ML20058A978
| ML20058A978 | |
| Person / Time | |
|---|---|
| Site: | 07001201 |
| Issue date: | 10/24/1990 |
| From: | Lester K BABCOCK & WILCOX CO. |
| To: | Haughney C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| NUDOCS 9010290334 | |
| Download: ML20058A978 (39) | |
Text
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LJ An Amencen Company wth Woddende Resources P.O. Bos 11646 Lynchburg VA 245061646 t
Telephone:804 522-6000 October 24, 1990 Mr. Charles Haughney Uranium Fuel Section Fuel Cycle Safety Branch Division of Industrial end Medical Safety, NMSS Nuclear Regulatory Commission Washington, D.C.
20555
REFERENCE:
SNM-1168 License, Docket 70-1201
Dear Mr. Haughney:
B&W Fuel Company's Commercial Nuclear Fuel Plant has reorganized.
Several chapters of our SNM license was effected by the restructure and have been amended to refisct the changes.
The major change is the separation of the Quality and Safety Department.
Quality Assurance is now under Mr.
W.
T. Engelke who reporta directly to the BWFC President (Old Forest Roed).
Safety la headed by the Manager, Safety and Licensing, Ms.
K. S.
- Lester, who reporta directly to the Commercial Nuclear Fuel Plant Manager, Mr.
R.
A.
Alto.
Most of the functions formally assigned to the Manager, Quality & Safet.y have been transferred to the Manager, Safety and Licensing to cupport the new organization.
Attachment I
provides the changes of effected paragrapha contained in the license.
The pages that have been changed are dated October 24, 1990, Revision 1.
The changes have also been aide barred for easy identification of the modifications.
Pages that were renumbered and not directly effected by the reorganization are also included, however, they still have the original date and revision O.
Six coplea of the amended pages have been submitted.
Please remove the former pages of the license and replace them with those included.
Should you have any comments or questions, please feel free to call me, <804) 522-6202.
Sincerely, B&W FUEL COMPANY COMMERCIAL NUCLEAR FUEL PLANT btVLLO d.
[htte Id Kathryn S.
Lester ggO2((((k901024oyoOgyg1 Manager, Safety and Licensing C
J.. J
o I
ATTACHMENT I 1
1 CHAPTER SECTION/PAGE CHANGE 2
Figure 2.1/2-1 The former organizational chart shows
- Manager, Quality Safety reporting to the CNFP Plant Manager.
The new organizational chart replaces this position with the Manager, Safety and Licensing.
2 2.1.4/2-3 This section stated that the
- Manager, Quality &
Safety or his quellfied designee shall be responalble to provide management with assurance of the effectiveness of the safety program....
The
- Manager, Quality Safety was replaced with the Manager, Safety and Licensing.
2 2.2.2/2-3 The position of Manager, Quality &
Safety was removed and replaced with the
- Manager, Safety and Licensing.
K.
S.
Lester meets the already established qualifications for this position.
2 2.3/2-5 Although the
- Manager, Quality Safety acted as the Safety Review Board Chairman, we did not commit to that.
He did serve as a board member.
This was changed to the Manager, Safety and Licensing.
We
- did, however, connect him as the SRB chairman in section 14.1.
See 14.1 for that change.
2 2.3/2-6 The annual ALARA report will now be prepared under the direction of the Manager, Safety and Licensing.
2 2.5/2-7 The Manager, Quality &
Safety was responsible for ensuring that Health-Safety Personnel are properly trained.
- Manager, Safety l
and Licensing now assumes that responsibility.
o 2
2.6/2-8 & 2-9 The Manager, Quality &
Safety was l
responsible for reviewing and approving operating procedures that involve SNM every 2 years.
He also approved all Health-Safety and SNM accountability procedures.
He was respone.ible to ensure that appropriate personnel review Health-Safety procedures annually.
All these responsibilities now i
reside with the Manager, Safety and Licensing.
2 2.7/2-9 & 2-11 The Manager, Quality &
Safety was responsible to assure that the internal inspection program is conducted effectively.
The Manager, Safety and Licensing is now responsible for this function.
The independent auditor's reports shall be submitted to the Plant Manager and he shall ensure that it is reviewed by the appropriate management.
3 3.2.3/3-10 MPC action levels exceeding those established required that the
- Manager, Quality Safety be notified.
The Plant Manger is now denoted as the person to notify.
4 4.1.2/4-1 The overall plant nuclear criticality safety is the responsibility of the
- Manager, Safety and Licensing.
S 5.1.2/5-1 Action levels for liquid effluents that are exceeded must now be reported to the Plant Manager.
8 The Radiological Contingency Plan, chapter 8, was updated on October 17, 1990 and indicated that the
- Manager, Quality Assurance, BWFC will act as the Emergency Officer so no changes need to be made.
