ML20198G641
| ML20198G641 | |
| Person / Time | |
|---|---|
| Site: | 07000371 |
| Issue date: | 01/22/1986 |
| From: | UNC, INC. (FORMERLY UNC RESOURCES, INC.) |
| To: | |
| Shared Package | |
| ML20198G633 | List: |
| References | |
| NUDOCS 8605290717 | |
| Download: ML20198G641 (184) | |
Text
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UNC NAVAL PRODUCTS License SNM-368 Chapter 2 Page 2-1 Date: 1/22/86 Docket No.70-371 Rev.0
- 2. ORGANIZATION AND ADMINISTRATION 2.1 Orcanizational Resnonsibilities and Authority "We shall work in a safe manner at all times" is the Policy of UNC Resources. The President and General Manager of UNC Naval Products.
Division has implemented this statement to all employees by organization, communication, procedures, and training.
The President and General Manager of UNC Naval Products reports to the Executive Vice President of UNC Resources, Inc., and has overall responsibility for the safe operation of the Division facilities.
Responsibility for safety, medical services, nuclear materials, security, and data processing has been delegated to the Director of Technical Services. Responsibility for implementing the safety and medical programs has been delegated to the Manager, Nuclear and Industrial Safety. The Vice Presidents of Operations, Engineering,and Quality Control and the Manager, Nuclear Materials Control are responsible for enforcing and applying the rules and program conditions for nuclear criticality safety and radiological safety which have been established by the Manager, NIS.
O The organization of the Division provides for administration, production, technical support, and nuclear and industrial safety functions, security and nuclear materials management on a Division-wide basis. This is shown on the Division organization Chart, Figure 11.1.a.
Typical lines of responsibility leading to the President and General Manager of UNC Naval Products are shown in figure 2.1.
Key to any safety program is the supervisor in a line organization, or the project leaders and engineers in a technical staff organization. In the manufacture of nuclear reactor components,both groups are important to the safety related tasks of training personnel, process and equipment design and use, supervisory review and enforcement of requirements and procedures.
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Page 2-1 8605290717 060411 DR ADOCK 07000371 PDR
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TYPICAL GENERAL LINES OF SAFETY RESPONSIBILITY President / General Manager Establish Requirements Assure Personnel Compliance and Obtain Nuclear & Industrial Safety Approval'of New or changed Measure Compliance operations or equipment i
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Director Executive V.P.
Quality Control Director Technical Services Vice President Technical Serv.
Operations V.P.
Engrg. V.P.
I I
Manager, NIS Managers Managers Managers Manager, NMC i
i i
1
-Criticality Spec.
General Supv.
Project Ldrs.
Project Idrs.
Supervisor Supervl isors l
l or
- H. P. Spec.
Spec /Engrs Gen. Supvs Matl. Custodians l
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-Ind. Safety Spec.
Employee Technicians Supv/lEngrs.
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--Engineers /Techs.
Inspectors /
Techs.
Figure 2.1 Page 2-2 Date:1/22/86
'Rev.0 l
UNC NAVAL PRODUCTS
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License SNM-368 Chapter 2 Page 2-3 Date: 1/22/86 j
Docket No.70-371 Rev.0 1
2.1.1 Divisional Positions - Functional Descrintion (as related to Nuclear Safety) 4 i
President and General Manaaer has overall responsibility for the safe j
operation of Division facilities.
Director, Technical Services has been delegated responsibility for j
nuclear criticality safety, radiological safety, medical services, environmental releases, nuclear materials, security,and data processing.-
i Manacer. Nuclear and Industrial Safety (NIS) provides nuclear criticality safety, health physics, environmental controls, industrial safety and fire prevention, and medical services for the l
Division. The Department's assigned responsibilities include:
i Establishment of Division nuclear and industrial safety policy and
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programs.
Preparation of, maintenance,and compliance with regulatory agency licenses.
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Instruction and training of all personnel in handling and movement of SNM, proper Health Physics and Industrial Hygiene procedures.
j on-site nuclear criticality safety and health physics control j
functions independent of, but parallel to the functions of operating personnel.
4 Technical support services, as related to nuclear criticality safety and health physics, for review of proposed additions to or modifications of process equipment.
Coordination of Emergency Services.
The department organization is shown on Figure 11.1.b.
c Nuclear criticality Safety Seecialist administers the nuclear i
criticality safety pro % ram in compliance.with Federal regulations, provides evaluations of Nuclear Criticality Safety, and provides regular audits including follow-up with responsible operating management. The Specialist reviews and independently checks the i
nuclear safety evaluations and calculations performed by the Nuclear Safety Engineer or other Nuclear Criticality Safety Specialists.
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5 UNC NAVAL PRODUCTS License SNM-368 Chapter 2 Page 2-4 Date: 1/22/86 Docket No.70-371 Rev. O Health Physics Seecialist administers the Health Physics and i
l environmental program in compliance with Federal and State regulations, provides evaluation of radiological safety, and performs i
regular audits including follow-up with responsible operating management.
4 Health Physics Technicians perform specified health physics and
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environmental programs: (e.g. air monitoring, smear survey, bicassay, air and liquid effluent checks, transportation package checks and i-special work permit. issues.).
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Nuclear Criticality Safety Encineer or Nuclear criticality Safety
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Suecialist is responsible for the day-to-day criticality control and j
verification that equipment, processes, and operations meet the safety I
criteria explicitly described in the license or an NIS' approved i
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internal document. He performs initial criticality safety evaluations, makes any necessary calculations,and proposes them to j
the Specialist for review. He assists in the training of employees j
and performs regular inspections including follow-up with responsible j
operating management.
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Manaaer. Nuclear Materials control administers the Nuclear Materials Management Control Program including maintenance of the NRC i
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Fundamental Nuclear Materials Control Plan,and accountability of all j
SNM at this facility. He has safety responsibility for these functions and assures personnel training, compliance with all safety i
j rules and practices, and obtaining NIS approval prior to introduction of new or modified methods.
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Executive Vice President manages the operations and Engineering Departments and Project Managers and has' safety responsibility for these functions.
Vice President. Ocarations manages manufacturing, facilities,
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j maintenance,and plant services. He has overall safety responsibility for these functions. Safety responsibilit Department managers, general supervisors,y is delegated to operations 4
i supervisors and employees
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for on-the-job training, assuring compliance with all safety rules and practices, and obtainin new or modified processes, g NIS approval prior to introduction of
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equipment or facilities.
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IJNC NAVAL PRODUCTS License SNM-368 Chapter 2 Page 2-5 Date: 1/22/86 Docket No.70-371 Rev. O Vice President. Eneineerine manages the Division's technical activities, including development of manufacturing processes, process surveillance and improvement, and provision of equipment, tooling and 4
inspection devices. He has overall safety responsibility for these functions. Safety responsibility is delegated to Engineering Department managers, project leaders, specialists, engineers,and technicians for training, assuring compliance with all safety rules and practices, and obtaining NIS approval prior to introduction of developnent programs and new or modified processes, equipment or tooling.
Vice President. Quality Control manages the Division's inspection and quality assurance activities, including the Metallurgical and Chemical Laboratories. He has overall safety responsibility for these functions. This safety responsibility is delegated to Quality Control Department managers, project leaders, general supervisors, supervisors, engineers, technicians and inspectors.
Complete material loading and loss control is maintained for SNM and nuclear absorbers at all manufacturing stages of nuclear reactor components by Quality Control.
O Manaaers. General Sucervisors. Proiect Leaders. Sueervisors and Enaineers (All departments, as appropriate to figure 2.1) provide the management links to the worker (e.g. machinist, welder, inspector, technician). These positions, particularly the supervisor, control personnel, machines, and working conditions on a daily full time basis. They train new or transferred employees, monitor their understanding, and assure their compliance with safety requirements.
