manager - Quality Data, Manager - JMC Quality Liaison for foreign fuel manufacturing, Manager -
Uranium Fuel Fabrication Operation, and Manager - Fuel-Fabrication.
Mr. Patterson was assigned to his present position as Manager - Fuel Manufacturing Engineering in 1985.
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11.5.1.3 Manager - Components Manufacturing e
N/
W.
T.
ROSS BS - Metallurgical Engineering Mr. Ross joined General Electric in 1957 at the Hanford Atomic Products Operation in Richland, Washington, as a participant in the Hanford Technical Graduate Program.
After one year, he accepted a permanent assignment as a metallurgist in the Plutonium Fuels Development branch of the operation.
In 1962, he transferred to San Jose, California, as Materials Engineer in the Fuel Design Engineering Unit, Atomic Power Equipment Department.
In 1971, Mr. Ross became Manager of the Wilmington Engineering Unit reporting to Design Engineering in San
(]
Jose.
Mr. Ross was appointed Manager - Fuel Components Operation at GE-Wilmington in 1976 with responsibility for the manufacture of zircaloy fuel components including tubing, spacers, end plugs, water rods and fuel channels.
1 i
In 1986, he was named Manager-Components Manufacturing which added the responsibility of the Services Components Operation to his responsibility of Fuel Components.
Services Components produces stainless steel reactor components for BWR's.
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11.5.1.4 Manager - Regulatory Compliance LO C. M. VAUGHAN BS - Chemistry Mr. Vaughan entered the nuclear industry in 1965 when he joined Nuclear Fuel Services as a Chemist with responsibility'for operation of the uranium scrap accountability laboratory.
He subsequently was active in the development of analysis and metalography of plutonium, exotic metals and U888, activities which resulted in his promotion to Manager of the Alpha Containment Laboratory.
He joined General Electric as a Specialist - Nuclear Materials Management at the Wilmington, N.
C.,
nuclear fuel fabrication facility in 1970.
In this position, he was responsible for the MC&A programs associated with
()
measurements, measurement control and statistics.
He was promoted to the position of Manager - Nuclear Materials Management in 1974.
During this period, he was responsible for all MC&A programs and contributed significantly to the current state-of-the-art MC&A system in place at GE-Wilmington.
In 1981, he assumed the position of Acting Manager, Licensing & Compliance Audits and in 1982, he was assigned the new position of Manager of Licensing &
Nuclear Materials Management (the combined Nuclear Materials Management and Licensing & Compliance Audits units).
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1 In 1985 he was promoted to Manager - Regulatory f( )
Compliance.
This position establishes end oversees the GE-Wilmington programs for nuclear and criticality safety, environmental protection, industrial safety, emergency preparedness, material control and accounting, security, and all licensing and permitting.
Mr. Vaughan is active in the nuclear community.
He has Served the INMM for many years holding several positions within the organization including Chairman in fiscal years 1987 and 1988.
He is affiliated with the National Academy of Science and serves on the N Division Advisory Board for LANL.
11.5.1.4.1 Sr. Program Manager - Nuclear Safety Engineering G.
M.
BOWMAN BS - Industrial Engineering f^)
's >
Mr. Bowman joined the General Electric Company in 1960 at the Metallurgical Products Department in Houston, Texas where he operated the cemented carbides l
metallurgical laboratory until graduating from the University of Houston and joining the Manufacturing i
Management Program in 1965.
While on the three year program, he held positions as a Requisition Specialist, Manufacturing Engineer, and Quality Control Engineer in the Computer Equipment, Large Lamp, and Specialty Control Departments.
In 1968 Mr. Bowman j oined the GE-Wilmington quality control function and served in Quality Systems Engineer l
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and Manager - Quality Assurance positions.
In 1977, he-h accepted a Senior Engineer - Nuclear Safety position in Nuclear.' Safety Engineering, and servea in that capacity.
until 1986, with interim positions as Acting Manager -
Nuclear Safety. Engineering in-1981, 1983, and.1986..
In 1986, he was appointed to his present position as Sr.
Program Manager - Nuclear Safety Engineering.
Senior Engineer - Nuclear Safety (Criticality)-
F.
G. WELFARE BS - Nuclear Engineering MS - Nuclear Engineering From.1959 to 1965, Mr. Welfare was employed in the Radiation Safety Department at the Oak Ridge Y-12 Planti performing nuclear criticality safety evaluations of processing of fissile materials.
In 1965, he moved to l
O the neector Ame1rei nevertme=t et oex asase net 1ome1 Laboratory.where his primary duty was the physics and
' economic evaluation of various reactor types.