11 11.1/11-1 It stated that the Health-Safety Section is under the
- Manager, Quality Safety.
The
- Manager, Safety and Licensing replaced this.
t
4 11 11.2.1/11-1 Responsibility for the health and safety of the CNFP is now vested in the Manager, Safety and Licensing.
11 11.2.3/11-2 The health physicist shall report to the
- Manager, Safety and Licensing.
11 11.3/11-3 & 11-10 E.J.
Coppola's resume was removed and K.
S.
Lester's resume was updated.
11 Pages 11 11-23 Due to the removal of E.
J.
Coppola's
- resume, they were renumbered but contain no direct changes.
11 11.4/11-24 All Health-Safety procedures are opproved by the Manager, Safety and Licensing.
11 11.6/11-26 Manager, Safety and Licensing must approve pro 7edural changes that involve SNM or other radioactive material prior to implementation.
11-28 They were renumbered but contain no 11 pages 11-24 direct changes.
11 Figure 11.1/11-29 A
new organizational chart was added to reflect the new management.
The line from the Manager, Field Operations, Manager, Purchasing and Manager, Accounting is dotted as they actually report to the BWFC President.
- However, they do reside at the CNFP and are responsible to comply with the SNM license and therefore indirectly report to the Plant Manager.
14 14.1/14-1 The Manager, Safety and Licensing will serve as the Safety Review Board Chairman.
K. S. Lester meets the qualifications established for the Safety Review Board Chairman.
i
B&W FGEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT USNRC LICENSE SNM-1168, DOCKET 70-1201 PART I CHAPTER 2.0 ORGANIZATION AND ADMINISTRATIVE l
2.1 Organizational Responsibilities and Authority 2.1.1 Manacement It is the responsibility of the Plant Manager to assure the safety of the operation and compliance with license l
conditions. Control shall be established by:
- deLignation of responsibility to qualified personnel
- review and approval of Health-Safety procedures
- review of program effectiveness
- prompt correction of nonconforming conditions l-The CNFP management structure is as shown in Figure 2.1.
l FIGURE 2.1 l
l OFP puwi ammKR MD.IAR CRITICR.!TY 5lEC.
i N N B M CHR.
PRODUCTION Mmm K RS Me#ER, SEETY & UC.
ADMINISTMT!W MemEE l
4 OPEMT10ML SUPulVISORS HER.THPHYSICIST RTH SFETY FORDmN
- HEALTH-SAFETY SECTION RTH SRFETY MellTORS 1
l
- (e.g., Manufacturing Engineering, Fuel Operations, Field Operations)
- (e.g., Accounting Personnel, Purchasing. Information Services)
- (not directly responsible for production functions)
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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 2.1 Organizational Responsibilities and Authority The Manager, Safety and Licensing or their qualified designee shall be responsible to provide maragement with assurance of the effectiveness of the safety program by maintaining an audit program that includes per17dic inspection of controls and operations, reports t7 management, follow-up of nonconforming conditions and necessary documentation (see Audits, Section 2.7) 2.2 Personnel Education and Experience Requirements 2.2.1 Plant Manager 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 Manager, Safety & Licensing The manager to whom the section reports shall have a Bachelor's Degree and a minimum of five years experience, which would develop an understanding of nuclear and radiation safety.
Such experience shall be of a nature which demonstrates to the Plant Manager sufficient judgment and capability to establish and maintain an effective 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 olant Health Physicist.
This person shall have a Bachelor's Degree in Science or Engineering.
A minimum of 2 years experience in applied health
~i 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 Foreman The Health-Safety Foreman shall have a high school education and three years experience in radiation safety which would develop an understanding.of nuclear and radiation safety.
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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 2.3 Safety Review Board e
The continuing effectiveness of established controls and safeguards e-Maintenance of ALARA criteria (review of quarterly air sample averages, review of surface contamination surveys) e Safety-related audit and inspection findings
-e Other items (such as abnormal occurrences) that Safety i
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 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, i
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.
.The Safety Review Board Chairman reviews all requests for changes in process and equipment which involve hazardous materials and determines if Board review is necessary.
An 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 Chairman on such minor changes.
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B&W-FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT USNRC LICENSE SNM-ll68, DOCKET 70-1201 PART.I CHAPTER 2.0 ORGANIZATTON AND ADMINISTRATIVE 2.3 Satety Review Board 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.
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 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 sont 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 the effectiveness of the radiation /nucicar safety training program.
2.4 Approval Authority for Personnel Selection Personnel selection for those CNFP staff level positions shall be approved by the Plant Manager.
2.5 Training 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 following topics:
e license. conditions e
federal regulations e
operating procedures e
radiation safety e
nuclear safety e,
emergency procedure e
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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 2.5 Training-The extent and depth of the training, relative to the detailed aspects of the health physics and nuclear safety programs, is dependent on the employee's job assignment and potential exposure to radioactive materials as determined by Health-Safety.