Individual Emelovees are responsible for working in a safe way at all times and reporting to work physically fit and alert. Any real or potential safety concern is brought to the attention of their supervisors for resolution. Full compliance with all applicable safety and process regulations and procedures is required.
2.1.2 Shutdown of Unsafe Oeerations Any employee shall shutdown an operation which is abnormal and is deemed a threat to the health and safety cf any employee or the public. Any supervisor may shutdown an operation which he deems a threat to the health and safety of any employee or the public.
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4 UNC NAVAL PRODUCTS License SNM-368 Chapter 2 Page 2-6 Date: 1/22/86 l
Docket No.70-371 Rev. O i
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2.2 Personnel Qualifications The Nuclear and Industrial Safety Department Manager shall hold a degree in science or engineering, and have at least ten years experience in a responsible position in the nuclear industry, at least three years of which have been in an activity which would develop an understanding of nuclear criticality safety, health physics, and industrial safety and fire prevention problems.
Nuclear and Industrial Safety Department Criticality and Health Physics Specialists shall have a degree in science or engineering and at least three years experience in a responsible nuclear engineering 4
or health physics position,at least two years of which is professional experience in the area of their specialty.
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The Nuclear Criticality Safety Engineer shall have a degree in science or engineering with at least one years experience in performing nuclear criticality safety assessments and calculations.
Nuclear and Industrial Safety Department Consultants shall meet the same requirements as listed for the Specialists.
4 Health Physics Technicians progress from an entry level (grade 4 or 6), to grade 8 and to Genior H.P. Technician (Grade 10).The minimum qualifications for entry level is a high school diploma. The minimum of one years satisfactory performance in the entry level is necessary before promotion to Grade 8: with 3 years of satisfactory performance required to become Grade 10.
The Nuclear Materials Control Manager shall have a college degree or equivalent and at least three years experie'nce in the nuclear field and shall have demonstrated sufficient judgement and capability to manage the nuclear materials control function.
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UNC NAVAL PRODUCTS j
License SNM-368 Chapter 2 Page 2-7 Date: 1/22/86 Docket No.70-371 Rev. O i
The minimum qualifications of Vice Presidents, Managers,and Supervisors who are responsible for employees handling nuclear materials are:
a.
2 years of work ekperience at UNC Naval Products or another facility engaged in the handling of formula quantities of nuclear materials, b.
or specific approval by the President and General Manager, a Vice President or Department Manager, and the NIS Manager recognizing the competency and/or training given to an individual, and his/her demonstrated judgment and capability to manage or supervise the function.
2.3 Safety Review Ccmmittee Nuclear Safety and Health Review Committee (NSHRC)
The NSHRC considers new and revised facilities, equipment, and processes involving radioactive materials and assures appropriate safety, health,and environmental controls have been evaluated for
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items that are beyond the approval authority of individual NIS specialists. The criteria for review by the NSERC are:
- 1. Any change or addition requiring a license amendment.
- 2. Any new or modified core / reactor design unlike a previously approved design.
- 3. Any new or modified fuel process or new types of fuel processing equipment unlike previously approved processes or equipment. A new process is one which involves different feed materials whose safety has not been evaluated, may introduce a new element of safety, or may affect the physical or chemical properties of the radioactive bearing materials.
- 4. The relocation or decommissioning of a previously approved fuel processing area.
- 5. Radiological safety or control systems, except those system changes that do not reduce the margin of safety previously approved for the operation.
- 6. Situations where an average increase of more than 50% in current average surface contamination levels is projected by the radiological safety evaluation (increase may not cause levels to exceed regulatory or license action levels)
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Page 2-7
l UNC NAVAL PRODUCTS License SNM-368 Chapter 2 Page 2-8 Date: 1/22/86 Docket No.70-371 Rev. 0 l
- 7. Situations where an average increase of more than 25% in current airborne contamination levels are projected by the radiological safety evaluation (increase may not cause levels to exceed regulatory, or license action levels) j
- 8. Where an exhaust is required to meet airborne contamination levels
- 9. Conditions where uranium effluent levels are projected by the radiological safety evaluation to increase by more that 25% of the monthly plant average for the previous year.
- 10. Other changes not specifically covered in items 1-9, but which are judged by the Nuclear Criticality Safety or Health Physics Specialist te contain an element that should be reviewed by the NSHRC Permanent members of the NSERC are the Manager-NIS, Nuclear Criticality Safety Specialist, Health Physics 1
Specialist, Industrial Safety Specialist, and selected personnel with qualifications appropriate to evaluate the agenda items.
The special NSERC members are selected by and report to
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the Manager, Nuclear and Industrial Safety in their NSHRC capacity.
The annual ALARA report on radiological exposures and monitoring shall be reviewed and recommendations made to the President and General Manager for implementation.
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i UNC NAVAL PRODUCTS License SNM-368 Chapter 2 Page 2-9 Date: 1/22/86 Docket No.70-371 Rev.0 2.4 Accroval Authority For Personnel Selection All personnel in safety-related staff positions and the Safety Review Committee are approved by the President and General Manager of UNC Naval Products.See paragraph 2.2.7.b also.
The assignment of individuals to the NIS Department is approved by at least two (2) levels of management above the assigned positions.
2.5 Trainina 2.5.1 General Training programs concerning the safety aspects of handling source and special nuclear materials shall be established on a Division-wide basis. Indoctrination and training for new employees (persons on the employment roll less than 2 months) shall be provided. Reorientation for those already in the employ of UNC Naval Products shall be given at least every 2 years, except that employees working with' radioactive materials in readily dispersible form shall be trained at least annually in nuclear criticality safety and radiation protection. These portions of the training program shall be given or supervised by specialists in the field of safety involved.
2.5.2 Indoctrination and Training The indoctrination and training of new ecployees in the safety aspects of the fuel fabrication process shall be conducted by, or under the supervision of, specialists in th'a topic covered.
An indoctrination shall be given on the basic concepts of radiation, protective action and devices, atomic fission and chain reaction control methods in general. Specific methods used to control NPD operations are presented with emphasis on following the safety restrictions on mass, dimension, or concentration. Other topics shall include the radiation detection and alarm system, its sound, and action to be taken in such emergency; company safety regulations and action in event of fire, explosion,or other non-nuclear emergency.
Written examinations shall be given to monitor employee understanding. A record is kept of training received. The indoctrination shall be completed prior to access of new employees to licensed material or restricted areas.
Page 2-9 l
UNC NAVAL PRODUCTS License SNM-368 Chapter 2 Page 2-10 Date: 1/22/86 Docket No.70-371 Rev.0 Purther training of the new employee shall be continued by the supervisor, who is responsible for instruction in all aspects of the particular assignment. Health physics and nuclear criticality aspects are routinely included as a part of the regular department safety meetings. A minimum of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> indoctrination and training shall be given to each new employee. Documentation shall be provided to assure compliance 2.5.3 Re-Orientation NPD shall conduct mandatory refresher training in radiation protection, nuclear criticality safety, and emergency procedures at least every two years, except that employees working with radioactive materials in readily dispersible form shall be trained at least annually in nuclear criticality safety and radiation protection.
Documentation shall be provided to assure compliance. A written test shall be given to each individual to evaluate the effectiveness of the refresher training.
2.5.4 On-The-Job Trainina Instruction specific to the proper and safe performance of a job O
the' responsible supervisor. The supervisor shall assure himself that shall be given to new area personnel (i.e. new hires or transfers) by each employee who works under his cognizance shall be able to do all activities in compliance with applicable nuclear criticality limits, health physics requirements, industrial safety methods,and management i
approved manufacturing instructions / procedures.