In 1972, Mr. Welfare joined Babcock & Wilcox, Lynchburg, Virginia, as Research Specialist in the Research &
Development Division, where his primary responsibility was development of methods used to evaluate nuclear-criticality safety of processing of fissile materials.
Mr. Welfare joined GE-Wilmington in 1983.
His primary assignment at GE-Wilmington has been the evaluation of the criticality safety of the processing of fissile s
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materials and the' establishing of controls required to O
meinte1= eeretv.
Mr. Welfare has approximately 30 years of experience in' neutronics. work, of which 24 years have been in criticality. safety.
Senior Engineer - Nuclear Safety (Criticality) 1 Cl. T. TAYLOR BS Physics MS - Industrial Administration Following service in the Army, Mr. Taylor joined General Electric Company at the Knolls Atomic Power Laboratory in 1966 as a nuclear engineer.
Mr. Taylor came to GE-Wilmington in 1978.
In his O
preeent voeition. he aes the 1eed reevone18111tv for criticality safety.
Senior Engineer - Nuclear Safety (Radiological P. S. STANSBURY BS
- Physics MS
- Physics PhD.- Nuclear Engineering, Health Physics Dr. Stansbury became a Research Associate in the Health & Safety Research Division at Oak Ridge National.
Laboratory in 1977.
This was followed by a five year LICENSE SNM-1097 DATE 2/06/89 Page DOCKET 70-1113 REVISION 22 II-11.21
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position as Assistant Professor, Radiological Hygiene m
l i,)
Program, at the University of North Carolina, Chapel Hill.
Dr. Stansbury joined GE-Wilmington in 1982 in his present position.
In this position, his prime responsibility is radiological safety.
Senior Engineer - Nuclear Safety (Radiological)
S.
P. MURRAY BS - Radiation - Nuclear Protection (Health Physics)
Certified - American Board of Health Physics From 1976 to 1978, Mr. Murray was a health physicist at Abbott Laboratories in Chicago, Il31nois.
He was responsible for the radiation safety program of a broad scope research, manufacture and distribution
( ))
radiopharmaceutical license.
In 1978, Mr. Murray joined Radiation Management l
Corporation, Chicago, Illinois, as a staff health physicist where he provided a variety of client consulting services including management of decontamination and decommissioning projects, development of emergency plans and radiation safety training programs.
Mr. Murray joined GE-Wilmington in December 1979 as a Nuclear Safety Engineer.
In his present position, he is responsible for providing radiation safety evaluations for manufacturing facility change requests and LICENSE SNM-1097 DATE 2/06/89 Page DOCKET 70-1113 REVISION 22 II-11.22 fS V
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1 operational nuclear safety programs, including the g()
external and internal personnel monitoring programs, sealed source control program, and respiratory protection program.
11.5.1.4.2 Program Manager - Radiation Protection R.
L. TORRES AA - Applied Sciences Mr. Torres joined Sandia Corporation in Albuquerque, New Mexico, in 1962 and was certified as a Reactor Health Physicist on the Sandia Pulsed Reactor Facility.
From 1963-73, he was employed by Pan America at Jackass Plats, Nevada, in the following positions:
Radiation Monitor, Senior Radiation Monitor and Lead Technician.
In these positions, he was involved in assembly /
()
disassembly and testing of high enriched test reactors.
Mr. Torres joined Los Alamos Scientific Laboratory in 1973 as a Health Physics Surveyor.
In this position, he assisted operating crews in the operation, experimental set-up, shield design and safety program at the accelerator.
In 1976, Mr. Torres j oined GE-Wilmington as a Shif t Supervisor.
In 1978, he was appointed to the position of Supervisor, Radiation Protection.
In this position, he was responsible for the overall plant radiation protection program administered through crews of salaried, weekly, and hourly personnel.
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e, In 1983, Mr. Torres was promoted to his present position lll as Program Manager, Radiation Protection.
11.5.1.4.3 Sr. Program Manager Manager - Environmental Protection
& Industrial Safety H. R. STRICKLER BS - Chemistry & Physics MBA - Business Administration In 1968 and 1969, Mr. Strickler worked for General Electric Company as Foreman, Fuel Manufacturing in the nuclear fuel fabrication plant in San Jose, California.
Manufacturing tasks such as pellet grinding, rod loading and final rod loading were completed under his direction.
Prom 1970 until 1974, Mr. Strickler worked at General llh Electric Company's nuclear fuel reprocessing plant in Morris, Illinois.
Mr. Strickler developed training for AEC licensed reprocessing operators.
Later, he directed plant startup activities on one shift.
Included in the startup systems under his responsibility were plant steam, electrical utilities, and UF, loadout facilities.