The initial indoctrination training shall be reinforced (as appropriate to the individual's job assignment) by the employce'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.
A continuing 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 sarety 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 monitoring and control techniques and regulatory-requirements before being allowed-to function without' direct oversight.
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4 B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT USNRC LICENSE SNM-1168, DOCKET 70-1201 PART I CHAPTER 2.0 ORGANIZATION AND ADMINISTRATIVE 2.6 Operating 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 and shall be reviewed and approved by appropriate 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 written procedures for the handling of radioactive materials shall.be approved by the Manager, Safety and Licensing, or their qualified designee.
Procedural control of activities at the CNFP are categorized as follows:
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-3afety 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 plant management.
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 the Manager, Safety and Licensing and the Manager, Production and Materials Control.
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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 2.6 Operating Procedures Other Plant Groups Procedures from other plant groups (i.e., Manufacturing, Quality Assurance) where nuclear or 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.
New operations and major operational changes shall require the written recommendation of the Safety Review Board Chairman 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.
2.7 Audits and Inspections An internal Health-Safety inspection program 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, n 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.
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B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT e
USNRC LICENSE SNM-ll68, DOCKET 70-1201 ORGANIZATION AND ADMINISTRATIVE Cl! APTER 2.0 PART I.
2.7 Audits and Inspections Independent auditors' 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 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.
2.8 Investigations and Reporting Unusual events requiring reporting under NRC regulations shall be investigated as appropriate, with results reported to plant management and NRC.
Events not otherwise requiring a report may lua reported to NRC based on potential public or media involvement, etc., in order to keep NRC appraised of the situation.
2.9-Records Plant alterations or additions, abnormal occurrences, events associated with radioactive releases, criticality analyses, audits, inspections, instrument calibration, ALARA findings, employee training.and retraining, 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-ll68, DOCKET 70-1201 RADIATION PROTECTION CHAPTER 3.0 PART I 3.2 Technical Requirements - Alpha Contamination 3.2.3 Work-Area (Controlled Area) Air Sampling In order to verify the adequacy of the ventilation and containment systems, air sampling technique (s) shall be employed.
Air samplers shall be positioned at (controlled area) work stations based on evaluation of smoke tests, special air samples, and operator working position.
The location of fixed air sample heads shall be reexamined for effectiveness at least annually.
Based on operational status and/or exposure potential, air samples shall be collected continuously during each operational shift.
Sample media shall be changed for analysis at the end of each shift and evaluated at-the start of the next shift.
General area air samples shall be collected and analyzed as' stated in the preceding paragraph.
Upon initiation of new operations, non-repetitive operations, or operations modified such that previous airborne contamination levels may be affected, Health-Safety shall verify that satisfactory control is being maintained by means of the air sampling techniques stated above.
The scope and duration of such special programs shall be determined by Health-Safety based on g_od health physics practice.
The following action points shall apply to the routine work station air. sampling program:
PERSONNEL EXPOSURE Ouarterly % MPC Averace Action i 25%'
No action required.
> 25%, 1 50%
Report to Plant ~ Manager or designee.
Evaluate operation and containment.
> 50%, f 75%
Report to the Plant Manager.
Take steps necessary to' lower airborne activity to acceptable range.
> 75%
Notify the-Plant-Manager.
Terminate operation if > 100% MPC.
Modify or install air. capture devices.
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C&W FUEL COMPANY,. COMMERCIAL NUCLEAR FUEL PLANT USNRC LICENSE SNM-ll68, DOCKET 70-1201 CHAPTER 4.0 NUCLEAR CRITICALITY SAFETY PART I 4.1 Administrative Conditienn 4.1.1 Design Philosophies The double contingency principle as defined in the American Nuclear Standard ANSI /ANS-8.1 shall be followed in establishing nuclear criticality safety for all equipment, systems and operations.
Process designs shall incorporate sufficient factors of safety to require at least two unlikely, independent, and concurrent changes in process conditions before a criticality accident is possible.
Where possible and practicable, reliance will be placed on equipment design in which dimensions (i.e.,
favorable geometry) are limited rather than on administrative controls.
Where structural integrity is necessary to provide assurance for safety, the design and construction of the equipment will be made -ith due regard to abnormal loads, accidents e:.d deterioration.
4.1.2 Criticality Safety Analyses With respect to the overall plant nuclear criticality safety, the Manager, Safety. Licensing is responsible for controlling all modifications and/or additions to any operation, system or equipment.
Nuclear criticality safety evaluations are performed by qualified nuclear criticality safety 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 analyses.-
Individuals not satisfying the above requirements may perform safety evaluations provided the-j ovaluations are approved in writing by a qualified-nuclear criticality safety specialist.
All nuclear criticality safety evaluations shall be independently reviewed by an individual meeting the qualifications of nuclear criticality safety specialist as defined above with.two years of experience as a Nuclear Criticality Specialist.