Continuing review of each employee shall be made by the supervisor.
Additional training shall be given as deemed necessary.
Frequent area inspections by NIS personnel shall detect groups or individuals that may require additional explanation,and training. The added special training shall be documented.
2.5.5 Visitor /Tenoorarv Emolovee A program shall be established for providing an appropriate amount of instruction, as determined by the Nuclear and Industrial Safety Department, for a short term visitor or temporary employee.
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UNC NAVAL PRODUCTS
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License SNM-368 Chapter 2 Page 2-11 Date: 1/22/86 Docket No.70-371 Rev.0 2.6 ooeratine Procedures Activities involving materials under this license shall be performed in accordance with approved written procedures.
UNC's entire formal operational system is based on employee compliance with written, approved, and controlled manufacturing and inspection procedures. Our customer (Department of Energy) has very stringent requirements for written procedures and their use by operating personnel.In addition to the governing UNC procedures, internal audits, etc., on-site Government representatives (30-40) are constantly performing strict compliance overchecks for assurance of contract requirements concerning document preparation, review, approval, control and use. The routing instructions for each item manufactured require the operator or inspector to record the dccument revision in his possession when he performs the operation. The Process Information Control Centers assure use and control of documents in the facilities.
2.7 Inscections and Audits 2.7.1 General A continuing re-appraisal of the safety program shall be provided through a system of daily checks, regular inspections, and audits.
Violations are corrected on the spot with the concurrence of the cognizant Specialist and/or Manager of NIS and recorded. If corrective action requires additional time to complete, a record of the violaton shall be prepared and maintained until corrective action is complete. For daily checks, inspections and audits, all observed violations including corrective action initiated and/or completed shall be documented. A planned schedule of regular inspections and audits shall be established.ing the NIS Manager.
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UNC NAVAL PRODUCTS License SNM-368 Chapter 2 Page 2-12 Docket No.70-371 Rev.0 Date: 1/22/86 2.7.2 Daily Checks Daily checks and visits shall be made routinely by Health Physics Technicians who make general observations in addition to their radiation survey functions. A technician shall report observed problems to the area Supervisor, and the Supervisor shall take appropriate action as required. Violations shall require a written notice and correction.
2.7.3 Inspections Plant inspections of Health Physics and Criticality Control shall be performed by personnel meeting the respective qualifications identified in paragraph 2.2.
An inspection includes a review of recorded violations to determine the areas requiring more detailed observation. Generally, a specific area will be observed for a sufficient time to indicate that work activities are acceptable.
l Inspections shall be documented. These inspections shall be performed as follows:
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Function Bv Minimum Frecuency Health Physics NIS Professional Personnel 1/ month (a) (b)
Nuclear Criticality Safety NIS Professional Personnel 1/ month (a) (b) (c)
Operating Production, Process, or Quality Continuing with Procedures and Control Engineering NMC being Records Control annually including Nuclear Materials
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Control NOTE:
(a) All plant facilities shall be inspected within each year.
(b) Each operating shift should be inspected within each year.
(c) All process areas should be inspected during each 2 month period.
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UNC NAVAL PRODUCTS 1
License SNM-368 Part I Page 2-13 Docket No.70-371 Chapter 2 Rev.0 Date: 1/22/86 2.7.4 Audits An audit is a comprehensive review of the total protection or control aspects of the Criticality Control & Health Physics Program.
An audit shall be performed once a year by a specialist or higher level personnel from outside the Nuclear and Industrial Safety Department.
The methodology used and the areas of review shall be determined by the person (s) performing the audit. License requirements, 10 CFR 20, and appropriate NRC Regulatory Guides shall be used in establishing the areas of review. The professional qualifications of the personnel performing the audit shall be reviewed and approved by the Manager, Nuclear and Industrial Safety and the President, UNC Naval Products.
Written audit plans shall be used. The plans shall be reviewed and approved in a manner established by the President, UNC Naval Products.
A report shall be made to the President on the effectiveness of the i
program.
2.8 Incident Reeortina and Investication Division Operating Procedures provide for the reporting, investigation, and corrective actions associated with abnormal incidents at our facility. An abnormal incident covers damage to components, equipment or facilities, exposed fuel, contamination spread, fire, explosion, dropping items, collapse loss of l
components, and similar extraordinary occurrences,.
The Quality Control Vice President has administrative and reporting responsibility; Engineering is responsible for investigation and corrective action; Nuclear and Industrial Safety participates in review of safety related items; and other departments participate as related to the abnormal incident and future prevention. A report is written for each incident and retained for at least one year.
The Manager, Nuclear and Industrial Safety will report required incidents under NRC Regulatory Guide 10.1 for the subjects of nuclear and radiation safety. The Security Plan and Fundamental Nuclear Material Control Plan provide for reporting requirements in those subject areas.
The Radiological Contingency Plan describes emergency actions, I
recovery,and return to operation for significant events. Any shutdown associated with criticality safety or radiological safety shall be reviewed by the Nuclear and Industrial Safety Department Manager
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prior to resumption of operations.
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UNC NAVAL PRODUCTS License SNM-368 Chapter 2 Page 2-14 Date: 1/22/86 Docket No.70-371 Rev.0 2.9 Records Nuclear criticality and radiological safety analyses are retained for at least six months after the approved operations are discontinued.
Records of violations, abnormal incidents, inspections, instrument calibration, and employee. training and retraining are retained for at least 1 year. Audits and ALARA reports are retained for 2 years.
Records of personnel exposure and radiation surveys are retained as required by applicable NRC regulations.
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es UNC NAVAL PRODUCTS License SNM-368 Chapter 3 Page 3-1 Date:l/22/86 Docket No.70-371 Rev.0 CHAPTER 3 - Egdiation Protection 3.1 Suecial Administrative Recuirements 3.1.1 AIARA Procram UNC Naval Products shall make every reasonable effort to maintain radiation exposures and radioactive contamination in affluents as far below the limits specified in Part 20 of Title 10 CFR as practicable.
Methodologies, which have been developed for calculating the potential operational benefits of external and internal radiation dose reduction actions, shall be used when evaluating possible incremental reductions in radiation doses received by workers.
UNC Naval Products Management shall demonstrate commitment to a viable ALARA program by providing for good radiation protection planning and
. practice as well as establishing policies that maintain awareness against departures from good practice and that fester vigilance in searching out new and better ways to perform necessary work with less exposure to radiation.
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Methods and considerations for maintaining the ALARA program at this site are:
a.
Training, awareness sessions,and information distribution to all plant personnel; more detailed sessions with those personnel.
involved in jobs with potential higher radiation exposure. This is done by the Training Department, Supervisors, and the NIS Department.
b.
Periodic internal and external audits of operational efforts to maintain exposures ALARA.
c.
Management support of the Health Physics Group to enforce safe plant operation.
1 d.
Evaluation of plant equipment, facilities,and operation and maintenance procedures,and 'odification made or considered for j
m reduction of radiation exposure.
e.
Performance of sufficient surveillance programs and investigations to ensure that occupational exposures are as far below the specified limits as is reasonably achievable.
f.
Evaluation of health physics data by location, operation,and job j
and an awareness of trends and potential high exposure areas or operations. Investigation of unusual exposures with corrective
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action as appropriate.
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UNC NAVAL PRODUCTS License SNM-368 Chapter 3 Page 3-2 Date:1/22/86 Docket No.70-371 Rev.0 t
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Provision for. adequate equipment, supplies, and work area to I
conduct a vigilant and in-depth health physics radiation protection program.
An annual report will be made to the President, NPD by the NIS Manager. The report will address significant areas of concern, areas in'which exposures and releases might be lowered in accordance with ALARA,and recommendation for actions in consideration of all areas of the radiation safety program at NPD.
