ML20056C335
| ML20056C335 | |
| Person / Time | |
|---|---|
| Site: | 07001201 |
| Issue date: | 05/07/1993 |
| From: | Knapp K BABCOCK & WILCOX CO. |
| To: | Adensam E NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| NUDOCS 9305190249 | |
| Download: ML20056C335 (52) | |
Text
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("% B&W FUEL COMPANY ON
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Y:.) An Arnencan Company with Worldwude Resources P.O. Box 1164S Lynchburg. VA 24506-1646 Telephone:804-522-6000 May 7, 1993 Ms. Elinor G. Adensam, Acting Chief Licensing Branch Division of Fuel Cycle Safety and Safeguards, NMSS Nuclear Regulatory Commission Washington, D.C.
20555
REFERENCE:
SNM-1168 License, Docket 70-1201
Dear Ms. Adensan:
In past operating history of B&W Fuel Company's Commercial Nuclear Fuel Plant (CNFP), CNFP and B&W's Naval Nuclear Fuel Division (NNFD) had mutual ownership and NNFD provided CNFP with nuclear criticality support.
Our current Section 2.2.6 of our license states that the nuclear criticality safety specialist is a separate component within the corporate structure.
In April 1993, CNFP obtained different ownership which deviates from the statement contained in Section 2.2.6.
Although the contract for nuclear criticality support is still in place, we have decided that we would receive better sapport using nuclear engineers in-house.
In order to support this transition, the qualifications for the nuclear criticality safety specialist defined in Section 2.2.6 and 4.1.2 needs to be expanded.
The amended qualifications permit higher education to reduce the experience requirements.
Due to a recent promotion, the Health Safety Foreman position has been removed.
Gerald Lindsey's title is now Health Physicist but remains in the supervisory role over the Health Safety Monitors.
This change has been included in revisions to Chapter 2.
Attachment I provides all the changes made to each section.
The changes are easily identified in the license by a side bar.
Since this is an organizational change, we felt that this should be included under the review of the branch technical positions amendment.
BWFC initial correspondence addressing this issue was submitted to NRC on March 16, 1992.
The submittal was supplemented on November 4, 1992 and March 23, 1993.
100005 9305190249 930507 PDR ADDCK 07002202
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As required, six copies of the Chapter 2 in it's entirety, page 4-1 of Chapter 4, and Chapter 11 in it's entirety which includes currer.t resumes of the nuclear safety engineers have been provided.
If you should have any questions regarding this matter, please feel free to call me at (804) 522-6202.
Sincerely, B&W FUEL COMPANY COMMERCIAL NUCLEAR FUEL PLANT Y[dtY% b Kathryn S.
Knapp Manager, Safety & Licensing
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ATTACHMENT I SECTION PAGE CHANGE l
Figure 2.1 2-1 Removed Health Safety l
Foreman 1
Section 2.2.4 2-3 Removed Health Safety Foreman and renumbered the rest of Sections.
Section 2.2.5 2-4 Removed the statement that l
(This was 2.2.6 prior the nuclear criticality l
to the renumbering of safety specialist was within the sections mentioned the same corporate i
above.)
structure.
Section 2.2.5 2-4 Added additional (This was 2.2.6 prior qualifications to account to the renumbering of for higher education for the sections mentioned nuclear criticality safety above.)
specialists.
Section 4.1.2 4-1 Added additional qualifications to account for higher education for l
nuclear criticality safety g-specialists who perform the l
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independent review of
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evaluations.
Section 11.2.4 11-2 Removed the position of the Health Safety Foreman.
Added the Health Safety l
Foreman's responsibility under 11.2.3 Health Physicist.
Section 11.3 11-3 Added current resumes for the BWFC nuclear criticality j
specialists.
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I B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT USNRC LICENSE SNM-1168, DOCKET 70-1201 ORGANIZATION AND ADMINISTRATIVE PART I CHAPTER 2.0
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2.1 Oraanizational Responsibilities and Authority 2.1.1 Manacement t
It is the responsibility of the Plant Manager to assure the safety of the operation and compliance with license i
conditions.
Control shall be established by:
designation of responsibility to qualified personnel l
t review and approval of Health-Safety procedures review of program effectiveness prompt correction of nonconforming conditions The CNFP management structure is as shown in Figure 2.1.
Ficure 2.1 SAFETY REVIEW CNFP PLANT NUCLEAR CRITICALITY BOARD CHAIRMAN MANAGER SPECIALIST t
- PRODUCTION MANAGER, SAFETY
- ADMINISTRATIVE MANAGERS
& LICENSING MANAGERS OPERATIONAL HEALTH SAFETY SUPERVISORS SECTION (e.g., Mfg. Eng., Fuel Manufacturing & Field Operations)
(e.g.,
Accounting, Personnel, Purchasing, Info. Services, Production and Inventory Control - not directly responsible i
for production functions) 2.1.2 Production Manaaers i
Production Managers report directly to the plant manager with except for the Manager, Field Operations i
who reports to the President of the Company.
They are responsible for managing operational area supervisors and are responsible for production functions.
The Managers of Manufacturing Engineering, Fuel Manufacturing and Field Operations are production managers.
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B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT USNRC LICENSE SNM-1168, DOCKET 70-1201 ORGANIZATION AND ADMINISTRATIVE CHAPTER 2.0 PART I 2.1 Orcanizational Responsibilities and Authority 2.1.2 Production Manaaers The Production Managers shall have, at a minimum, a bachelor's degree in science or engineering, followed by two years experience in the nuclear industry.
2.1.3 Operational Area Supervision operational area supervision is that supervision directly responsible for the control of materials, personnel, equipment, and activities in specific areas.
Those responsibilities include assuring that approved control procedures developed by Health-Safety shall be available in writing to operators and other concerned personnel and shall be adhered to.
Minimum qualification of operational area supervision shall include:
(a)
A high school education and a minimum of 2 years experience in the nuclear industry.
Experience shall include the practical application of O
criticality control techniques and a familiarity with the applicable specific limitations imposed on CNFP operations.
2.1.4 The Health-Safety Section The Health-Safety Section shall be responsible to interpret the license conditions, provide monitoring facilities, develop safe operation guidelines, maintain training programs, and review and approve operating procedures to assure safe operation and license compliance. These responsibilities include maintenance of nuclear safety and radiation safety with the approval authority limited to authorized specific or general license conditions. The Health-Safety section shall not be directly responsible for the performance of manufacturing operations.
The Manager, safety and Licensing or their qualified designee shall be responsible to provide management with assurance of the effectiveness of the safety program by maintaining an audit program that includes periodic inspection of controls and operations, reports to management, follow-up or nonconforming conditions and necessary documentation (see Audits, Section 2.7).
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B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT USNRC LICENSE SNM-1168, DOCKET 70-1201 PART I CHAPTER 2.0 ORGANIZATION AND ADMINISTRATIVE 2.2 Personnel Education and Exoerience Reauirements 2.2.1 Plant Manaaer The Plant Manager shall have a Bachelor's Degree in Science or Engineering, a
minimum of 10 years experience in the nuclear
- industry, and 5
years experience in management.
2.2.2 Manaaer. Safety & Licensino The manager to whom the section reports shall have a Bachalor's Degree and a
minimum of five years experience, which would develop an understanding of nuclear and radiation safety. Srch experience shall be of a nature which demonstrates to the Plant Manager sufficient judgment and capability to establish and maintain an ef fective nuclear criticality and radiation safety program for the activities authorized by license.
2.2.3 Health Physicist The Health-Safety Section shall include a person who shall act as the plant Health Physicist.
This person shall have a
Bachelor's Degree in Science or Engineering.
A minimum of 2 years experience in applied health physics is required along with sufficient formal training that provides an understanding of the health physics and nuclear safety hazards involved at the CNFP.
2.2.4 Health-Safety Monitors l
Health-Safety Monitors set up and conduct routine l
monitoring, sample collection and analytical tests in the plant to determine whether the amount of radioactivity is within acceptable limits and assists in verifying the radiological and industrial safety of employees.
The Health-Safety Monitors shall have, as a minimum, a high school diploma or GED equivalent with six months of experience as a radiation monitor. They may fulfill the experience requirements on the job as a Health-Safety Monitor trainee.
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l B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT USNRC LICENSE SNM-1168, DOCKET 70-1201 PART I CHAPTER 2.0 ORGANIZATION AND ADMINISTRATIVE 2.2 Personnel Education and Experience Reouirements 2.2.5 Nuclear Criticality Safety Specialist The Nuclear Criticality Safety Specialist is organizationally independent of the CNFP, with no interest in plant operations, other than the nuclear criticality safety aspects.
The Nuclear Criticality Safety Specialist is responsible for evaluating the basic nuclear criticality safety limis ations upon which plant safety was originally
- assessed, potential
- changes, validity of assumption, and accuracy of results.
The minimum qualifications for the Nuclear Criticality Safety Specialist shall be a Bachelor's Degree in Science or Engineering and a minimum of two years experience in nuclear reactor physics and one year experience in nuclear criticality analysis or two years experience performing nuclear criticality safety analyses or a Master's Degree in Nuclear Engineering i
and one year experience performing nuclear criticality safety analyses.