All evaluations shall include an appropriate statement of this review.
Both the analyzing and reviewing nuclear criticality safety specialist are independent of CNFP manufacturing 7
operations.
A library.of validated computer codes and cross: sections shall be maintained and utilized for h
l performing nuclear criticality safety evaluations.
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B&W FUEL COMPANY, COMMERCIAL NUCLE.%R FUEL PLANT USNRC LICENSE SNM-1168, DOCKET 70-1201 CHAPTER 5.0 PART I ENVIRONMENTAL PROTECTION 5.1 Effluent Control Systems A report providing the effluent results in accordance with section 5 of Regulatory Guide 4.16 dated December 1985 shall be
. submitted to the NRC semiannually.
5.1.1 Gaseous Effluent Control Gaseous effluents to uncontrolled areas are restricted and monitored as described in Chapter 3.
5.1.2 Liquid Effluent Control Potentially contaminated liquid effluents are normally processed through an evaporator and released as gaseous effluent through the HEPA filtration system.
The release limits are the same as those used for the gaseous effluents to uncontrolled areas as described in Chapter 3.
i Utilizing this process for the management of liquid effluents, the discharge from the retention tanks shall not exceed 2.5% MPC for uranium.
An investigation shall be conducted for levels exceeding 2.5% MPC, 10 CFR 20,
' Appendix B, Table II.
Circumstances may require that we dispose of liquid effluents through our retention' tank system.
If this route is used, the-liquid effluent.will be analyzed and evaluated for compliance with 10 CFR 20, Appendix B limits prior to release to unrestricted areas as indicated in the following table.
LIQU,ID EFFLUENTS
% 10 CFR 20 App. B. Table II Action "MPC"
< 20%
.No action required.
21 - 75%-
Individual releases authorized by the-Plant Manager or his alternate.
> 75%
Discharge prohibited.
Effluent routed for further treatment or disposal.
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.B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT LUSNRC LICENSE SNM-1168, DOCKET 70-1201 ORGANIZATION AND PERSONNEL CHAPTER 11.0 PART II 11.1.
Organizational Responsibilities Figure 11.1 illustrates the departmental and managerial organization at the CNFP.
The key organization responsible for maintaining the health 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 Manager, Safety and Licensing.
The Manager, Safety and Licensing reports directly to the Plant Manager.
11.2 Key Personnel Function 11.2.1 Overall Program Manaaement Responsibility for planning, coordinating, administering and managing the health and safety aspects of the CNFP is vested in the Manager, Safety and Licensing.
This position is organizationally parallel to other member of the Plant Manager's staff such as the Managers of Manufacturing Engineering and Fuel Operations.
11.2.2 The Health-Safety Section Health-Safety personnel are responsible for the general surveillance of all plant safety related 1
functions.
Specifically, these functions are described as follows:
Maintaining appropriate control of hazardous material, shipments, and receipts.
Supervising and coordinating the hazardous waste disposal program.
Assisting in personnel.and equipment-decontamination.
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,l COMMERCIAL NUCLEAR FUEL PLANT USNPC LICENSE SNM-1168, DOCKET 70-1201 CHAPTER 11.0
-PART II ORGANIZATION AND PERSONNEL 11.2 Key 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.
Leak testing on sealed radioactive sources.
Developing and disseminating procedures related to 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 reconmend appropriate restrictions or corrective measures.
The Health Physicist reports directly to the Manager, Safety &
- Licensing.
11.2.4 Health-Safety Foreman
^
The Health-Safety Foreman is 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-Safety Foreman reports directly to the-Health Physicist.
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B6W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT USNRC LICENSE SNM-1168, DOCKET 70-1201 ORGANIZATION AND PERSONNEL CHAPTER 11.0 PART II 11.2 Key Personnel Functions 1
11.2.5 Health-Safety Monitor The Health-Safety Monitor is responsible for conducting routine monitoring, sample collection and I
analytical tests to determine radiation and contamination levels.
11.3 Resumes Since it is also the responsibility of the entire plant i
l-management to assure safe operations and regulatory compliance, we are including resumes from other managerial organizations within the CNFP as well as those within the Quality and_ Safety Group.
These are as follows:
l Name Title R. A. Alto Plant Manager, Commercial Nuclear Fuel Plant D. V. Ferree Manager, Fuel Operations (Production Manager)
C. G. Dideon Manager, Manufacturing Engineering (Production Manager)
B. W. Pugh Manager, Production & Materials Control K._S.
Lester Manager, Safety & Licensing G.