3.1.2 Radiation Work Permit Procedures A Special Work Permit system shall be used to guide contractor and UNC personnel in performing non-routine work. operations that could cause or threaten to cause personnel exposure to uranium contamination or radiation levels which are likely to exceed the limits specified in 10 CFR Part 20.
A special work permit shall be prepared for work not covered by an approved written procedure involving entry into a system containing radioactive material if a potential exists for release of a
contamination exceeding the limits of 10 CFR Part 20.
The special work permit will contain the following:
a.
Location of work.
j b.
Radiation safety control requirements.
j c.
Signature approval by a member of the Health Physics staff.
3.2 Technical Recuirements 3.2.1 Restricted Areas-Personnel Contamination Control General personnel access is controlled by Security personnel at the entrance to such areas. Only personnel approved by a specified.
management list may enter such areas.
Change rooms or change areas are used at the entrance for either clothing changes or the addition of shoe covers and lab 1
coats / coveralls to normal personnel clothing and shoes.
The boundary between an uncontaminated floor and a potentially contaminated floor is designated by a step off pad or floor markings.
Protective clothing or special clothing as specified by Health Physics shall be worn in restricted areas. Health Physics shall establish the contamination. levels for protective clothing that may be reused and for personnel release.
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UNC NAVAL PRODUCTS O
License SNM-368 Chapter 3 Page 3-3 Date:l/22/86 4
Docket No.70-371 Rev.0 The current levels are stated in Chapter 12.8. A washup facility and alpha survey or hand monitor shall be provided at the exit from the change room.
Before exiting the change room, all personnel shall be required to monitor their hands with an alpha monitor. If the meter indicates the presence of skin contamination, the individual shall wash and resurvey. An individual whose skin or personal clothing is found contaminated above background shall not be allowed to exit the area without prior approval of the radiation protection staff.
Special contamination control zones established temporarily or for quality control purposes, which have sink and shower facilities accessible, but not necessarily in the control zone, may be approved by Health Physics.
3.2.2 Ventilation 3.2.2.1 Local Exhaust only portions of Building B (Designated "B-South") handle exposed O-uranium, very small amounts of which can become airborne. Hoods, glove boxes, or local exhaust shall be provided as required to maintain airborne and surface contamination within acceptable limits.
Ventilation exhaust equipment shall be required for routine operations generating airborne concentrations in excess of 25% of MPC (See paragraph 3.2.2.2 below),with minimum air movement requirements as i
follows:
Fume Hood Face Velocity
- 50 linear ft.per min.
General Purpose Hood Face Velocity
-100 linear ft.per min.
Local Exhaust
-100 linear ft.per min.
Glove Boxes
-Slight negative pressure (Except inert atmosphere boxes)
Air flow shall be checked and recorded on at least a monthly basis or whenever equipment changes are made affecting air flow.
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UNC NAVAL PRODUCTS l
License SNM-368 Chapter 3 Page 3-4 Date:l/22/86 Docket No.70-371 Rev.0 3.2.2.2 Filters and Scrubbers Before it is exhausted from the building,the contaminated and potentially contaminated dry air from the controlled areas shall be filtered by high efficiency particulate filters with 199.95%
efficiency for 0.3 micron particles, or scrubbed.to assure that air concentrations do not normally exceed 25% of the 10 CFR 20 Appendix B i
Table 2 limit.
If air is recycled in a controlled area, an evaluation shall be.
performed to determine whether this air requires additional filtration to protect personnel.
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Recycled air shall not be used in areas if airborne radioactive material exists in concentrations which, averaged over the number of hours in any week during which individuals are in the area, exceed 25%
1 of the amounts specified in Appendix B, Table 1, Column 1 of 10 Part 20.
The minimum frequency for measuring airborne contamination of j
radioactivity in recycled air shall be at least weekly.
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Pressure drop across each filter bank shall be measured and recorded on a monthly basis. Filters shall be changed when the 6 P is 14 in.
of water. This change may be deferred over a short term in order to coordinate with production or maintenance schedules provided Health j
Physics personnel can monitor and verify that such deferral will not adversely impact the area local exhaust or air flow as defined in j
3.2.2.1, and airborne concentrations as defined in 10 CFR 20. The evaluation shall be recorded.
3.2.3 Work Area Air Sameline I
3.2.3.1 Airborne Concentrations Process and breathing zone air samples shall be taken in sufficient i
numbers and frequency to comply with internal Health Physics requirements as stated in 3.2.3.2. The limits and guidelines of 10 CFR 20.103 " Exposure of Individuals to Concentrations of Radioactive Material in Restricted Areas" shall be followed.
The room air in all areas where non-capsulated licensed material is processed or where the operation could result in worker exposure to radioactive material exceeding those concentrations specified in 10 CFR 20.103 shall be regularly sampled and analyzed for airborne concentration of radioactiviuy. The survey frequency for the continuous air sampling shall be in accordance with Section 3.2.6.2 where applicable The airborne concentration level in the work area will be evaluated.by l
the data measured from all operating sampler stations in each work area.
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UNC NAVAL PRODUCTS i
License SNM-368 Chapter 3 Page 3-5 Date:l/22/86 Docket No.70-371 Rev.0 If lapel samplers are used in determining the concentration level in workers' breathing zone air, the samplers shall be worn by all workers in the work station. Additionally, the samples must be counted for radioactivity on a daily basis.
j If fixed air sampling equipment is used to determine concentration in l
workers' breathing zones, the locations of the fixed air sampling heads shall be re-examined for their representativeness of workers exposure at least once every 12 months.
1 3.2.3.2 Action Levels Analyses of the air samples are made after natural activity has had sufficient time for decay, at least 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after sampling completion.
Action levels for the data acquired by each fixed air sampler 4
representing a work station are:
Result Action C
A. Weekly average exceeding 25%
(1) Investigate and report of 10 CFR 20, App.B, Table I corrective action levels.
taken B. Monthly average exceeding (1) Investigate and report 25% of 10 CFR 20, App.B, Table corrective action I levels.
taken.
l (2) Consider work restrict-ion or installation of engineering controls.
C. Quarterly average exceeding (1) Investigate and report 25% of 10 CFR 20, App.B, Table corrective action I levels.
taken.
(2) Impose work restriction, engineering controls, or respirator use in accordance with 10 CFR 20.103.
(3) Increase bioassay sample collection 4
frequency.
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UNC NAVAL PRODUCTS License SNM-368 Chapter 3 Page 3-6 Date:1/22/86 Docket No.70-371 Rev.0 Result Action D. Single result exceeding 10 (1) Investigate and report CFR 20, App.B, Table I corrective action taken, levels.
(2) If a daily operation, consider work restriction or installation of 1
engineering controls.
l E. Weekly average exceeding 10 (1) Investigate and report CFR 20, App.B, Tabl's I levels.
corrective action taken.
(2) Impose work restriction, engineering controls,or respirator use in accordance with 10 CFR 20.103.
(3) Increase bioassay sample collection frequency.
F. Monthly average exceeding 10 (1) Investigate and report CFR 20, App.B, Table I levels.
corrective action taken.
(2) Terminate operation until i
process or engineering changes are installed.
(3) Review bicassay sample collection frequency.