2.3 Safety Review Board The Safety Review Board reviews the following as a minimum on a quarterly basis:
New or revised facilities Analysis of equipment and processes involving hazardous e
materials Maintenance of fire safety e
The continuing ef fectiveness of established controls and safeguards Maintenance of ALARA criteria (review of quarterly air o
sample averages, review of surface contamination surveys)
Safety-related audit and inspection findings e
Other items (such as abnormal occurrences) that Safety Review Board members wish to discuss.
The Safety Review Board Chairman shall have a Bachelor's Degree in Science or Engineering and a minimum of five years experience in responsible positions which would develop an understanding of nuclear and radiation safety.
The Safety Review Board Chairman shall be directly responsible to the Plant Manager for the proper conduct of the Safety Review Board.
The Plant Manager shall be kept informed in l, f3 L
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B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT USNRC LICENSE SNM-1168, DOCKET 70-1201 PART I CHAPTER 2.0 ORGANIZATION AND ADMINISTRATIVE 2.3 Safety Review Board writing of Safety Review Board action.
The permanent membership of the Board shall consist of representatives from production management (section 2.1.2), Manager, safety and Licensing and others as deemed necessary by the Chairman.
Technical representatives of outside consulting organizations shall be included as necessary.
Board meetings may be convened at the discretion of the Safety Review Board Chairman, but shall be held at least quarterly.
The Safety Review Board Chairman shall decide whether or not the necessary disciplines are present during a board meeting to evaluate the item (s) under consideration.
There shall be a minimum of 4 Safety Review Board members present during a board meeting.
Records of Safety Review Board proceedings, including supporting calculations and approvals, shall be retained for 2 years minimum after the completion or termination of the subject activity.
An annual ALARA report shall be prepared under the direction of the Manager, Safety and Licensing.
The report shall be submitted to the Safety Review Board in which they will review to determine:
- 1) if there are any upward trends developing in s
personnel exposures (internal and external) for identifiable categories of workers, types of operations, or effluent releases; 2) if exposures and releases might be lowered in accordance with the ALARA concept; and 3) if equipment for effluent and exposure controls is being properly used, maintained, and inspected. A copy of the report shall be sent to the Plant Manager along with the results of the review and recommendations.
At least every two years, the Safety Review Board shall evaluate the effectiveness of the radiation / nuclear safety training program.
2.3.1 Pre-coerational Evaluations New operations and facilities and major operational changes require Health Safety to perform an evaluation prior to initial operation to ensure that adequate radiation, nuclear, fire, and chemical protection is established.
The Safety Review Board Chairman reviews all pre-operational evaluations which involve hazardous materials and determines if Board review is necessary.
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o B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT USNRC LICENSE SNM-1168, DOCKET 70-1201 PART I ORGANIZATION AND ADMINISTRATIVE CHAPTER 2.0 2.3.1 Pre-operational Evaluations In the case of minor changes where existing safety practice remains the same, the Safety Review Board.
Chairman may determine that Board review is not necessary.
Safety Review Board members shall be kept appraised of actions taken by the Safety Review Board l
Chairman on such minor changes. Where other than minor changes are involved, the Safety Review Board review and approval process shall be conducted in accord with procedures approved by the Plant Manager.
2.4 Approval Authority for Personnel Selection i
Personnel selection for those CNFP staff level positions shall be approved by the Plant Manager.
2.5 Traininct Initial indoctrination of employees to nuclear and radiological safety shall be the responsibility of Health-Safety and shall conform with 10 CFR 19.
Initial indoctrination training shall, as a minimum, include the f
following topics:
N
- license conditions federal regulations e
operating procedures e
radiation safety e
nuclear safety emergency procedure chemical and fire safety e
The extent and depth of the training, relative to the detailed aspects of the radiation, chemical, fire and nuclear safety programs, is dependent on the employee's job assignment and potential exposure to radioactive materials ac determined by Health-Safety.
The initial indoctrination training shall be reinforced (as appropriate to the individual's job assignment) by the employee's immediate supervisor or his designee with respect to individual unit safety requirements, location of emergency
- exits, contamination control techniques, specific local controls, and operating procedures, prior to the employee being released to operate independently.
The employee's immediate supervisor shall complete a new employee training verification form prior to allowing the employee to operate independently.
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l B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT USNRC LICENSE SNM-1168, DOCKET 70-1201 i
PART I CHAPTER 2.0 ORGANIZATION AND ADMINISTRATIVE
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2.5 Trainino A contiiming safety training program shall be conducted by Health-Safety to the extent necessary to assure the maintenance of acceptable safety practices. Such training may be conducted on an individual or group basis.
The content of retraining programs may be varied by Health-Safety but will include radiological and nuclear safety as a
minimum.
Emphasis is placed on new or revised safety criteria or areas in need of reinforcement.
A formal retraining of radiation workers shall be conducted at least annually.
Documentation of formal training and retraining shall be maintained by Health-Safety and retained for at least two years.
The Manager, Safety and Licensing shall be responsible to assure that personnel assigned to Health-Safety are properly trained.
The extent and depth of the training is based on the specific job assignment involved.
Health-Safety monitoring personnel shall receive a combination of formal and "on-the-job" training such that they can successfully demonstrate their proficiency in basic nuclear and radiation physics i
monitoring and control techniques and regulatory requirements before being allowed to function without direct oversight.
t 2.6 Operatina Procedures l
Written procedures for the conduct of specific operations l
including maintenance and development of work within the plant are prepared by the functional component responsible for that activity and shall be reviewed and approved by appropriate i
production management and Manager, Safety and Licensing.
Operating procedures which involve SNM shall be reviewed at least every two years by the appropriate production manager and Manager, Safety and Licensing.
Applicable procedures shall be available in the work area and adherence to procedure shall be required of all personnel. Procedures for operations where nuclear and radiological safety are involved shall include specific reference to applicable safety requirements.
Procedure and format shall be such that operations are clearly detailed and specific directions are provided for operation under both normal and abnormal conditions.
Deviation from 1
written procedures for the handling of radioactive materials shall be approved by the Manager, safety and Licensing, or their qualified designee.
In
- addition, administrative procedures shall supplement operating procedures to ensure proper procedural implementation.
Procedural control of activities at the CNFP are categorized as fol bws:
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I B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT USNRC LICENSE SNM-1168, DOCKET 70-1201 PART I CHAPTER 2.0 ORGANIZATION AND ADMINISTRATIVE I
2.6 Operatina Procedures Health-Safety Procedures developed by Health-Safety specify the method by which safety related functions are to be accomplished.
The procedures shall encompass all health physics activities required by the license.
Such procedures may be for internal Health-Safety use or may be intended for general distribution to affected individuals within other components. As a minimum, Health-Safety procedures shall be approved in writing by the Manager, Safety and Licensing as well as approved by affected members of 1
j plant management, f
SNM Accountability Nuclear Materials Control procedures provide techniques for the accountability and measurement of SNM.
As a minimum, such procedures shall be approved in writing by l
the Manager, Safety and Licensing and the Manager, i
Production and Materials Control.
t Other Plant Groups l
Procedures from other plant groups (i.e., Manufacturing, Quality Assurance) where nuclear chemical, fire or l
radiological safety, license conditions, or regulatory requirements are involved require prior approval by the Manager, Safety and Licensing as well as approval by affected members of plant management.
i New operations and major operational changes shall require the written recommendation of the Safety Review Board Chairman prior to implementation.
If the change requires revisions to procedures or the local safety rules, these modifications shall be in place prior to implementation.
Revised procedures shall be subject to approval in the same manner as new procedures.
Health-Safety procedures shall be reviewed at least annually for technical correctness and applicability.
The Manager, Safety and Licensing shall use-their discretion to assure that the appropriate personnel of Section 2.2 performs the procedure review.
Procedure distribution and control shall be in accord with procedures approved by plant management.
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B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT USNRC LICENSE SNM-1168, DOCKET 70-1201 PART I CHAPTER 2.0 ORGANIZATION AND ADMINISTRATIVE 2.7 Audits and Inspections s
An internal Health-Safety inspection
- progran, shall be maintained to provide assurance that plant activities are conducted safely and in accord with license specifications.
The Manager, Safety and Licensing shall be responsible to assure that the inspection program is conducted effectively.
The internal Health-Safety inspection program at the CNFP is structured as follows:
Monthly Safety Inspections Health-Safety personnel shall conduct, at least monthly, a formal inspection of plant status relative to safety related functions to include fire safety, except.during plant shutdown of a week or longer.
Inspection results shall be documented, reported to plant management and supervision as appropriate, and will be maintained on file by Health-Safety for at least 2 years.
The monthly safety inspections shall be conducted by personnel technically qualified to perform this function and in the application of license specifications.
Informal Daily Insoections Health-Safety personnel shall, as part of their routine
- duties, conduct informal daily inspections of plant activities.
These ' inspections are not formally documented unless adverse findings are identified.
Other Inspections Ventilation, containment, and air cleaning equipment shall be routinely inspected at least annually by Health-Safety personnel to assure continued effectiveness and compliance with license specifications.
Indeoendent Audits Independent auditors shall conduct,.as a minimum, semi-annually nuclear safety, fire safety and health physics r
inspections at the CNFP. These audits-shall be conducted in accordance with written instructions or procedures.
The audit scope shall consist of physical inspections and i
records reviews for the industrial,- nuclear, and j
radiological safety. elements-of plant activities including:
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l B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT l
USNRC LICENSE SNM-1168, DOCKET 70-1201 PART I CHAPTER 2.0 ORGANIZATION AND ADMINISTRATIVE l
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\\w-Independent Audits
- effectiveness of procedural controls impacting on i
cperational safety parameters.