B. Lindsey Health-Safety Foreman L
C. W.
Speight Manager, Facilities and Services R. W. Penoza Manager,. Field Operations (Production Manager)
F. M.-Alcorn Manager, Nuclear Criticality Safety L
Engineering l
J. M. Harwell Nuclear. Criticality Specialist Engineer b
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B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT USNRC LICENSE SNM-1168, DOCKET 70-1201 ORGANIZATION AND PERSONNEL CHAPTER 11.0 PART II NAMES-Kathryn S. Lester TITLE:
Manager, Safety & Licensing EDUCATION:
1985 - University of Nevada, Las Vegas - B.
S.
Health Physics EXPERIENCE:
Jan 1990 -
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 preparedness, and-transportation programs.
Responsible for budgeting for the Health-Safety Section.
Liaison with regulatory agencies.
May 1989 -
Jan 1990 B&W Fuel Company, License and Control Administrator.
Liaison with Federal, State and Local regulatory agencies.
Assist in the Health Physics Program for CNFP.
Feb. 1987 -
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, training, waste management, calibration of instrumentation, records maintenance (both personnel and operational history), radiation monitoring (both personnel and environmental), and liaison with
-licensing authorities.
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B&W FUEL COMPANY, COMMERCIAL NUCLLAR FUEL PLANT USNRC LICENSE SNM-1168, DOCKET 70-1201 ORGANIZATION AND PERSONNEL CHAPTER 11.0-
~PART II NAME:
Kathryn S. Lester EXPERIENCE:
1987-1989 Also responsible for analyses and evaluations to assure that radiological protection and ALARA considerations are incorporated into system and facility designs, operations and handling procedures, and personnel training programs for both customers and employees.
Sept. 1986 -
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 low-level radioactive waste burial site criteria.
Supervised projects for the proper handling, packaging, shipping, and ultimato disposal of various radioactive materials.
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 safety surveys, radiological training programs, and maintaining project records.
Participated in a major radioactive waste cleanup and disposal project with t
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 ORGANIZATION AND PERSONNEL CHAPTER 11.0 PART II NAME:
Kathryn S. Lester 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 t
manner and personnel exposures were kept as low as reasonably achievable.
Also conducted surveys and released equipment and vehicles off-site.
April 1985 -
Sept. 1985 Drpartment 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.
i~
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i B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUE! PLANT
'USNRC LICENSE'SNM-1168, DOCKET 70-1201 ORGANIZATION AND PERSONNEL CHAPTER 11.6 PART II 7
NAME:
Gerald B.
Lindsey TITLE:
Health-Safety Foreman CITIZEN OF UNITED STATES EDUCATION:
1975 Graduate of Virginia Polytechnic Institute and 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 Service)
EXPERIENCE:
1969-1976 Lynchburg General Hospital Emergency Room.
Duties include vital signs, emergency aid, patient care.
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 -
April 1986 Babcock & Wilcox Company, Commercial Nuclear Fuel Plant.
Employed as a Senior _ Health-Safety Monitor.
April 1986 -
Present B&W Fuel Company (Babcocx & Wilcox Co.).
Employed as Health-Safety Foreman.
i Duties include standard review and implementation, safety training program, plant safety audits, procedure l
J writing, accident investigations.
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B&W FULL. COMPANY, COMMERCIAL NUCLEAR FUEL PLANT USNRC LICENSE SNM-1168, DOCKET 70-1201 ORGANIZATION AND PERSONNEL CHAPTER 11.0 PART II.
i NAME:
Charles W. Speight TITLE:
Manager, Facilities and Services CITIZEN OF UNITED STATES EDUCATION:
Matriculation Certificate, Hebden Bridge Grammar School, Hebden Bridge, England (1941).
National Certificate Electrical Engineering, Coventry, England (1950)
EXPERIENCE:
1944-1946 Royal Navy 1946-1947 S. Sutcliffe & Son, Ltd., Mythc1mroyd, Yorkshire, England - Office Clerk.
1947-1948 Government Training Center, Leeds, England - Draftsman Trainee.
1948-1949 General Electric Co., Ltd., Coventry, England - Draftsman.
Made drawings of equipment control panels for telephone communication, t
1949-1950 Armstrong-Siddeley Motors, Ltd.,
Coventry, England - Draftsman.
Made drawings of a facility for testing aircraft jet engines.
1950-1952 Raleigh Industries, Ltd., Nottingham, 3
England - Draftsman.
Designed production and service equipment for use in manufacture of bicycles.
1952-1953 A. V. Roe (Canada) Ltd., Malton, Ontario, Canada - Draftsman.
Made layouts of the machine shop for aircraft jet engine manufacture.
1953-1956 Canadian Westinghouse Company, Hamilton, Ontario, Canada - Draftsman, Plant Engineering Department.
Designed miscellaneous equipment for use in manufacture of Westinghouse products.
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F
'B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT USNRC LICENSE SNM-1168, DOCKET 70-1201 ORGANIZATION AND PERSONNEL j
CHAPTER 11.0 PART II I
NAMES.