Temporary 100% MPC airborne levels may be accepted in controlled areas if. proper corrective action / evaluation is taken to reduce the probability of recurrence and provided that the requirements of 10 CFR 20.103 are not exceeded. Continuous air sampling shall be used to determine the average concentration of radioactive materials in each work area. If it is determined that monthly averages are less than 10%
i of the derived air concentration (DAC) and that the potential for airborne radioactive material is low, a confirming sample program of 8 working hours of continuous sampling at least once a month may be substituted for the continuous program.
i Page 3-6 n
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UNC NAVAL PRODUCTS License SNM-368 Chapter 3 Page 3-7 Date:1/22/86 Docket No.70-371 Rev. 0 3.2.4 Radioactivity Measurement Instruments 3.2.4.1 Nuclear Alarm System A criticality alarm system shall be provided for all areas in which j
i special nuclear material shall be handled, used or stored. The monitoring system shall meet the requirements of 10 CFR 70.24 paragraph (a) (1) or (a) (2) as appropriate, using gamma sensitive radiation detectors which shall energize clearly audible alarm signals if accidental criticality odeurs.
- a. Location of Radiation Detectors The Health Physics Specialist shall authorize the relocation, addition, or deletion of specific nuclear criticality monitors, provided that a written evaluation of the change is prepared, and is approved by the Manager, NIS to assure that the change is in accord with 10 CFR 70.24 (a) (1) or (a)(2) - Criticality Accident Requirements.
1
- b. Detection Criteria i
The location and spacing of detectors shall be chosen to consider the 4
effects of shielding by massive equipment or materials.-Low density 4
materials of construction such as wood framing, thin interior walls, plastic or metal corrugated panels, etc., can be disregarded in determining spacing. The transmission through a 4,6,8 or 12 inch hollow concrete block wall shall be assumed to be constant based on normal incidence since the absolute nominal thickness of the blocks remains approximately three inches.
- c. Calibration and Testina The audible horn system shall be tested' monthly by mechanically tripping the alarms. The horn and alarm system shall be tasted quarterly by activating the system with a radioactive source, replacing the mechanical test for that month.
Each monit'or and alarm shall be calibrated at least every six months and after each repair that would affect the accuracy of measuring.
I 3.2.4.2 Radiation Measurement Instruments A wide range of instrumentation is maintained by the Health Physics Section for surveying contamination and radiation levels and measuring radioactivity. Sufficient units shall be available to support all operations authorized at the Naval Products Division.
()
Typical survey equipment currently in use is tabulated in Table 3.2.4.2.
Page 3-7 l
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i Table 3.2.4.2 Radioactivity Measurement Instruments 1
Type af g
Isstrument-Purpose Range sensitivity Altre Setpelats Ca g g lea Callbretten cuantlty f requenc y Testtae (Informatten emirl Ratemeter ulth General 0-50 er/hr 1200 CPM per none Source G-al detector Survey aA/br (sposure 5eet-Anaval Sefere use 2
IberIIne 120;530 0-100 erIhr hctrar Chicago 2650 Actemeter utth Contemlaa.
0-500.000 40 eV none Source Alpha 5ctattilation llen CPM Count Quarterly sefore use 4
prote Ludium Survey Katemeter ulth Bete 0-500.000 40 te Pancake type probe Sama CPM nome Source C u t Seel-Annual tuJ1 an Survey Before Use 2
Alpha Mand Contamina-0-500.000 15eV at 75 degrees 400 CPM Source Count Quarter'ly Weekly 12 Neltor tion CPM Eberline Survey lea Chaatser I-ray 0-5000 mA/hr 12 heV-1,3 MeV home Source (berline A0-2 Surveys taposure Seal.Aamual Sefore Use 1
Eas flou y
Proporttonal Measuring 10 counts hone Source Count Weekly Dolly 2
Alpha /Seta Countees Tranehc neutrom Meter Survey Victoreen 4774 0-800.000 045 mAes/hr nreme
, Pulse Rate,
$ael-Annual Before use,
,,1 CPM (avthermal)
GaJore Type Ni
[mergency 0-1000 R/hr home Source Esposure 5ent-Annual sefere use 4
Range Survey Survey 25mRM tieter.* beri tae Criticastty tagineering 0-50 aA/hr 30 g,y gg gjg, source Esposure Guarterly Meathly 22 Foaltering b etterlag Syst em bchar Measure.
Ieat.[grp.
Ofrect Readlag feessuring 0-200 d 80 teV mone Drsteeters 0-200 t Source Esposure Yearly Yearly 10 i
Sete-Easma F11e huettertag Badge geta-Gasma.
Vendor Vendor Vender 10 See mone nextron file gadge Natterlag GA Controls 0A controls 04 Centrets As needed L andauer theresluminescent Nat tering to see home Vendor Vendor Veneer Dos teettes -Teledyne 04 Controls 04 Controls l
4A Controls As needed aChapter 3 Page 3-8 Date: 1/22/06 l
See. O j
"UNC NAVAL PRODUCTS License SNM-368 Chapter 3 Page 3-9 Date:1/22/86 Docket No.70-371 Rev. O 3.2.5 Radiation Execsures It is company policy to maintain and conduct programs for determining, validating,and controlling occupational exposures.
3.2.5.1 Controlline External Radiation Excosure
- a. The possession, use, and transfer of licensed radioactive material shall be conducted in such a manner that no individual in a restricted area shall receive a radiation dose in excess of the levels specified below:
i Permitted External Radiation Extosure Part of Body Ouarterly l
(a rem) i Whole Body, Head &
1,250 Trunk, Gonads Extremities-Hands, Feet, 18,750 Forearms Skin of whole Body 7,500
- b. Personnel exposures shall be maintained as far below the above levels as is reasonably achievable.
- c. Allowable Modifications of External Excesure Limits i
Exposure to whole body external radiation in excess of 1250 millirem, can be permitted only with specific approval of.the Manager, NIS on recommendation by the Health Physics Specialist, and then in accordance with 10 CFR 20.101(b).
- d. Action Levels Any exposure to more than 50% of the 10 CFR 20 limits shall require an investigation and evaluation by NIS personnel. The exposed individual shall be restricted from operating radiation producing equipment i
pending completion of the investigation and implementation of NIS requirements.
I
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UNC NAVAL PRODUCTS i
License SNM-368 Chapter 3 Page 3-10 Date:1/22/86 Docket No.70-371 Rev.0
- e. Tvees and Frecuency of Measurements Personnel Monitorina I
Personnel who are required to be monitored per 10 CFR 20.202 and personnel who are routinely operating radiation producing equipment shall be supplied with appropriate personnel monitoring equipment.
Frequency of film badge readout and analysis of personnel exposure i
reports for this group shall be monthly.
Gamma and X-ray Surveys of Facilities 1
]
All previous evaluations have verified that,under normal conditions of operation,there are no occupied areas of radiation greater than 25% of applicable 10 CFR Part 20 limits. However, routine surveillance shall continue to be carried out'in order to find and gain control of any abnormal or previously undetected areas of radiation. X-ray facilities j
shall be surveyed monthly and after any maintenance modifications j
which could compromise radiation shielding.
General gamma surveys shall be taken at regular intervals to insure that personnel shall not be exposed to radiation hazards. The O
frequency of such surveys shall be dependent on initial Health Physics scoping of operations with subsequent review. Minimum frequency shall be at least bi-annual.
]
3.2.5.2 Controllina Internal Radiation Exeosure i
Dese levels and corrective actions taken if levels are exceeded shall I
be as described in Section 3.2.3, Work-Area Air Sampling and Section 3.2.7, Bioassay Program.
I i
4 4
4 i
l Page 3-10
UNC NAVAL PRODUCTS License SNM-368 Chapter 3 Page 3-11 Date:1/22/86 Docket No.70-371 Rev.0 3.2.6 Surface Contamination operations involving the handling of exposed fuel are confined to one area of the facility referred to as B-South. Within this area, work is performed to maintain any loose contamination to the lowest, levels reasonably achievable.
3.2.6.1 Zonine The facility shall be zoned to define controlled areas, limited control areas,and clean areas based on the levels of loose contamination.