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- audit of operating records, where such records provide a means of verifying procedural compliance with safety specifications.
- review and evaluation of contamination survey data.
- ascertaining the overall performance of the plant j
functions in providing adequate controls, surveillance, f
l and follow-up to assure safety and license compliance.
Independent auditor's reports shall be submitted to the Plant Manager for his review.
He will ensure that the proper management reviews the report. The audit report shall include l
any audit findings or recommendations.
Actions taken as a result of audit findings shall be documented.
Qualifications of the independent auditors shall include competence in the areas of health physics or nuclear physics as appropriate at a level at least equivalent to Paragraph 2.2.3 or 2.2.6 respectively.
Designation of the independent auditors shall be the responsibility of the CNFP Plant Manager.
l 2.8 Investications and Reportina j
Unusual events requiring reporting under NRC regulations shall be investigated as appropriate, with results reported to plant f
management and NRC.
Events not otherwise requiring a report may be reported to NRC based on potential public or media involvement, etc.,
in order to keep NRC appraised of the.
situation.
2.9 Records r
Plant alterations or additions, abnormal occurrences,' events associated with radioactive releases, criticality analyses, audits, inspections, instrument calibration, ALARA findings, employee training and retaining, personnel exposures, routine radiation
- surveys, and environmental surveys shall be maintained on file for a minimum of 2 years or as otherwise required by federal regulation or other license condition, for review by CNFP management and regulatory agencies.
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B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT USNRC LICENSE SNM-1168, DOCKET 70-1201 l
PART I - CHAPTER 4.0 - NUCLEAR CRITICALITY SAFETY Administrative Conditions O
4.1 4.1.1 Desian Philosophies The double contingency principle as defined in the American Nuclear Standard ANSI /ANS-8.1 shall be followed in establishing nuclear criticality safe-ty for all equipment, systems and operations.
l Process designs shall incorporate sufficient fac-l tors of safety to require at least two unlikely, independent, and concurrent changes in process conditions before a criticality accident is possi-ble.
Where possible and practicable, reliance will be placed on equipment design in which dimen-i sions (i.e., favorable geometry) are limited rath-l t
er than on administrative controls.
Where struc-l tural integrity is necessary to provide assurance I
l for safety, the dasign and construction of the equipment will be made with due regard to abnormal loads, accidents and deterioration.
4.1.2 Criticality Safety Analyses With respect to the overall plant nuclear criti-cality safety, the Manager, Safety & Licensing is responsible for controlling all modifications O,
and/or additions to any operation, system or equipment.
i Nuclear criticality safety evaluations are per-formed by qualified nuclear criticality safety i
specialists.
These specialists must have a B.S.
Degree in Science or Engineering and either a minimum of two years experience performing nuclear criticality safety analyses or a minimum of two years experience in reactor physics and one year experience performing nuclear criticality safety F
analyses.
Individuals not satisfying the above requirements may perform safety evaluations pro-vided the evaluations are approved in writing by a i
qualified nuclear criticality safety specialist.
All nuclear criticality safety evaluations shall f
l be independently reviewed by an individual meeting the qualifications of nuclear criticality safety specialist as defined above with two years of l
experience as a Nuclear Criticality Specialist or a PhD in Nuclear Engineering with one year experi-ence in nuclear v~iticality analysis.
All evalua-tions shall include an appropriate statement of this review.
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j B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT l
USNRC LICENSE SNM-1168, DOCKET 70-1201
)
ORGANIZATION AND PERSONNEL
~
CHAPTER 11.0 PART I j
11.1 Orcanizational Responsibilities i
Figure 11.1 illustrates the departmental and managerial i
organization at the CNFP.
The key organization responsible for maintaining the health f
and safety aspects at the CNFP is the Health-Safety Section.
}
The Health-Safety Section is a part of the Safety and Licensing Group.
The Health-Safety Section reports to the l
Manager, Safety and Licensing.
The Manager, safety and Licensing reports directly to the Plant Manager.
1 1
11.2 Kev Personnel Function J
l 11.2.1 Overall Procram Manacement i
Responsibility for
- planning, coordinating, administering and managing the health and safety i
aspects of the CNFP is vested in the Manager, Safety I
and Licensing.
This position is organizationally parallel to other member of the Plant Manager's staff f
such as the Managers of Manufacturing Engineering and Fuel Manufacturing.
3 11.2.2 The Health-Safety Section i
Health-Safety personnel are responsible for the general j
surveillance of all plant safety related functions.
l Specifically, these functions are described as follows:
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Maintaining appropriate control of hazardous
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material, shipments, and receipts.
Supervising and coordinating the hazardous waste disposal program.
j 1
Assisting in personnel and equipment I
decontamination.
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I Distribution and processing of personnel monitoring equipment.
Maintaining individual exposure records.
Orienting and training CNFP personnel in radiological and nuclear safety.-
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B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT USNRC LICENSE SNM-1168, DOCKET 70-1201 CHAPTER 11.0 ORGANIZATION AND PERSONNEL PART I 11.2 Kev Personnel Functions 11.2.2 The Health-Safety Section Furnishing consulting services and advice on radiation protection to plant supervision and management.
Generating or acquiring, maintaining, and appropriately distributing all records and reports required by applicable regulations or procedures.
1 Leak testing on sealed radioactive sources.
Developing and disseminating procedures related to l
radiation safety and reviewing procedures prepared by other operating sections for regulatory compliance and the adequacy of safety considerations.
The key positions within the Health-Safety Section are the Health Physicist, the Health-Safety Foreman and the Health-Safety Monitors.
11.2.3 Health Physicist The Health Physicist is responsible to provide management with assurance of the effectiveness of the entire health and safety program from a radiological, nuclear, industrial, and chemical safety aspect.
This position is responsible for evaluating the potential for exceeding authorized control limits and to recommend appropriate restrictions or corrective measures.
The Health Physicist is also responsible for supervising the activities of the Health-Safety Monitors and to assure that the requirements of the Health-Safety program as defined by license and procedures are carried out.
The Health Physicist reports directly to the Manager, Safety & Licensing.
11.2.4 Industrial Safety & Environmental Control Officer The Industrial Safety & Environmental Control Officer is responsible for implementing the occupational and industrial safety programs to include chemical and fire safety.
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B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT USNRC LICENSE SNM-1168, DOCKET 70-1201 l
ORGANIZATION AND PERSONNEL PART I CHAPTER 11.0 11.2.5 Health-Safety Monitor f
The Health-Safety Monitor is responsible f.'or conducting routine monitoring, sample collection and analytical tests to determine radiation and contamination levels.
11.3 Resumes Since it is also the responsibility of the entire plant management to assure safe operations and regulatory compliance, we are including resumes from other managerial
[
organizations within the CNFU as well as those within the Quality and Safety Group.
These are as follows:
H_agp.g Title a
C.W.
Can.
Plant Manager, Commercial Nuclear Fuel l
Plant l
J.T. Ford Manager, Fuel Manufacturing (Production i
Manager)
T.S. Wilkerson Manager, Manufacturing Engineering (Production l
Manager) i l
B.W.
Pugh Manager, Materials & Transportation K.S. Knapp Manager, Safety & Licensing j
j l
G.B.
Lindsey Health Physicist
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j D.L. Gordon Sr. Health Physicist j
i K.L. Bennett Industrial Safety & Env. Control Officer W.T. Foot Manager, Facilities and Services R.W. Penoza Manager, Field Operations (Production Manager) i L.A. Hassler Senior Principal Engineer P.L. Holman Senior Principal Engineer S.A. Alafifi Engineer l
F.M. Alcorn Manager, Nuclear Criticality Safety Engineering
}
J.M. Harwell Nuclear Criticality Specialist Engineer 1
J.G. Tennant Manager, Production & Inventory Contro?
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B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT
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USNRC LICENSE SNM-1168, DOCKET 70-1201 ORGANIZATION AND PERSONNEL CHAPTER 11.0 PART I O
NAME:
Charles W. Carr TITLE:
Plant Manager, Commercial Nuclear Fuel Plant 1
CITIZEN OF UNITED STATES EDUCATION:
Virginia Polytechnic Institute and State University BS in Mechanical Engineering - 1966 Registered Professional Engineer in Virginia Reg. No. 8442 EXPERIENCE: 1967-1968 Combustion Engineering, Chattanooga, Erection Department - Erection Tenn.
Site Field Engineer for large controlled circulation and combined circulation steam generators.
Worked with erector and craft labor to resolve erection
- problems, make
- plans, and monitor schedules.
1968-1972 Babcock & Wilcox Co., Naval Nuclear Fuel Design
- Division, Lynchburg, VA.
Engineer in Core Assembly Section.
Wrote procedures for assembly,
- testing, and shipment of nuclear fuel for the U.S.
N Navy.
Obtained customer (U.S.
Government) approval of all procedures and engineering changes.
1972-1976 Babcock & Wilcox Co., Naval Nuclear Fuel
- Division, Lynchburg, VA.
Senior
- Engineer, Advanced Core Engineering.
Developed manufacturing processes for an advanced NR fuel design.
Designed tooling and purchased (specified) welding equipment.
Completed pre-production hardware and final pre-production report.
1976-1981 Babcock & Wilocx Co., Naval Nuclear Fuel Division, Lynchburg, VA. - Unit Manager, Core Structurals Procurement.