Charles W. Speight EXPERIENCE:
1956-1960 H. G. Acres and Company, Ltd., Niagara j
Falls, Ontario, Canada - Draftsman.
Made drawings of piping arrangements for fossil fired power plants.
1960-1961 Babcock & Wilcox Company, Fossil Power Generation Division, Barberton, Ohio -
Draftsman.
Made drawings of plant equipment and property plots.
1961 New Zealand Ministry of Works, Public Works Department, Wellington, New Zealand - Draftsman.
Made HVAC ducting drawings for government buildings.
1961-1968 Babcock & Wilcox Company, Fossil Power Generation Division, Barberton, Ohio -
Senior Draftsman until 1967 then Assistant Project Engineer until 1968.
Responsibilities included design of plant equipment and machines.
1968-1980 Babcock & Wilcox Company, Nuclear Materials and Manufacturing Division, Commercial Nuclear. Fuel Plant, Lynchburg, Virginia - Works Industrial Engineer.
Responsible for-the design and procurement of equipment, services, and facilities-in support of manufacturing.
1980-April 1, 1982 Babcock & Wilcox Company,. Nuclear Materials and Manufacturing Division, Commercial Nuclear Fuel Plant, Lynchburg, Virginia - Manager, Facilities Engineering.
Responsibilities' included management of Facilities Engineering and administration of Capital Projects, membership on Safety Review Board.
~
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' B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT USNRC LICENSE SNM-1168, DOCKET 70-1201 ORGANIZATION AND PERSONNEL CHAPTER 11.0 PART II NAME:
Charles W. Speight
. EXPERIENCE:
April, 1982 to May 1985 Babcock & Wilcox Company, Nuclear Power Generation Division, Commercial Nuclear Fuel Plant, Lynchburg, Virginia - Manager, Facilities Control.
Responsibilities included management and planning for health physics, safety, security, and facilities engineering, and administration of Capital Projects, membership on Safety Review Board.
May 1985 -
Present B&W Fuel Company (Babcock & Wilcox Co.),
Lynchburg, Virginia - Manager, Facilities and Services.
Responsibilities include management of' Facilities Engineering and miscellaneous services, administration of Capital Projects, membership on-Safety Review Board.
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D&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT-
'USNRC-LICENSE SNM-1168, DOCKET 70-1201 ORGANIZATION AND PERSONNEL CHAPTER 11.0 PART II NAME:
Richard W. Penoza TITLE:
Manager, Field Operations CITIZEN OF UNITED STATES EDUCATION:
B.S. - Mechanical Engineering, Lawrence Institute of Technology M.A.
- Industrial Management, Lynchburg College EXPERIENCE:
1971-1973 DACAM Corporation - Assistant Chief Engineer.
Responsible for the design and development of new packaging equipment, production follow, and field service engineering.
1973-1979 Babcock & Wilcox Company, Naval Nuclear 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.
-1979-1981 Owen & Mayes - Project Engineer.
Responsible for the design and
~ installation of industrial process.
piping systems and production equipment.
1981-1983
. Babcock & Wilcox, Special Products &
In-Service Inspection.- Tooling Design 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-Service Inspection ~ - Plant Service Tooling Manager, Tooling Applications Manager.
Managed teams of 7 to 18 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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B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT USNRC LICENSE SNM-1168, DOCKET 70-1201 ORGANIZATION AND PERSONNEL CHAPTER 11.0 PART-II NAME:
Richard W.
Penoza EXPERIENCE:
1986 -
l Present B&W Fuel Company (Babcock & Wilcox Co.)
i
- Field Operations Manager.
Manages and directs all activities related to field operations on irradiated nuclear fuel.
Responsibilities include directing the design, fabrication, testing, and qualification of new field i
service tooling; overseeing the maintenance, reconditioning, L
I transportation, and documentation of the adequacy of existing tooling; I
providing for the training and certification of field service personnel; and interfacing with customer representatives at the reactor sites to assure satisfaction with the work.
l.
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B6W FUEL COMPANY, COKMERCIAL NUCLEAR FUEL PLANT USNRC LICENSE SNM-1168, DOCKET 70-1201 PART II CHAPTER 11.0 ORGANIZATION AND PERSONNEL NAME:
Francis M. Alcorn TITLE:
Manager, Nuclear Criticality Safety Engineering CITIZEN OF UNITED STATES EDUCATION:
B.
S. - Nuclear Engineering, North Carolina State University, 1957 L
M.B.A. - Master of Business Administration, Lynchburg College, 1974 - Graduate Study in Nuclear Engineering, University of Virginia EXPERIENCE:
1957 to -
1960 Babcock & Wilcox, Atomic Energy Division, Lynchburg, VA.
Functioned as a Nuclear Engineer doing both core neutron. physics and shielding calculations.
1960 to -
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 Technology, which was published by GNEC for-the AEC at that time.