The term " Controlled Area" shall be applied to work surfaces (excluding equipment and machinery) and floors having the potential for being normally contaminated in the range of 100-500 dpm/100 cm2 or above for removable alpha radioactive material,and wherein special protection measures to control the spread of radioactive contamination shall be required for all personnel. Normal entry and exit to the controlled area is through change rooms. Protective clothing or special clothing, hand sinks, shower, and hand monitoring instruments shall be available for use.
)
The term " Limited Control Area" shall be applied to work surfaces (excluding equipment and machinery) having the potential for being contaminated in the range of 50-100 dpm/100 cm2 for removable alpha radioactive material and 150 to 15,000 c/m (Probe area) for fixed alpha radioactive material, but where floors can be maintained at 4
clean area levels. However, shoe covering and step-off pads may be required in some rooms to insure that even sporadic floor contamination is not tracked. Limited control areas may not be j
physically separated by change rooms nor have showers in the immediate area. Protectivo clothing, a hand washing facility and hand monitor i
shall be provided.
i The term " Clean Area" shall be an area having measurable contamination levels of less than 150 c/m (Probe area) for fixed alpha radioactive material and below 50 dpm/100 cm2 for removable alpha radioactive j
material. Higher levels shall require posting and appropriate controls and/or restrictions.
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Page 3-11 i
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i UNC NAVAL PRODUCTS License SNM-368 Chapter 3 Page 3-12 Date:1/22/86 Docket No.70-371 Rev.0 Permissible contamination levels shall be established by Health Physics and/or Quality Control and shall be evaluated by. Health Physics as necessary. Currently enforced levels are presented in Section 12.8.4. A plan layout identifying the defined controlled areas, limited control areas, clean areas of the facility and all the access points to the controlled areas is presented in Section 12.14.
3.2.6.2 Action Levels and Survey Frecuencies The following survey frequencies and action levels shall be maintained,for the program to control surface contamination:
l General surveys shall be taken at regular intervals to assure that personnel are not exposed to radiation hazards and in order to locate and control any radioactive contamination. The frequency of such surveys shall be dependent on initial Health Physics evaluation of operations with subsequent review. Minimum survey frequency shall be i
as described below for removable surface contamination.
i f
)
Action level (removable)
Minimum and action when the level 4
l ()
Plant Area Survey Frecuency is exceeded Sectioning Area Daily 5000 dpm /100cm2 End of DeCon Area Shift i
clean up Chemistry Lab -
Bi-weekly j 10,000 dpm /100 cm2 Immediate (Controlled Portions).
clean up i
and sample preparation rm.
Other controlled Weekly-500 dpm /100 cm2 End of areas and limited shift controlled areas, 1000 dpm/100 cm2 Immediate s
clean up i
I Lunch Area, Bldg.A Weekly 30 dpm/100 cm2 Immediate clean Areas
- clean up i
- Survey frequency for non B-South clean areas may be monthly.
i i
Page 3-12 I
UNd NAVAr PRODUCTS License SNM-368 Chapter 3 Page 3-13 Date:1/22/86 Docket No.70-371 Rev.0 4
3.2.7 Bioassav Procram The UNC HP bioassay program shall meet or exceed the recommended bioassay program as put forth in Reg Guide 3.11 except that in-vivo 2
counting shall be performed as described in 3.2.7.3.
Sampling frequency in the bioassay program will be increased according i
to the last quarterly average airborne uranium concentration as specified in Table 3 of Regulatory Guide 8.11 " Application of Bicassay l
for Uranium".
i 3.2.7.1 Urine Analysis The extent of the bicassay program performed shall be based on the uranium quantity, form, degree of contamination confinement, and air sampling test results.
j a.
Minimum Bicassav Frecuency (Urine)
^
All employees shall have urine bicassay samples taken at the start and termination of employment.
! ()
A representative sample of the workers in the work area composed of the most highly exposed or potentially exposed personnel shall l
be sampled monthly and others in the area shall be sampled on a routine schedule that is consistent with the degree and results 1
of past samples and at least as follows:
- Area Frecuency Limited Control Areas 6 months Controlled area or area 3 months i
where respirators are routinely or occasionally required
- Note: Areas are defined in Section 3.2.6.1 A sample shall be considered representative for the work j
area as follows:
Total Workers Reoresentative i
>100 10%
i 10-100 at least 10 i
<10 at least 5 l
Page 3-13 i
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"UNC' NAVAL PRODUCTS License SNM-368 Chapter 3 Page 3-14 Date:1/22/86 Docket No.70-371 Rev.0 b.
Action Levels:
Level Actions
~
50 d/m/litar Health Physics Evaluation 100 d/m/ liter Work restriction and Health Physics evaluation until 50 d/m/ liter 100 d/m/ liter constant continued work restrictions; for 3 sampling periods intense evaluation 4
Urine bio-assay samples shall be collected from the persons involved following any incident which may cause or threaten to cause an over-exposure. If such a urine analysis indicates the potential for 50% or more of the maximum permissible lung burden for non-transportable uranium, a reasonably. prompt in-vivo count shall be performed.
3.2.7.2 Fecal Analysis Fecal Analysis shall be used for evaluation studies of suspected local O
airborne exposures which result from or could result from an incident such as a fire, spill, equipment malfunction, high air sample, or other departure from normal operations.
Actions to be based upon diagnostic results include:
- a. selection of subsequent measurement techniques and frequencies
- b. imposition or removal of work restrictions
- c. referral to a physician
- d. the physician's decision to attempt acceleration of the nuclide elimination process f,
3.2.7.3 In-Vivo Countine I
In-vivo counting of employees as a method of assessing the internal deposition of enriched uranium shall be considered a part of the l
overall bio-assay program.
Employees potentially subject to occupational internal deposition of radioactive materials shall be in-vivo counted according to a
i pre-published schedules which shall be established by the Health i
Physics Section. The Health Physics Specialist shall coordinate the in-vivo counting program
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UNC NAVAL PRODUCTS
)
License SNM-368 Chapter 3 Page 3-15 Date:1/22/86 Docket No.70-371 Section Rev.0 J
In-vivo lung counting will be taken from workers in the area where routine Bioassay is required according to the criteria set below.
For routine in-vivo counting, a representative sample of each designated area work group shall be counted. The sample shall include at least 10% of the workers who have regular job assignments in an area. This representative group shall always include the most highly i
potentially exposed personnel. Any person with a measurement result greater than 25% of the maximum permissible dose commitment shall be-scheduled for counting at six month intervals until his result is less than 25%.
In addition, the following selection critieria shall be used:
i (1) Urine bio-assay review for 6 months prior to in-vivo count.
(2) Air sample review.
(3) Incident review.
(4) Special Work Permits review A
l (5) Review of personnel and job previously selected.
(6) Evaluation of supervisors comments; personnel work appraisal.
1 (7) Others as determined by the Health Physics Section.
Results obtained shall be used in accordance with Regulatory Guide 8.11 recommendations as a basis for restricting employees if necessary, to areas that are not expected to exceed 15% of the maximum permissible concentrations. prescribed in 10 CFR 20 Table 1.
Definitions:
Full Restriction - Restricted to work assignments such that the individual will not be knowingly exposed to uranium.
Partial Restriction - Restriction to work assignments or areas where the average uranium alpha airborne activity is not expected to be in excess of 15% of the acceptable derived air concentration.
Page 3-15 i C) i
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UNC NAVAL PRODUCTS License SNM-368 Chapter 3 Page 3-16 Date:1/22/86 Docket No.70-371 Rev.0 4
Criteria:
(1) Restriction is implemented immediately upon receipt of the formal in-vivo report. A confirming whole body count at a separate facility shall be made to verify the full restriction.