Managed a group of engineers responsible for specification and procurement of core structurals (non-fuel) for naval reactors.
Provided technical evaluation and disposition of manufacturing discrepancies, engineering changes and manufacturing procedures.
Responsible for vendor technical and schedule performance.
s
)
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i B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT USNRC LICENSE SNM-1168, DOCKET 70-1201
)
PART I CHAPTER 11.0 ORGANIZATION AND PERSONNEL Q
NAME:
Charles W. Carr (Cont'd.)
1981-1983 Babcock Wilcox Co.,
Nuclear Power
- Division, Lynchburg,
.VA.
Project
- Manager, Nuclear Engineering Services.
i Managed several service contracts ranging i
from $20K to $4.2M including design and procurement of new reactor coolant pump seals for five B&W and two CE designed nuclear steam systems.
Responsibilities includen cost
- control, estimating, customer interface and vendor contract negotiations.
Negotiated several agreements for technology transfer, both to and from EdF in France.
1983-1986 Babcock Wilcox Co.,
Nuclear Power l
- Division, Lynchburg, VA.
- Manager, l
Engineered Products & Parts.
Provided hardware for several major repair / service projects in B&W and W nuclear steam systems.
Improved revenue in the EP&PS i
Business Unit and improved the quality of l
hardware and the service to B&W nuclear l
customers.
l l
1986-1991 Babcock Wilcox Co.,
Nuclear Power l
- Division, Lynchburg, VA.
- Manager, l
Component Engineering & Field Services.
l Responsible for technical adequacy of i
modifications and new construction of components in nuclear steam systems serviced by B&W.
Also responsible for t
field services including new equipment installation, plant modifications, refueling, and consultation.
Section duties include estimating,
- proposal, l
customer interfaces on technical issues, and contract execution within authorized budget and schedule.
Supervisory responsibilities for staff of five i
l managers and a
group of 80 to 120 i
l engineers and technicians.
j 1991-Present B&W Fuel Company, (Babcock & Wilcox Co.)
- Commercial Nuclear Fuel Plant.
Plant Manager.
Responsible for all plant operations including safety, licensing, safeguards, environment, manufacturing, and quality.
O PAGE:
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.~ _.
I B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT l
USNRC LICENSE SNM-1168, DOCKET 70-1201 i
PART I CHAPTER 11.0 ORGANIZATION AND PERSONNEL O
NAME:
J. T. Ford TITLE:
Manager, Fuel Manufacturing f
t CITIZEN OF UNITED STATES EDUCATION:
1969 Davidson County Community College - A.A.
1975 Central Virginia Community College -
Nuclear Technology j
l MILITARY:
1970-1972 U. S. Army l
EXPERIENCE: 1970-1972 Manufacturing Technician, B&W, Commercial l
Nuclear Fuel Plant.
l l
1972-1975 Data Evaluation Technician, B&W Commercial Nuclear Fuel Plant, Reviewed i
and certified fuel assemblies and control l
components.
1 1975-1978
- Foreman, Pelletizing. Operations, B&W, l
Commercial Nuclear Fuel Plant.
Responsible for pellet operations.
l 1978-1979
- Foreman, Grid Manufacturing, B&W, Commercial Nuclear Fuel
- Plant, Responsible for grid manufacturing.
j 1979-1981 Foreman, Bundle Assembly, B&W, Commercial l
Nuclear Fuel
- Plant, Responsible for assembly operations, and the shipment of finished products.
1981-1982 License Administrator, B&W, Commercial Nuclear Fuel Plant.
Responsible for obtaining and administering all licenses and permits including those issued by NRC, EPA, State, and Local agencies.
)
I 1982-1985
- Manager, Regulatory
- Control, B&W, Commercial Nuclear Fuel Plant.
Responsible for nuclear materials
- control, licensing, health-safety, physical-
- security, nuclear
- safety, receiving and stores.
1985-
- Manager, Fuel Manufacturing, B&W, Commercial Nuclear Fuel Plant.
Responsible for fuel
- rod, control component, grid, fuel bundle, and incore detector fabrication.
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B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT USNRC LICENSE SNM-1168, DOCKET 70-1201 PART I CHAPTER 11.0 ORGANIZATION AND PERSONNEL NAME:
T. Scott Wi."cerson TITLE:
Manager, Manufacturing Engineering CITIZEN OF UNITED STATES I
EDUCATION:
i 1986 - M.E.
- Applied Mechanics, University of Virginia i
1978 - B.S.
- Mechanical Engineering, Virginia i
Polytechnic
. Institute and State i
University, Blacksburg, Virginia, EXPERIENCE: 1992 -
B&W Fuel Company - Manager, Manufacturing l
Engineering.
Unit manager with l
responsibility for manufacturing procedures and processes.
used for production of_ nuclear fuel components.
t Unit provides technical responsibility j
for equipment
- design, fabrication l
- methods, process qualifications and j
evaluation of deviated components.
Function includes liaison with vendors, fuel design engineering and customers.
1976-1990 B&W Fuel Company - Group Supervisor in charge of the Present Production i
Engineering Group of the Fuel Mechanical Engineering Unit.
As such, responsible for the interface between the design of fuel assemblies and control components t
and the fabrication facility.
All l
drawings, specifications, and associated i
documentation for component fabrication are
- released, maintained, and 1
administered by this group.
1980-1990 B&W Fuel Company - Principal Engineer, entered as an Associate Engineer (Engineer l
II).
Work consists primarily of the mechanical (structural) design testing, analysis, and associated documentation of commercial nuclear fuel assembly structural components and related equipment.
This work typically involves the use of open shop computer programming as well as large scale structural analysis computer codes such as ANSYS.
Project Administrative tasks such as preparing proposals, schedules, O
presentations, cost estimates, and PAGE:
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t i
I B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT i
USNRC LICENSE SNM-1168, DOCKET 70-1201 PART I CHAPTER 11.0 ORGANIZATION AND PERSONNEL 1
i O
NAME:
T. Scott Wilkerson (cont'd) l technical reports are routinely done as necessary.
Often this work is in close l
cooperation with the manufacturing plant; i
therefore, familiarity with standard i
manufacturing practices is also maintained.
j l
1978-1980 Lynchburg Foundry - Associate Engineer, i
Lynchburg, Virginia.
In this capacity i
responsible for the budget,
- schedule, I
- design, installation, and startup of capital projects and for solving-a variety of mechanical plant engineering j
problems.
Most of the work was in direct i
support of the manufacturing and quality l
control process of the plant.
Lynchburg Foundry makes gray and ductile iron l
castings primarily for the automotive and heavy equipment industries.
1977-1978 Lynchburg Foundry Engineering l
Assistant.
As a co-op, was involved in O-engineering problems and worked as a
draftsman preparing engineering drawings i
under close supervision.
PROFESSIONAL AFFILIATION:
ASME 4
l t
-l i
l l
l O
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a B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT USNRC LICENSE SNM-1168, DOCKET 70-1201 PART I CHAPTER 11.0 ORGANIZATION AND PERSONNEL O
NAME:
Bob W. Pugh TITLE:
Manager, Materials & Transportation CITIZEN OF UNITED STATES EDUCATION:
1963 Phillips Business College Data Processing i
EXPERIENCE: 1969-1970 Production Sponsor, Jr., Babcock & Wilcox Company, Commercial Nuclear Fuel Plant, Lynchburg, Virginia.
Responsible for requisition and monitoring Contract Materials.
1970-1975 Production
- Sponsor, Babcock Wilcox
- company, Lynchburg, Virginia.
Responsible for Materials Control Function.
1976-1983 Supervisor, Materials Control, Babcock &
Wilcox
- company, Lynchburg, Virginia.
Responsible for Materials
- Control, Stores, and Shipping and Receiving Functions.
1983-1985
- Manager, Special
- Projects, Babcock Wilcox
- Company, Lynchburg, Virginia.
Responsible for all special project activities, j
1985-1991 Manager, Production & Materials Control, B&W Fuel Company (Babcock Wilcox Co.),
Lynchburg, Virginia.
1991-Present Manager, Materials & Transportation, B&W Fuel Company, Lynchburg, VA i
O F
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B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT USNRC LICENSE SNM-1168, DOCKET 70-1201 i
PART I CHAPTER 11.0 ORGANIZATION AND PERSONNEL j
NAME:
Kathryn S. Knapp TITLE:
Manager, Safety & Licensing EDUCATION:
1985 - University of Nevada, Las Vegas - B.
S. Health Physics y
l EXPERIENCE: Jan 1990 -
l Present B&W Fuel
- Company, Manager, Safety Licensing.
Responsible for coordinating the technical aspects of radiation control for the fuel manufacturing plant and for the field operations refurbishment facility.
Involved in the decommissioning,
- training, emergency f
preparedness, and transportation programs.
Responsible for budgeting for j
i the Health-Safety Section.
Liaison with i
regulatory agencies.
l May 1989 -
Jan 1990 B&W Fuel Company, License and Control Administrator.
Liaison with Federal, l
State and. Local regulatory agencies.
O.
Assist in the Health Physics Program for CNFP.
Feb 1987 -
i May 1989 Transnuclear, Inc.,
Radiation Safety Officer.
Functioned as the Corporate Radiation Safety Officer.
Responsible for all aspects of the radiation protection program to include:
regulatory compliance (both State and Federal), radioactive material shipments, l
training, waste management, calibration of instrumentation, records maintenance l
(both personnel and operational history),
l radiation monitoring (both personnel and environmental),
and liaison with t
l licensing authorities.