1961 to -
]964
' Babcock'& Wilcox, Nuclear Power Generation Division, Lynchburg, VA.
Concerned with core neutron physics 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.
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B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT USNRC LICENSE SNM-ll68, DOCKET 70-1201 CHAPTER 11.0 ORGANIZATION AND PERSONNEL PART II NAME:
Francis M. Alcorn EXPERIENCE:
1964 to -
l 1969 Babcock & Wilcox, Utility Power Generation Division (formerly Nuclear Power Generation Division), Lynchburg, VA.
l Physicist in the PWR Development Section I
and was responsible for determining the most economical method for utilizing plutonium as a recycle fuel in B&W's pressurized water reactor concepts.
In addition, was Nuclear Criticality Safety Advisor to the Company's Navel Nuclear Fuel Division.
1969 to -
1971 Babcock & Wilcox Company, Lynchburg l
Research Center, Lynchburg, VA -
Criticality Specialist, Nuclear Safety Engineer.
Transferred to the LRC as Nuclear Criticality Safety Specialist for Babcock & Wilcox's Naval Nuclear Fuel l
l Plant, Commercial Nuclear Fuel Plant, and the LRC.
Appointed Nuclear Safety Officer for the LRC.
1971 to -
April 1987 l
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 audits, and gave assistance to the various divisions of the Company and the Company's customers in matters related to 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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B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT USNRC LICENSE SNM-ll68, DOCKET 70-1201
'PART II CHAPTER 11.0 ORGANIZATION AND PERSONNEL NAME:
Francis M. Alcorn EXPERIENCE:
April 1987-1 Present Manager, Nuclear Criticality Safety Engineering.
Responsible for managing the 1
Nuclear Criticality Safety Engineering Unit which develops and validates the analytical methods needed for criticality sa ety evaluations, performs criticality safety calculations needed within Babcock
& Wilcox, conducts nuclear safety audits, and assists 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 s.:
USNRC LICENSE SNM-1168, DOCKET 70-1201 CHAPTER 11.0 PART II ORGANIZATION AND PERSONNEL NAME:
J. Wayne Harwell TITLE:
Principal Engineer, Nuclear Criticality Safety CITIZEN OF UNITED STATES EDUCATION:
B.S. Nuclear Engineering, 1963 Mississippi State University M.S. Nuclear Engineering, 1968 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.
1964-1968 Mississippi State University -
Instructor & Graduate Assistant Engineering Graphics Department.
Graduate assistant and instructor teaching freshmen engineering drawing classes.
Attended graduate school in nuclear engineering.
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 physics models for the Farley PWR cores including generation of cross section tablesets and geometries for PDQ07 using EPRI ARMP code package.
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B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT
~USNRC LICENSE SNM-1168, DOCKET 70-1201 ORGANIZATION AND PERSONNEL CHAPTER 11.0 PART II NAME:
J. Wayne Harwell 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 PDQO7 computer code.
Work includes cross 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 development.
1988-Babcock & Wilcox Company - Principal Engineer Nuclear Criticality Safety Engineering.
Performs nuclear criticality safety evaluations using the SCALE computer code package that utilizes the Monte' Carlo computer codes (KENO-4 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 criticality calculations.
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B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT
+
USNRC LICENSE SNM-1168, DOCKET 70-1201 ORGANIZATION AND PERSONNEL i
CHAPTER 11.0 PART II
- l 11.4 Operating Procedures Written procedures for the conduct of specific operations 1
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 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.
t Applicable procedures are made available in the work area and adherence to procedure is required of all personnel.
11.5 Training All personnel receive basic training in radiological, industrial, and: nuclear safety upon being hired.
This initial 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:
' i 11.5.1 Initial Employee Training 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.
4 i
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- B&W PU"L COMPANY, COMMERCIAL NUCLEAR FUEL PLANT USNRC LICENSE SNM-1168, DOCKET 70-1201 PART II CHAPTER 11.0 ORGANIZATION AND PERSONNEL 11.5 Training i
11.5.1 Initial Employee Training Following the initial indoctrination, the employee receives additional safety training from his immediate supervisor regarding the nuclear and radiological safety requirements of his specific job assignment.
Training sessions are documented and l
filed as part of the employee's Health-Safety record.
11.5.2 Employee Retraininc I
continuing training of a general nature is provided as necessary by Health-Safety and supervision.
This l
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 Lincreased airborne activity, or changes in license i
specifications.
The responsibility for determining l
the necessity for retraining or special training
-rests with Health-Safety based-on plant conditions or the request of supervision.
i 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 Training
{
11.5.3.1 Respiratory Protection Training and retraining in the use of respiratory protection devices is provided l
by Health-Safety as required.
Points relating to proper use are-covered as the unit is issued and fitted by I
Health-Safety.
This approach provides continuing review of respiratory i
protection requirements.