(2) If on the basis of a single count, the predicted 12 month dose is in excess of 70% of the annual maximum permissible exposure, a partial restriction shall be imposed.
(3) Restrictions shall be in force until subsequent in-vivo counts indicate the extrapolated exposure for 12 months prior to the date of the latest in-vivo count is less than the annual maximum permissible a
exposure.
In-vivo counting shall also be used in addition to urine and fecal sampling to evaluate accidental internal exposures. Employees known or suspected of having been subjected to concentrations exceeding 40 MPC hours shall be counted at the next scheduled session at the plant site 3.2.8 RESPIRATORY PROTECTION PROGRAM p
4 The conditions for use of respiratory protection equipment shall be v
pursuant to Paragraphs 3.2.8.1 or Paragraph 3.2.8.2 as follows:
3.2.8.1 Respiratory equipment may be issued in non-routine situations by the Health Physics Section in accordance with our ALARA commitments and as an adjunct to a Special Work Permit involving absolute filter changes, 4
sump clean-outs, or other anticipated maintenance operations in controlled areas, provided that:
a.
No allowance shall be made for particle size or the use of respiratory equipment in controlling the individual exposure to a quantity of radioactive material below that quantity which would result from inhalation for 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> per week for 13 weeks at uniform concentrations of radioactive material in air specified in 10 CFR 20 Appendix B, Table 1, Column 1 and 10 CFR 20.103.
4 Page 3-16
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UNCiNAVAIrPRODUCTS' License SNM-368 Chapter 3 Page 3-17 Date:l/22/86 Docket No.70-371 Rev.0 b.
Air sampling, other surveys,or HP evaluations shall be used to identify the hazard and to evaluate individual exposure.
'l c.
Increased surveillance, limitation of working times, and/or early information air monitors shall be used to maintain intake of radioactive material within any period of seven consecutive days below that which would result from inhalation of such material for 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> at the uniform concentration specified in 10 CFR 20 Appendix B, Table 1, Column 1.
s d.
Health Physics technicians' assure the adequate fitting of the 4
respirator, instruct the user in its use, and advise the user that he may leave the area at any time for relief from respirator use.
3.2.8.2 i;
When it is impracticable to apply process or other engineering controls to limit concentrations of radioactive material in air below 25 percent of the amounts specified in 10 CFR 20 Appendix B, Table 1 with concentrations averaged over the number of hours in any week O
during which individuals are in the area, other precautionary l
procedures, such as increased surveillance, limitation of working times, or provision of respiratory protective equipment, shall be used to maintain intake of radioactive material by any individual within any period of seven consecutive days as far below that intake of 1
radioactive material which could result from inhalation of such j
material for 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> at the uniform concentrations specified in 10 j
CFR 20 Appendix B, Table 1, Column 1 as is reasonably achievable, rr Respiratory protection required to limit the inhalation of airborne i
radioactive material pursuant to Paragraph 3.2.8.2 will be used dn accordance with Regulatory Guide 8.15 " Acceptable Program For
~
Respiratory Protection".
Page 3-17 I
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UNC NAVAL
- PRODUCTS I
License SNM-368 Chapter 5 Page 5-1 Date:l/22/86 Docket No. 70,371 Rev.0 CHAPTER 5 - ENVIRONMENTAL PROTECTION j
5.1 Radioactive Effluent Control Systems 5.1.1 Gaseous Effluents All stacks emitting radioactive particulates shall be continuously monitored for alpha activity at the point of l
release. As a minimum, the analysis frequency for alpha activity shall be weekly. Beta / gamma activity shall be monitored and analyzed when necessary. Emissions shall be kept as low as is reasonably achievable below the limits specified in 10 CFR 20.106, Radioactivity in Effluents To Unrestricted Areas.
Tabulations are maintained for the results found from these measurements in order to observe trends, establish the quantities of material lost to the outside atmosphere, and to 1
determine the status of air releases in relation to 10 CFR 20 1
i limits and ALARA.
A discharge concentration averaged over any 60 day material 3
balance period which exceeds 25% of the 10 CFR 20 limits will require investigation. Corrective action will be undertaken if i
the investigation indicates these levels may be exceeded as an annual average concentration or for obvious system failures.
1 Corrective action may include such action as equipment repair, i
equipment replacement, equipment cleaning, equipment modification and/or equipment addition..
5.1.2 Licuid Effluents Trace amounts of uranium are processed through the radwaste treatment system and released to the Sanitary System. This waste j
is controlled and sampled prior to discharge.
Releases shall be kept as low as reasonably achievable below the limits specified in 10 CFR 20.106, Radioactivity in Effluents to l
Unrestricted Areas for releases into the on-site sanitary septic system and as low as reasonably achievable below the limits i
specified in 10 CFR 20.303, Disposal by Release into Sanitary Sewerage Systems for releases into the municipal sewerage treatment plant.
Page 5-1 C:)
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License SNM-368 Chapter 5 Page 5-2 Date: 1/22/86 Doc.kat No.70-371 Rev.0 A control limit, applied to each approximately 2,000 gallon batch of rad-wasta prepared for release, shall be the appropriate 10 CFR 20 Appendix B value applied at the point of release from the treatment system.
If the rad-waste exceeds the control limit, supervision shall be notified batcre release to determine whether additional treatment erfcombination with other wastes can be authorized.
If the control limit must be exceeded, an investigation shall be t
conducted and corrective action initiated to avoid recurrence.
Such corrective action may include process modification, procedure modification, equipment modification and/or equipment addition.
Site surveillance shall be designated to establish the quantities and concentrations of effluents regulated by 10 CFR 20 after they have been released but prior to leaving the site bound 6 ries. The environmental acceptance of 10 CFR 20 effluents shall be evaluated on an annual basis against applicable State
)
andeFederal regulations.
5.2 EnvironmentaleMqnitorinc 5.2.1 SiteSurveil$ance a.
Air Locations surrounding the plant, ccordinated with meteorological
,i data, shall be sampled quarterly for approximately 24 continuous hours using,high volume air samplers. Filters shall be analyzed for gross alpha and beta / gamma activity.
b.
Water Surface water shall be analyzed quarterly at the following locations:
(1) Thames River-Upstream and downstream"from the plant (2). Trading Cove (3) Outfall of drainage trench (4) Incoming, city water Sam)les*fron"the four surface locations shall be analyzed for uranium >
k.
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Page 5-2
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UNC NAVAIt PRODUCTS License SNM-368 Chapter 5 Page 5-3 Date:l/22/86 Docket No.70-371 Rev.0 Ground water samples shall be obtained at least~ quarterly from wells surrounding the plant and shall be analyzed for uranium radioactivity. Trends shall be evaluated, to assure that the plant discharge water is not adversely affecting residential walls.
c.Meteorolecical Monitorine A wind measuring system for accurate data on the immediate micro wind conditions at the affluent release points shall be operated on site. Wind speed and direction shall be recorded.
- d. Terrestrial Soil samples shall be taken around the perimeter of the plant semi-annually. Three to six samples shall be taken at each sample period.
All samples shall be analyzed for radiometric uranium.
Should adverse trends be identified in comparing the results of
(-].
samples taken prior to and during the operation of this facility since the plant consolidation, an evaluation shall be made, reviewed with the NRC, and agreed action taken. Corrective action may include such action as increased frequency of sampling, additional sampling points, and additional effluent treatments.
I Page 5-3
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f)/
UNC NAVAL PRODUCTS w
License SUM-368 Chapter 7 Page 7-1 Date:1/22/86 Docket No.70-371 Rev.0 CHAPTER 7 - DECOMMISSIONING PLAN 7.1 General Provision for decommissioning will be made should UNC decide to terminate this license. The facilities and site shall be decontaminated so that release for unrestricted use may be made in compliance with Tabre 7.1.