/~
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B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT USNRC LICENSE SNM-1168, DOCKET 70-1201 PART I CHAPTER 11.0 ORGANIZATION AND PERSONNFL
\\
NAME:
Kathryn S. Knapp (cont'd)
EXPERIENCE: 1987-1989 Also responsible analyses and evaluations to assur sat radiological protection and ALAR 7 asiderations are incorporated into system and facility
- designs, operations and handling procedures, and personnel training programs for both customers and employees.
Sept. 1986 -
t Feb. 1987 Chem-Nuclear
- Systems, Inc.,
Senior Radiological Control Technician and DOT broker.
As DOT broker, acted as the Company's legal representative for verifying that the contents of radioactive waste shipments were in compliance with all State and Federal laws, rules and regulations, and CNSI's i
low-level radioactive waste burial site criteria.
Supervised projects for the proper handling, packaging, shipping, and ultimate disposal of various radioactive Q
materials.
NJ This included supervising work activities, scheduling and personnel utilization, and providing technical
- guidance, and addressing the interpretation of waste disposal criteria for special wastes.
As Senior Radiological Control Technician, was responsible for implementing the radiation and safety
- program, directing daily project activities to minimize radiation
- exposure, conducting radiological and I
safety
- surveys, radiological training
- programs, and maintaining project records.
Participated in a major radioactive waste cleanup and disposal project with the U.
S.
Air Force involving curie-level contamination of Americium-241.
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B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT USNRC LICENSE SNM-1168, DOCKET 70-1201 PART I CHAPTER 11.0 ORGANIZATION AND PERSONNEL j
s NAME:
Kathryn S.
Knapp (cont'd)
EXPERIENCE: Sept. 1985-Sept. 1986 Chem-Nuclear
- Systems, Inc.,
Health Physics Technician.
Verified that incoming shipments met DOT regulations and CNSI site disposal criteria.
Responsible for ensuring off-load operations were conducted in a
safe manner and personnel exposures were kept j
as low as reasonably achievable.
Also conducted surveys and released equipment and vehicles off-site.
April 1985-l Sept. 1985 Department of Energy, Nevada Operations, Co-op Health Physicist.
Involved in classified projects with the nation's weapons testing program at the Nevada test site.
Researched noble gas leakage and developed reports on the extremity TLD program.
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i i
I B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT USNRC LICENSE SNM-1168, DOCKET 70-1201 PART I CHAPTER 11.0 ORGANIZATION AND PERSONNEL NAME:
GC.rald B. Lindsey TITLE:
Health Physicist j
i CITIZEN OF UNITED STATES i
i l
EDUCATION:
1975 Graduate of Virginia Polytechnic Institute and f
State University, Blacksburg, Virginia -
B.
S.
in Biology
[
CVCC Emergency Medical Technician 110 hours0.00127 days <br />0.0306 hours <br />1.818783e-4 weeks <br />4.1855e-5 months <br /> (coordinated through Blue Ridge Emergency Medical l
Service) i EXPERIENCE: 1969-1976 Lynchburg General Hospital Emergency Room.
Duties include vital
- signs, emergency aid, patient care.
l 1976-1983 Babcock Wilcox
- Company, Commercial Nuclear Fuel Plant.
Employed as a QA lab technician 5
years; Health-Safety Monitor - 2 years.
1983-1985 Babcock Wilcox
- Company, Lynchburg
(])
[
Research Center.
Employed as a H.P.
Surveyor for the Building C
Decommissioning Project.
Oct. 1985 -
Apr 1986 Babcock Wilcox
- Company, Commercial Nuclear Fuel Plant.
Employed as a Senior Health-Safety Monitor.
April 1986 -
Present B&W Fuel Company (Babcock & Wilcox Co.).
Employed as Health-Safety Foreman.
Duties include standard review and implementation, safety training program, plant safety audits, procedure kTiting, accident investigations.
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l B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT l
USNRC LICENSE SNM-1168, DOCKET 70-1201 PART I CHAPTER 11.0 ORGANIZATION AND PERSONNEL O
NAME:
Darryl L. Gordon TITLE:
Sr. Health Physicist j
CITIZEN OF UNITED STATES i
University of Lowell, Lowell,- MA EDUCATION:
1988 B.S.
Radiological Sciences EXPERIENCE: May, 1991 -
i Present B&W Fuel Company, Commercial Nuclear Fuel
- Plant, Health Physicist.
Responsible for Coordination, Management and Technical Development of the Radiation Protection Program for fuel manufacturing and field operations refurbishment divisions.
This responsibility includes radiological training, emergency response coordination, compliance with NRC, EPA, State, and Local regulations, i
_ procedure development,
- Bioassay, and ALARA l
Program.
l 1
l July, 1988 -
i O
April, 1991 Portsmouth Naval Shipyard, Portsmouth, NH, Radiological Control Technician.
Responsible i
for Radiation and Contamination control associated with the overhaul, maintenance, and l
refueling of Naval nuclear propulsion systems.
l Established guidelines for various industrial tradesmen to reduce
- exposure, minimize radwaste, and prevent spread of contamination l
to uncontrolled areas, personnel, tools and l
equipment.
Assisted in Processing and disposal of
- waste, man-rem estimates, procedure development, environmental impact monitoring, decommissioning, and radioactive material shipments.
Jan. 1986 -
f Jan. 1987 Pennsylvania Power and Light
- Company, Allentown, PA, Health Physicist.
As i
j Cooperative Associate, performed various activities to assist the corporate Health Physics organization in support of an operational two-unit BWR (SusquehannaSES) including resolution of operational HP problems, ALARA review, LLRW storage facility safety analysis, primary system gamma PAGE:
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i i
B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT j
USNRC LICENSE SNM-1168, DOCKET 70-1201 PART I CHAPTER 11.0 ORGANIZATION AND PERSONNEL O
NAME:
Darryl L. Gordon (cont'd) spectroscopy, and man-rem estimates.
Also coordinated the activities of the company's by-products materials license including source management and inventory, regulatory 1
compliance, and instrument calibration services.
May, 1985 -
i August, 1985 l
Applied Health Physics, Inc.,
- Holyoke, MA, i
Health Physics Technician.
Performed cleanup operations of a large manufacturing facility l
following a
fire involving Polonium-210.
Responsible for air, water, soil, and surface 4
J contamination surveys and removal of 1
contaminated plant equipment.
Packaged and shipped Radioactive-LSA waste and interacted with regulatory officials (NRC/ EPA) to monitor the total environmental impact of the fire.
MEMBERSHIPS / CERTIFICATIONS:
4 I
O Certified Radiological Control Technician -
,)
(NAVSEA 389-0288 Art. 108) a 1,
1 1
i i
l Iv PAGE:
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l B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT USNRC LICENSE SNM-1168, DOCKET 70-1201 CHAPTER 11.0 ORGANIZATION AND PERSONNEL PART I f%
\\')
NAME:
Karl L.
Bennett i
TITLE:
Industrial Safety and Environmental Control Officer Masters Degree in Safety Management, West EDUCATION:
1990 Virginia University, Morgantown, West Virginia Associate of Arts Degree, Major in Mining 1985 Technology, Salem College, Salem, West Virginia 1982 - Graduate, Resident II College Cooperative Safety Training Program, National Mine Health and Safety Academy, Beckley, West Virginia 1979 - Bachelors Degree, Major in Social Studies / Minor in Safety, 1979 Glenville State College, Glenville, West Virginia EXPERIENCE:
1990 - Present Industrial Safety and Environmental Control Officer -
Working for the Health-Safety Department.
O Responsibilities include:
Investigating and filing accident reports, ensuring compliance with the local safety rules, maintaining compliance for our NPDES permit to include reporting commitments, and ensure adequate training is being performed for CNFP personnel and the emergency teams in regard to industrial safety.
1985-1990 Section
- Foreman, Consolidated Coal Corporation, Morgantown, West Virginia.
Promoted from Project Engineer to Section Foreman with responsibilities for coal production and safety.
Trained and supervised a crew of seven.
Conducted routine mine inspections to evaluate hazardous risks and implement various appropriate safety procedures.
1983-1985 Supply Sergeant, US Army, Salem, West Virginia Primarily responsible for the planning, procurement and management of supply functions in support of a 70-man 1
combat engineering unit.
Forecasted material requirements, completed all documentation, and distributed / documented inventory.
Assisted commander
~
with a variety of personnel and administrative matters.
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l i
e B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT USNRC LICENSE SNM-1168, DOCKET 70-1201 PART I CHAPTER 11.0 ORGANIZATION AND' PERSONNEL i
NAME:
Karl L. Bennett (cont'd)
CERTIFICATIONS:
I
- Assistant Mining Foreman #35244-36, State of West Virginia, 1987
- Impoundment Inspection, 1982
- Noise Level Testing, 1981
- Dust Calibration and Maintenance (Underground 1
Surface), 1981
- Dust Sampling (Underground and Surface), 1981
- Secondary Education Teaching Certification, State of West Virginia, 1978 PROFF.5SIONAL AFFILIATION:
I
- Member, American Society of Safety Engineers
- Member, Non-Commissioned Officer Club l
1 i
l 4
t(
(a)
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r 4
B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT USNRC LICENSE SNM-1168, DOCKET 70-1201 PART I CHAPTER 11.0 ORGANIZATION AND PERSONNEL 1
O t
NAME:
William T. Foot TITLE:
Facilities Manager i
EDUCATION:
1970 BS in Industrial Economics, Purdue University, l
West Lafayette, Indiana EXPERIENCE: Sept. 1991 to f
Present l
Facilities
- Manager, B&W Fuel Company I
Responsible for operation and maintenance of f
plant, grounds, and equipment.