From 1975 through 1983, Mr. Strickler held positions of Manager - Plant Engineering & Safety and Manager - Plant Operations at the Morris facility utilized as a R&D LICENSE SNM-1097 DATE 2/06/89 Page DOCKET 70-1113 REVISION 22 II-11.24
.a center and nuclear spent fuel storage facility.
Receipt L()
and storage of PWR_and BWR' fuel as_well as characterization studies were performed under Mr.
Strickler's guidance.
In 1984, Mr. Strickler joined GE-Wilmington.
From 1984 l
through May, 1988, Mr. Strickler,Las Factory System Engineering Program' Manager, was responsible for the installation of new CAD / CAM, maintenances and facility
' computer systems in the GE-Wilmington nuclear facility.
In June, 1988, POc. Strickler became Sr. Program Manager
- Environmental Protection and in January, 1989, became Manager - Environmental Protection & Industrial Safety.
He is responsible for administration of the site environmental protection program and the site industrial safety program.
(f 11.5.1.4.4 Manager - Licensing & Nuclear Materials Management T.
P. WINSLOW BS - Mechanical Engineering l
From 1967 to date, Mr. Winslow has worked at I
GE-Wilmington in various positions related to manufacturing of nuclear fuel and components.
From 1967 to 1973, his activities related to quality control of fuel cladding, spacers, channels, and end plugs.
From 1973 to 1977, Mr. Winslow held management positions in j
quality control related to pellet, rod, and bundle quality.
From 1978 to 1985, he was Manager - Chemet I
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Laboratory and was responsible for the chemical and
.,)
metallurgical testing of uranium and zircaloy materials
(,
and samples for product quality, environmental, criticality, radiological, and accountability purposes.
From 1986 until present, he has held the position of Manager - Licensing & Nuclear Materials Management.
11.5.1.4.5 Sr. Program Manager - Emergency Preparedness &
Security J. H.
BRADBERRY BS - Biology MS - Nuclear Engineering (Health Physics)
From 1962 to 1969, Mr. Bradberry worked at the Georgia Department of Public Health.
During this time, he was involved in collecting, preparing and running a multichannel analyzer and proportional laboratory
()
equipment.
He was also involved in comprehensive surveys at locations where x-ray equipment, radium or radioisotopes were being used to determine compliance with established laws and regulations.
From 1969 to 1972, he worked as a Senior Radiological Control Engineer at Newport News Shipbuilding & Dry Dock Company.
Work at this facility involved environmental analysis (river, mud, sludge), liquid samples from shipboard reactor plants, analysis for internal contamination from radioactive work at the shipyard, reactor plant shielding surveys and training for radiation technicians and supervisors.
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"o Mr. Bradberry joined GE-Wilmington in 1972.
From that
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period until his present assignment he has held positions as Radiological Safety Engineer, Manager -
Radiation Protection, and Supervisor - Certification &
Release.
I In his present position, Mr. Bradberry is also responsible for the administration of the site security program.
11.5.1.5 Manager - Materials R.
C. HAWK AB - Liberal Arts MP - Industrial Engineering From 1964 to 1967, Mr. Hawk was a member of the General Electric Manufacturing Management Program.
He held a
(( )
variety of positions at several General Electric plant
]
locations.
From 1967 to 1975, he held positions with the GE Nuclear i
Energy - San Jose Business Information System and was Manager - Projects Scheduling.
From 1975 to present, Mr. Hawk has held the GE-Wilmington positions of Manager - Production Planning
& Systems, Manager - Fuel Production Planning & Control, B&W Program Manager, Manager - Operational Planning, and his current position Manager - Materials.
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11.5.1.6 Manager - Plant Engineering & Maintenance
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R. M. McIVER BS - Civil Engineering In 1964, Mr. McIver j oined the U.S. Corps of Engineers as a Civil Engineer.
During the following years, he held the positions of Engineering / Maintenance Supervicor at the Kinston, N.C.,
DuPont plant (1966 to 1970), and Staff Civil Engineer at Consolidated Aluminum Corporation in Waverly, Tennessee (1970 to 1972).
Mr. McIver joined GE-Wilmington in 1972 as a project engineer.
In 1975, he was appointed Unit Manager, Installation Engineering & Site Services, in 1978 he was appointed Manager, Facilities, and in 1987 he was appointed Manager - Plant Engineering & Maintenance.
( [)
In his present position, he is responsible for managing the Plant Engineering & Maintenance operation.
This responsibility includes:
maintenance of all manufacturing facilities and equipment, facility engineering and design services, operation of all plant utility systems and management of site construction.
11.5.1.7 Manager - Quality Assurance W. W. McMAHON BS - Mechanical Engineering LICENSE SNM-1097 DATE 2/06/89 Page j
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