Should i
situations arise where frequent use of a-respirator is necessary, frequent Health-Safety surveillance will assure continued proper application.
l
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e B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT USNRC LICENSE SNM-1168, DOCKET 70-1201 ORGANIZATION AND PERSONNEL CHAPTER 11.0 PART II I
11.5 Training 11.5.3.2 Emergenc(_ Teams Training 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 eqe\\ valent.
Efforto are made to recruit indi.lduals who have had previous training such as military damage control or Civil Defense radiation monitoring.
11.6 Changes in Procedures, Facilities, and Equipment 11.6.1 Procedural Changes 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 Equipment Changes Changes or modifications to facilities and equipment that have a potential impact on nucienr, PAGE:
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B&J FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT
=USNRC LICENSE SNM-1168, DOCKET 70-1201 PART II CHAPTER 11.0 ORGANIZATION AND PERSONNEL 11.6 Changes in Procedures, Facilities, and Equipment 11.6.2 Facilities and Equipment Changes _
radiological, industrial, or chemical safety must be 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 Initiating Changes 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 Changes The Safety Review Board Chairman determines what safety evaluations are needed.
If the proposed modification changes the basis on which the nucicar criticality safety was originally 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.
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B&W FUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT USNRC LICENSE SNM-1168, DOCKET 70-1201 ORGANIZATION AND PERSONNEL CHAPTER 11.0 PART II l~
11.6 Changes in Procedures, Facilities, and Equipment 11.6.2.3 Management 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 Approval and Verification of Changes Approval and release of plant modifications for routine use is dependent upon satisfactory completion of a pre-operational evaluation.
This evaluation is a final verification that the proposed change has been installed r
consistent with the analyses.porformed 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 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 exposures, nuclear safety, chemical and industrial hazards.
11.6.2.5 Records All analyses, evaluations, pre-operational i
evaluations and other pertinent documentation relating to plant modifications will be maintained on file for at least six months after termination i
of the operation.
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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 II t
FIGURE 11.1 B&W FUEL COMPANY COMMERCIAL NUCLEAR FUEL PLANT R.
A.
Alto Commercial Nuclear Fuel Plant Manager K.
S.
Lester b
D.
V. Ferree Manager, Safety & Lic.
Manager, Fuel Operations B.
W.
Pugh l
Mgr, Prod & Matris Contel C.
G.
Dideon G
R.
W.
Penoza Mgr, Manufacturing Eng.
Manager, Field Dperations b
V.
D. Holaday C.
W.
Speight Manager, Speciality Mfg.
Mgr, Facilities & Sec.
{
R.
T.
Long F.
F.
Domdy Manager, Information Serv Personnel D.
N.
Codrea W.
L.
Wright Manager, Purchasing O
O Manager, Accounting PAGE:
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et D&W PUEL COMPANY, COMMERCIAL NUCLEAR FUEL PLANT USNRC LICENSE SNM-1168, DOCKET 70-1201 NUCLEAR CRITICALITY SAFETY CHAPTER 14.0 PART II i
14.1 Administrative and Technica. Procedures The ultimate responsibility for nuclear criticality safety at the CNFP rests with the CNFP Plant Manager.
The Plant Manager has assigned thic responsibility to the Safety Review Board Chairman (Manager, safety and Licensing) who must approve all modifications or additions which involve hazardous as well as nuclear materials.
The Safety Review Board Chairman will determine if Board review is necessary.
l Written procedures approved by plant management shall be utilized for all operations involving SNM.
Nuclear safety postings approved by Health-Safety shall be maintained specifying nuclear safety parameters that are subject to procedural controls.
The training program conducted at the CNFP (Sections 2.5 and 11.5) provide additional assurance that the criticality safety requirements are adhered to.
Administrative controls for performing and approving criticality safety analyses are described in Section 4.1.
14.2 Preferred Approach to Design The double contingency principle as defined in the American National Standard ANSI /ANS-8.1 shall be followed in establishing nuclear criticality safety for all equipment, systems, and operations.
Where possible and practicable, reliance will be placed on equipment design in which dimensions (i.e.,
favorable geometry) are limited rather than on administrative controls.
Where structural integrity is necessary to provide assurance for safety, the design and construction of the equipment will be made with due regard to abnormal loads, accidents, and deteriorations.
14.3 Basic Assumptions The basic nuclear criticality. safety limitations discussed
[
in Chapters 4, 14, and 15 were originally developed assuming UO with a maximum U-235 enrichment of 4.0 wt.
2 percent and a pellet diameter of 0.4 inches.
Uranium pellets processed at the CNFP can however range in diameter from 0.3 to 0.6 inches, and may include UO2 p wder and pellet chips.
All data given is valid for the most reactive heterogeneous geometry appropriate to the situation being considered.
Also the U-235 enrichment may-approach 4.10 wt. % due to measurement uncertainties.
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-,.