Supervise 3 l
persons directly and 15 indirectly.
Plans additions to buildings and plans for efficient i
layout of equipment.
Aug. 1989 -
Aug. 1991 President, Purchasing Services, Inc.
PSI provided services to clients in the areas of i
Project
- Buying, Cost Reduction
- Projects, Expediting, Vendor Sourcing and Evaluations, and recommended and provided Personal Computer software for Purchasing to clients.
PSI also l
provided temporary replacement for buyers and O
purchasing managers.
April 1988 -
l Present Project Procurement Manager, William T. Foot, CPM - As a self-employed individual and under contract to. Babcock & Wilcox, Fossil - Power Division, I managed the purchase of over 35 million dollars worth of materials and engineered products for a paper mill expansion project (Weyerhaeuser).
I coordinated the purchasing activities on the project between B&W and the engineering firm (CRS Sirrine)
I hired by B&W.
I developed a Purchasing plan, hosted vendor
- meetings, interfaced with engineers and salesmen, determined strategy and led negotiations, and wrote purchase orders.
Oct. 1984 -
Feb. 1987 Manager, Plant Purchasing, B&W - Supervise.d four buyers who purchased raw materials and MRO supplies to support manufacture of nuclear fuel for electric utilities.
Personally O'uJ responsible for purchase of the two highest l
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i B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT USNRC LICENSE SNM-1168, DOCKET 70-1201 PART I CHAPTER 11.0 ORGANIZATION AND PERSONNEL 1
b NAME:
William T.
Foot (cont'd) value commodities totalling 13 million dollars annually.
Interfaced with vendors, engineers, and plant manufacturing personnel.
Responsible for sourcing, vendor evaluations, proposal
- analysis, contract
- writing, and expediting.
March 1983 -
Oct. 1984 Group Leader, Sublet Purchasing - Supervised five buyers who purchased machined parts and welded fabrications for nuclear power and coal-fired utility boiler projects. Developed i
a computerized data base for sublet fabricators and machine shops that enables buyers to find the ideal vendor for practically any conceivable project.
March 1980 -
March 1983 Purchasing Coordinator, B&W, Barberton, OH -
Supervised three people who supported B&W's
['~
fossil boiler proposal group. Responsible for
(
scheduling and expediting buyers to purchase heavy equipment to meet contract schedules.
Developed purchasing plans for new contracts, resolved problems such as cancellations, delays, extension of warranties, etc.
July 1977 -
March 1980 Senior Buyer, B&W, Barberton, OH - Purchased electric motors, gears, reducers, couplings and other power transmission products for large utility boiler projects.
Achieved over 8% cost savings on total order value of over fifteen million dollars.
Developed sources and placed orders with Japanese vendors for precision gearing.
1970-1977 Various Manufacturing Assignments, B&W, Barberton, OH Held several assignments within Manufacturing including Mfg. Trainee, Project
- Engineer, Shop
- Foreman, and Mrf.
Engineer in B&W's Naval Nuclear Division.
O
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I B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT
~
USNRC LICENSE SNM-1168, DOCKET 70-1201 ORGANIZATION AND PERSONNEL i
PART I CHAPTER 11.O l
i i
liAME:
William T. Foot (cont'd) i PROFESSIONAL CERTIFICATIONS AND AFFILIATIONS:
Certified Purchasing Manager, National Association of Purchasing l
i Management l
i PMAC-V, Purchasing Management Association of the Carolinas and i
Virginia - Member I
Central Virginia Chapter, PMAC-V - Membership Chairman, Board of Directors I
?
l I
ii 4
d i
i i
r i
i i
i s
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i B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT USNRC LICENSE SNM-1168, DOCKET 70-1201 PART I ORGANIZATION AND PERSONNEL CHAPTER 11.0 s
O i
NAME:
Richard W. Penoza l
TITLE:
Manager, Field Operations CITIZEN OF UNITED STATES EDUCATION:
B.S.
- Mechanical Engineering, Lawrence Institute l
of Technology l
M.A.
- Industrial Management, Lynchburg College Assistant Chief EXPERIENCE: 1971-1973 DACAM Corporation Engineer.
Responsible for the design and development of new packaging equipment, production
- follow, and field service engineering.
I 1973-1979 Babcock & Wilcox Company, Naval Nuclear l
Fuel Division - Engineer.
Held several positions related to the manufacture of shipboard nuclear reactor core components during this time period including Manufacturing Engineer, Process Control Engineer, and Sales Specialist.
~
O Project Engineer.
1979-1981 Owen Mayes Responsible for the design and installation of industrial process piping systems and production equipment.-
i 1981-1983 Babcock & Wilcox, Special Products & In-Service Inspection Tooling Design i
Supervisor.
Responsible for supervising
{
4 to 6 engineers whose duties include'the
- design, fabrication.
and testing of special mechanical tooling for all nuclear applications.
1983-1986 Babcock & Wilcox, Special Products & In-i Service Inspection Plant Service Tooling
- Manager, Tooling Applications i
Manager.
Managed teams of 7
to 18 r
engineering personnel whose duties included the design, fabrication, and testing of special remote tooling and video support equipment for use in the inspection and servicing of nuclear reactors.
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)
s B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT -
{
USNRC LICENSE SNM-1168, DOCKET 70-1201 ORGANIZATION AND PERSONNEL i
CHAPTER 11.0 PART I O
NAME:
Richard W. Penoza (cont'd) l' EXPERIENCE: 1986-'
Present B&W Fuel Company (Babcock & Wilcox Co.)
l Field Operations Manager. Manages and directs all activities related to field operations on irradiated nuclear fuel.
Responsibilities include directing the design, fabrication, l
- testing, and qualification of new field l
service tooling; overseeing eh naintenance, j
reconditioning, transportation, and
~
documentation of the adequacy of existing tooling; providing for the training and certification of field service personnel; and i
interfacing with customer representatives at the reactor sites to assure satisfaction with the work.
t i
t l
l I
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_m B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT USNRC LICENSE SNM-1168, DOCKET 70-1201 PART I' CHAPTER 11.0 ORGANIZATION AND PERSONNEL
!O NAME:
L. A. Hassler s
TITLE:
Senior Principal Engineer EDUCATION:
B.S.
- Physics, St. Louis University, 1965 2
i Ph.D - Nuclear Engineering, University of Viriginia, 1
1973 l
EXPERIENCE: B&W Fuel Company, Senior Principal Engineer in the Fuel Engineering Section with 20 years experience at BWFC in 3
the areas of radiation transport, shielding, and criticality safety.
In the area of criticality safety he has been involved in the following tasks:
l Attending ORNL KENOIV training course and KENOVa training course.
i Analysis of the disrupted core at TMI-II and j
analytical design of the TMI-II defueling canisters using KENOIV program, i
On loan for three months to the Navel Nuclear Fuel Division (NNFD) criticality safety group.
Supported criticality safety analysis for storage at NNFD.
Provided criticality design analysis for the BR-100 spent fuel shipping container using KENOIV program.
Provided criticality analysis for the NNFD 5X22 shipping container SARP license submittal.
Provided criticality analysis for the new fuel
[
storage racks for Wisconsin Public Services
~
Corporation and for the spent fuel storage racks for Toledo Edison Corporation.
Provided QA review for the licensing criticality calculations for two types of LWFC new fuel shipping containers.
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i B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT USNRC LICENSE SNM-1168, DOCKET 70-1201 PART I CHAPTER 11.0 ORGANIZATION AND PERSONNEL i
NAME:
P. L. Holman i
^
TITLE:
Senior Principal Engineer Nuclear Engineering, University of Virginia, EDUCATION:
B.S.
1975.
Nuclear Engineering, University of Virginia, M.S.
1978 EXPERIENCE: B&W Fuel Company - Senior Principal Engineer with 17 years experience in reactor physics, including the following areas:
Core Follow analysis, Standard Models Development, Fuel Cycle Division for Oconee Units I, II, III, ANO-1 Unit 1,
and Crystal River, Licensing, Reload Licensing Analysis Task Engineer, Maneuvering analysis, and Criticality calculations using Monte Carlo methodology.
Recent criticality work involved licensing the ANF/BWFC Model 51032-2 new fuel shipping container and also included separate criticality analyses for new and spent fuel storage racks for NUSCO and the Wisconsin Public Services Corporation.
Preceding that work was O,
the criticality analysis for the Toledo Edison new and spent fuel storage racks which involved an enrichment limit increase utilizing burnup credit.
Additional criticality work involved the analysis for the GPU TMI-2 defueling canisters and the DOE 100 ton rail-barge shipping cask.
TECHNICAL PAPERS AND PUBLICATIONS:
"TMI-2 Defueling Canisters Reactivity Analysis", ANS Transactions, 1986.
"Three-Dimensional Analyses of a Highly Heterogeneous PWR Using the NOODLE Code", ANS Transactions 1988.
PROFESSIONAL AFFILIATIONS:
American Nuclear Society, Virginia Chapter ANS ON)
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1 I
l B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT 1
USNRC LICENSE SNM-1168, DOCKET 70-1201 i
PART I CHAPTER 11.0 ORGANIZATION AND PERSONNEL h
D NAME:
S. A. Alafifi TITLE:
Engineer II EDUCATION:
B.S.
- Nuclear Engineering, University of Tennessee, 1989 i
M.S.
- Nuclear Engineering, University of Tennessee, 1
1992 Graduate course work included:
l
- Introduction to Nuclear Criticality Safety
- Selected Topics in Nuclear Criticality Safety I
EXPERIENCE: 5/91 -
Present B&W Fuel
- Company, Engineer II.
Performs nuclear operations and licensing analysis, core follow analysis, codes maintenance and certifications, shipping cask and storage container criticality analysis.
1989 -
1990 University of Tennessee, Knoxville, TN Graduate Research Assistant.
Performed several nuclear criticality safety analysis lp for Martin Marietta Energy Systems, Inc. at l
Portsmouth, Ohio using the KENO Va code on the ORNL computer system.
Nuclear Criticality Safety Work included:
Nuclear Criticality Safety Analysis of the X-342 Building Sump Pump Pit at the Portsmouth Gaseous Diffusion Plant.
i Nuclear Criticality Safety Study of Loss of moderation Control in 10-Tom and 2 1/2-Ton UP.
Cylinders.
Nuclear Criticality Safety Analysis of a Mixed Waste Storage Facility proposed by Martin Marietta Energy Systems, Inc. to store waste in 55-gallon or 110-gallon drums containing U-235 generated at the Portsmouth Enrichment Plant.
Validation of KENO IV and the 123-group cross section library for LWR fuel storage and i
shipping applications.
O V
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i B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT USNRC LICENSE SNM-1168, DOCKET 70-1201 PART I CHAPTER 11.0 ORGANIZATION AND PERSONNEL NAME:
Francis M. Alcorn TITLE:
Manager, Nuclear Criticality Safety Engineering CITIZEN OF UNITED STATES i
Nuclear Engineering, North Carolina State EDUCATION:
B.S.
University, 1957 M.B.A. - Master of Business Administration, Lynchburg College,1974 - Graduate Study in Nuclear Engineering, University of Virginia EXPERIENCE: 1957 - 1960 Babcock & Wilcox, Atomic Energy Division, Lynchburg, VA.
Functioned as a Nuclear Engineer doing both core neutron physics and shielding calculations.
1960 - 1961 General Nuclear Engineering Corporation, Staff Physicist.
Engaged in core neutron physics design and analysis of the Boiling Nuclear Superheat Reactor. Wrote physics articles for Power Reactor Technolouv, which was published by GNEC for the AEC at that time.
l 1961 - 1964 Babcock
- Wilcox, Nuclear Power Generation
- Division, Lynchburg, VA.
Concerned with -core neutron physics i
analysis and design of the Consolidated Edison Reactor, the Liquid Metal Fuel
- Reactor, the Babcock Wilcox Test Reactor, the Advanced Test Reactor, the Heavy Water-Organic Cooled Reactor Concept, and Babcock & Wilcox Pressurized Water Reactor Concepts.
Developed methods for and performed calculations for criticality, fuel depletion, nuclear safety coefficients, power
- profiles, nuclear fuel
- costs, and critical experiment analysis.
Worked in the areas of kinetic safety analysis.
G/
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I B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT l
USNRC LICENSE SNM-1168, DOCKET 70-1201 PART I CHAPTER 11.0 ORGANIZATION AND PERSONNEL i
NAME:
Francis M. Alcorn (cont'd)
EXPERIENCE: 1964 - 1969 Babcock
- Wilcox, Utility Power Generation Division (formerly Nuclear Power Generation Division),
Lynchburg, VA.
Physicist in the PWR Development j
Section and was responsible for determining the most economical method i
for utilizing plutonium as a recycle fuel i
in B&W's pressurized water reactor concepts.
In
- addition, was Nuclear Criticality Safety Advisor.
to the j
Company's Naval Nuclear Fuel Division.
1969 - 1971 Babcock Wilcox
- Company, Lynchburg Research
- Center, Lynchburg, VA Criticality Specialist, Nuclear Safety l
Engineer.
Transferred to the LRC as i
Nuclear Criticality Safety Specialist for l
l Babcock & Wilcox's Naval Nuclear Fuel Plant, Commercial Nuclear Fuel Plant, and the LRC.
i 1971 to i
l April 1987 Babcock
- Wilcox, Lynchburg Research l
- Center, Lynchburg, VA Supervisor, Nuclear Criticality Safety Group.
This group was the Company's.
central organization which provided
- guidance, developed and validated the analytical methods needed for criticality evaluations, did criticality calculations, performed nuclear safety i
- audits, and gave assistance to the various divisions of the Company and the Company's customers in matters related to l
nuclear criticality safety.
In addition to responsibility as supervisor of this group, was the Nuclear Safety Officer for the Lynchburg Research Center (LRC).
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l B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT USNRC LICENSE SNM-1168, DOCKE'E 70-1201 PART I CHAPTER 11.0 ORGANIZATION AND PERSONNEL NAME:
Francis M. Alcorn (cont'd)
EXPERIENCE: April 1987 -
Present Manager, Nuclear Criticality Safety Engineering.
Responsible for managing the Nuclear Criticality Safety Engineering Unit which develops and validates the analytical methods needed for criticality safety evaluations, performs criticality safety calculations needed within Babcock & Wilcox, 4
conducts nuclear safety audits, and assists l
the various divisions of the Company and the Company's customers in matters related to nuclear criticality safety. This unit, within the Naval Nuclear Fuel Division, was formerly located within the Research and Development Division; its responsibilities and functions remain essentially unchanged.
Also the Nuclear Safety Officer for the Naval Nuclear Fuel Division Research Laboratory (formerly the Lynchburg Research Center).
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B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT USNRC LICENSE SNM-1168, DOCKET 70-1201 PART I CHAPTER 11.O ORGANIZATION AND PERSONNEL NAME:
J. Wayne Harwell TITLE:
Principal Engineer, Nuclear Criticality Safety CITIZEN of UNITED STATES l
EDUCATION:
B.
S. Nuclear Engineering, 1963 Mississippi State University M.
S.
Nuclear Engineering, 1968 l
Mississippi State University EXPERIENCE: 1963-1964 Ingalls Shipbuilding Corporation
- Engineer, Shielding Structure Unit Performed nuclear shield design modifications and project management related duties for shielded structures on nuclear submarines during construction.
l 1964-1968 Mississippi State University - Instructor l
& Graduate Assistant Engineering Graphics Department.
Graduate assistant and instructor teaching freshmen engineering drawing classes.
Attended graduate school in nuclear engineering.
7_s k
1968-1976 Babcock & Wilcox, Nuclear Power Division, Senior Engineer, Nuclear Development Work related to self-powered neutron detectors signal-to-power conversion, core physics analytical modeling and benchmarking, core model
- analyses, core and fuel assembly design optimization and reactor vessel fluence analysis.
1976-1976 Southern Company Services, Senior Core Analysis Engineer.
Developed core l
physics models for the Farley PWR cores including generation of cross section l
tablesets and geometries for PDQ07 using l
EPRI ARMP code package.
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I I
1 B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT l
USNRC LICENSE SNM-1168, DOCKET 70-1201 PART I CHAPTER 11.0 ORGANIZATION AND PERSONNEL i
NAME:
J. Wayne Harwell (cont'd) l l
EXPERIENCE: 1976-1988 Babcock
- Wilcox, Fuel Management Analysis.
Responsible for fuel cycle design and fuel management analyses for Connecticut Yankee and B&W design 177
{
fuel assembly reactor. cores using the i
PDQ07 computer code. Work includes cross l
section tableset generation and fitting strategy development, advanced' fuel and reactivity control concept development,.
[
new fuel management concepts and use of transport codes for analytical model j
development.
i t
Principal i
i 1988-Babcock & Wilcox. Company Engineer Nuclear Criticality Safety Engineering.
Performs nuclear criticality safety evaluations using the I
SCALE computer code package that utilizes i
the Monte Carlo computer codes (KENO-4 j
and KENO-5) and transport computer code (XSDRN).
Responsible for methods development along ~with computer' codes benchmarking, verification, and validations for the codes used in nuclear l
criticality calculations.
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B&W TUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT tJSNRC LICENSE SNM-1108, DOCKET 70-1201 PART I CHAPTER 11.0 ORGANIZATION AND PERSONNEL
\\
NAME:
James G. Tennant TITLE:
Manager, Production & Inventory Control EDUCATION:
1970 BS, Industrial Technology, East Tennessee State l
University.
Kepner-Tregoe Project Management and Problem Solving / Decision Analysis courses; AMA l
Manufacturing Management; GE Manufacturing Systems Implementation and Experienced Manager courses; Creative Leadership courses; plus various other professional workshops.
EXPERIENCE:
1991-Present Manager, Production & Inventory Control, B&W j
Fuel Company, Lynchburg, VA.
Responsible for l
the Nuclear Material Control
- plan, l
accountability, scheduling and transportation.
1989-1991
- Manager, Advanced Manufacturing
- Systems, l
Acadia
- Polymers, Inc.,
- Roanoke, Virginia.
l Reporting to Vice President of Development.
Responsible for corporate MRPII objectives;
[,'
including system implementation, J.I.T.
l (
education, product on-time delivery, master 1
planning and inventory objectives.
1983-1989 Program Manager, Manufacturing and Engineering
- Systems, General Electric
- Company, Mobile Communications Business, Lynchburg, Virginia.
Reported to Manager of Information Systems.
Directed ten information systems and end-users in new systems implementation and interfaced with nanufacturing and engineering management to define systems strategies for manufacturer of mobile communications equipment.
1979-1983 Director, Manufacturing Support, The Singer
- Company, American Meter
- Division, Philadelphia, Pennsylvania.
Reported to Vice President of Manufacturing.
Directed two
)
l project specialists and supervised five site managers.
Responsible for division manufacturing HRP11 and information systems including systems implementation, production
- planning, new product introduction, and b
monitoring of customer service performance for Q
manufacturer of gas meters and regulations.
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B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT l
USNRC LICENSE SNM-1168, DOCKET 70-1201 l
ORGANIZATION AND PERSONNEL j
PART I CHAPTER 11.0 i
NAME:
James G. Tennant (cont'd) l l
1970-1979 I
Manufacturing Manager,-.The Singer Company, Motor. Products Division,
- Pickens, SC, and Clarksville, AR.
Reported to Plant Manager.
i Directed activities of three general foremen, i
22 production supervisors, and up to 1300 i
hourly employees in the manufacture of j
portable electric tools.
Responsible for all aspects of shop operations, materials and production control, operations training and i
safety programs.
Controlled $8MM operating i
budget.
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B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT J
USNRC LICENSE SNM-1168, DOCKET 70-1201 PART I CHAPTER 11.0 ORGANIZATION AND PERSONNEL
\\
11.4 Operatina Procedures Written procedures for the conduct of specific operations-including maintenance and development of work within the plant are prepared by the functional component responsible for that activity. Health Safety activities are controlled by detailed operating procedures developed by Health-Safety to assure standardization and accuracy.
All written procedures are i
reviewed and approved by appropriate representatives of plant management.
If SNM or other radioactive materials are involved in an activity, approval by the Manager, Safety and Licensing or his designee shall be required prior to implementation.
Likewise all Health-Safety procedures are approved by the Manager, Safety and Licensing as well as by affected members of plant management.
Health-Safety procedures are reviewed periodically and updated accordingly.
l Applicable procedures are made available in the work area and adherence to procedure is required of all personnel.
B 11.5 Trainino All personnel receive basic training in radiological, industrial, and nuclear safety upon being hired. This initial O,
training is a cooperative effort involving Personnel, Health-Safety, and the employee's supervisor and is designed to satisfy the requirements of 10 CFR 19.12.
particular emphasis is placed on the nature of the materials handled, ALARA plant safety program and rules, 10 CFR 19 requirements, and the emergency evacuation system.
Specific areas covered in the safety training program are as follows:
11.5.1 Initial Ernolovee Trainino Employees are referred to Health-Safety by the Personnel Department for initial training in safety.
The entire plant safety program is reviewed in some detail with particular emphasis being placed on specific areas depending on the employee's job assignment. A brief discussion of, and familiarization with, the general principles of health physics and nuclear safety is included.
The employee is informed of his rights and responsibilities under CFR 19, and OSHA.
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l i
l B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT i
USNRC LICENSE SNM-1168, DOCKET 70-1201 PART I CHAPTER 11.0 ORGANIZATION AND PERSONNEL
[
11.5 Trainina 11.5.1 Initial Employee Traininc Following the initial indoctrination depending on the employees work location, they shall receive additional safety training from their immediate supervisor regarding the nuclear and radiological safety I
requirements of their specific job assignment.
Training sessions are documented and filed as part of the employee's Health-Safety record.
11.5.2 Ernployee Retrainino continuing training of a general nature is provided as necessary by Health-Safety and supervision.
This training may be formalized (i.e.,
" classes")
or informal and conducted as a part of routine Health-Safety audits.
Formalized retraining may be utilized to explain operational changes affecting
- safety, control of special problems such as increased airborne activity, or changes in license specifications.
The responsibility for determining the necessity for retaining or special training rests with Health-Safety
(
based on plant conditions or the request of
, (
supervision.
Radiation workers are all retrained annually as a routine part of our safety training program.
The retraining sessions are documented and kept as part of the employee's Health-Safety record.
11.5.3 Specialized Trainina 11.5.3.1 Respiratory Protection Training and retraining in the use of respiratory protection devices is provided by Health-Safety as required.
Points relating to proper use are covered as the unit is issued and fitted by Health-Safety.
This approach provides continuing review of respiratory protection requirements.
Should situations arise where frequent use of a respirator is necessary, frequent Health-Safety surveillance will assure continued j
proper application.
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B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT USNRC LICENSE SNM-1168, DOCKET 70-1201 PART I CHAPTER 11.0 ORGANIZATION AND PERSONNEL 11.5 Trainina 11.5.3.2 Emercency Teams Trainina Specialized training for special and emergency response units such as the Fire Brigade, Radiation Monitoring Team and First Aid personnel is coordinated by Health-Safety.
Fire Brigade training is conducted by representatives of Health-Safety and/or local Fire Departments and covers the use of fire fighting equipment and agents available at CNFP.
Radiation Monitoring Team members receive periodic training from Health-Safety in emergency response techniques, instrument use and maintenance, health physics and nuclear safety fundamentals, respiratory protection and contamination control.
Annual evacuation drills are generally utilized as a training period for the emergency teams.
First aid training is given by a qualified instructor and is the standard Red Cross program or equivalent.
Efforts are made to recruit individuals who have had previous O
training such as military damage control or Civil Defense radiation monitoring.
11.6 Chances in Procedures. Facilities, and Eauipment 11.6.1 Procedural Chances Procedural changes are initiated by the functional component responsible for that activity.
Such procedural changes are reviewed and approved by plant management prior to implementation.
If the activity involves SNM or other radioactive materials, the
- Manager, Safety and Licensing must approve the procedural change prior to implementation.
11.6.2 Facilities and Eautoment Chances Changes or modifications to facilities and equipment that have a potential impact on nuclear, PAGE:
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B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT
~
USNRC LICENSE SNM-1168, DOCKET 70-1201 PART I CHAPTER 11.0 ORGANIZATION AND PERSONNEL 11.6 Chances in Procedures. Facilities. and Eculpment l
l 11.6.2 Facilities and Eauipment Chances l
radiological, industrial, or chemical safety must be i
reviewed and approved by the Safety Review Board and/or the Safety Review Board Chairman or his qualified designee prior to initiation.
The Safety Review Board is described in detail in Chapter 2.0 of Part I.
11.6.2.1 Initiatina Chances
[
The responsibility for initiating changes as described in 11.6.2 is usually given to the immediate operational supervisor or manager.
The requested change is documented and submitted to the Safety Review Board Chairman for initial review.
11.6.2.2 Analysis of Chances The Safety Review Board Chairman determines what safety evaluations are needed.
If the proposed modification changes the basis on which the nuclear
\\
criticality safety was originally I
assessed, a technical evaluation by the nuclear criticality safety group will be initiated.
The organizational structure and minimum qualifications of the nuclear criticality safety group is as described in Chapter 4.0.
Radiation safety evaluations will be performed for new or revised operations to assure personnel protection is maintained.
Chemical and industrial safety aspects of proposed modifications will also be evaluated for acceptability.
These evaluations are documented and retained as described in 11.6.2.6.
0)
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B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT
~
USNRC LICENSE SNM-1168, DOCKET 70-1201 PART I CHAPTER 11.0 ORGANIZATION AND PERSONNEL 11.6.2.3 Manacement Review As a minimum, the Safety Review Board Chairman or his qualified designee shall review all safety analyses performed the plant modifications prior to implementation.
The Safety Review Board Chairman will determine if Safety Review Board approval is required.
11.6.2.4 Acoroval and Verification of Chances Approval and release of plant modifications for routine use is dependent upon satisfactory completion of l
a pre-operational evaluation.
This evaluation is a final verification.that.
the proposed change has been installed consistent with the analyses performed t
under 11.6.2.2.
This evaluation will consider
- nuclear, radiological, industrial, and chemical safety as well as license compliance.
This evaluation is performed by Health-Safety personnel O,
and is approved by the Safety Review Board Chairman prior to-implementation.
Compliance of plant modifications is assured by our existing Health-Safety controls and audit programs with regard to contamination
- control, personnel i
exposures, nuclear safety, chemical and industrial hazards.
11.6.2.5 Records All
- analyses, evaluations, pre-i operational evaluations and other i
pertinent documentation relating to plant modifications will be maintained on file i
for at least six months after termination of the operation.
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i B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PIANT 4
USNRC LICENSE SNM-1168, DOCKET 70-1201 PART I CHAPTER 11.0 ORGANIZATION AND PERSONNEL i
FIGURE 11.1 l
i 1
1 3
i I
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1 i
C W. Carr Commercial Nuclear Fuel Plant Manager i
4 J
b Manager,.G. Tennant T.S. Wilkerson 4
Prod & Inv Cntrlg Mana i
" ger, Mfg Engineering K
Kna Manager,.S.Sfty&pgicensing Manager.T., Fuel Mfg.
i J
Ford 1
1 F.F. Dowdv h
R Long
[
Manager,.T. Info Services Personnel FQot I-Manager,W.T. Facilities & Serl Manage.L. Wright I
i W
r, Accounting l
f
, Manager,.WFle d Operations R
enoza 4
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-