We have had prior experience in decommissioning a similar, but more extensive facility in 1975-1976 with no unexpected problems.
7.2 Plan only a small portion of the plant facilities (approx. 10%) is operated with any contamination present that would require cleanup upon decommissioning. The contamination is alpha type from non-irradiated enriched uranium.
Present sampling of the sanitary field shows that the requirements of Table 7.1.B Option 1 are met. Reference letter W.F. Kirk to W.
T.
Crow dated October 29, 1985..
Plant areas requiring decontamination for radioactive material at the time of decommissioning of the plant shall be handled in accordance with the following plan.
1.
Establish contaminated equipment / utilities / facilities listing.
2.
Review listing for potential criticality / health physics hazards.
3.
Using experienced personnel / existing decon facilities,
- a. Decontaminate useable equipment.
- b. Decontaminate unuseable equipment-dispose.
4.
Disassemble / cut up ventilation system. Watch for any accumulation beyond a specific volume. Decon and/or ship for burial (NRC approved sites) if uneconomical to clean.
5.
Disassemble / cut up drain / rad. waste systems. Watch for any accumulation beyond a specific volume (collect sludge). Decen and/or ship for burial.
4 6.
Decon the buildings (walls, roofs) and/or tear down, cut up and dispose by burial.
7.
Decon and/or tear up floors, foundations, contaminated earth and ship for burial.
Page 7-1 i
Table 7.
A. ACCEPTABLE SURFACE At1D S0ll C0ffTAMitlATI0rl LEVELS NUCLIDE*
AVERACE HAXIHU)
REMOVABLE U
be 2
2 U nat, U-235, U-238, and 5,000 dpm a/100 cm 15,000 dpm a/100 cm 1,000 dpm a/100 cm cssociated decay products 2
2 2
Transurantes, Ra-226, Ra-228, 100 dpm/100 cm 300 dpm/100 cm 20 dpm/100 cm Th-280, Th-228, Pa-231, Ac-227, I-125, I-129 2
2 Th-nat, Th-232, Sr-90, 1,000 dpm/100 cm 3,000 dpm/100 cm 200 dpm/100.cm Ra-223, Ra-224, U-232, I-126, 1-131, I-133 2
2 2
Bata-Camma Emitters (nuclides 5,000 dpm Sy/100 cm 15,000 dpm Sy/100 cm 1,000 dpm Sy/100 cm with decay modes other than cipha emission or spontaneous fission) except Sr-90 and ethers nnted above.
- Where surface contaminatio,n by both alpha-and beta gamma emitting nuclides exists, the limits established for elpha and beta gamma-emitting nuclides should apply independently.
As used in this table, dpm (disintegrations per minute) means the rate of emission by radioInctive material as datermined by correcting the counts per minute observed by an appropriate detector for background, efficiency, and geometric factors associated with the instrumentation.
"Maasurements of average contaninant sh'ould not be averaged over more than I square meter. For objects of less b
eurface area, the average should be derived for each such object.
d 2
The maximum contamination Icvel applies to an area of not more than 100 cm.
'O
- The amount of removable radioactive material per 100 en of surface area chould be determined by wiping that area with dry filter or soft absorbent paper, applying moderate pressure, and assessing the amount of radioactive a
caterial on the wipe with an appropriate instrument of known efficiency. When removable contamination on objects ef less surface area is determined, the* pertinent levels should be reduced proportionally and the entire surf ace chould be wiped.
The average and maximum radiation Icvels associated with surface contamination resulting from beta gamma emitters chould not exceed 0.2 mrad /hr at I cm and 1.0 mend /hr at I cm, respectively, measured through not more than 7 S
milligrams per square centineter of total absorber.
FROM:
Regulatory Guide 1.86.." Termination of. Operstging License for Nuclear Reactors", Revision 0, July, 1982.
O O
O
UNC NAVAL PRODUCTS License SNM-368 Chapter 7 Page 7-3 Date:l/22/86 Docket No.70-371 Rev.0 i
TABLE 7.1 S.
SUMMARY
OF SOIL DISPOSAL OPTIONS I
1.
Disposal of acceptably low concentrations (which meet EPA cleanup standards) of natural uranium, depleted or enriched uranium, and uranium ores with no restriction on burial method.
The concentrations specified for this option are acceptably low withoGt restricting the method of burial. It is expected, however, that currently licensed operations will be conducted in such a manner as to minimize the possibility of soil contamination and when or if such occurs the contamination will-be reduced to levels as low as reasonably achievable.
2.
Disposal of certain low concentrations of natural uranium and depleted or enriched uranium (with no daughters present) when buried under prescribed conditions with no land use restrictions and no continuing NRC licensing of the material.
1 Under this option, burial will be permitted only if it can be
()
demonstrated that the buried materials will be stabilized in l
place and not be transported away from the site. Acceptability of the site for disposal will depend on topographical, geological, hydrological and meteorological characteristics of the site. At a minimum, burial depth will be at'least four feet below the j
surface.
Discosal Ootions (pCi/gm)
Kind of Material la Ib Natural Uranium (U-238 + U-234) 10 with daughters present and in equilibrium i
Ocpleted Uranium Soluble 35 100 Insoluble 35 300 i
Enriched Uranium i
Soluble 30 100 Insoluble 30 250 a
Based on EPA cleanup standards.
(
b Concentrations based on limiting individual doses to 170 mrem /yr.
I Page 7-3
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'UNC NAVAL PRODUCTS
~
License SNM-368 Chapter 7 Page 7-4 Date:l/22/86 Docket No.70-371 Rev.0 8.
During above operations, contain/ sample any runoff (rain, snow, water, etc.) or gaseous effluent as necessary.
9.
Decon equipment, tools, clothing, etc. and disassemble decon area. Collect sludge, dust, etc.
10.
Sample remaining ea.rth, water (ponds, wells, pipes, etc.) waste disposal systems going off site. Statistically evaluate to requirement. Prepare report.
11.
Review with Federal, State, local agencies as required.
7.3 Cost Estimate UNC has experience in decommissioning and decontamination for unrestricted use of a similar facility. Its former core manufacturing shops in New Haven, Connecticut, were decontaminated in 1975-1976 and released for unrestricted use by the U.S. Nuclear Regulatory Commission on April 22, 1976.
O Based on this recent actual experience, UNC estimates the cost, measured in current dollars, will not exceed $1,180,000.
The New Haven decontamination work included 9 truckloads of piping, obsolete equipment, concrete, earth'and ducting. In our estimate for the Montville program, we have provided for-18 truckloads, though we expect it to be less than 6 truckloads.
Cost Breakdown Jtem Cost 18 truckloads (including burial)
$720,000 Contractor 150,000 UNC Expenses 150,000 Contingency 160,000 Total. $1,180,000 No irradiated material is involved in the contamination, only natural uranium which has been enriched in the U-235 isotope.
This estimate is belle >ed to be conservative because of the following factors:
AV Page 7-4
f]
UNC NAVAL PRODUCTS
%.)
License SUM-368 Chapter 7 Page 7-5 Date:l/22/86 Decket No.70-371 Rev.0 1.
UNC's decontamination experience.
2.
The fact that the New-Haven operation had included processes no longer used and which created more severe contamination in the floor areas.
3.
The fact that the Montville Plant was designed for its purpose initially, with design features intended to minimize spread of contamination and facilitate cleanup on both a routine basis and at final decommissioning. The New Haven buildings pre-existed and were adapted to nuclear material nsnufacture.
The New Haven decontamination was performed by UNC employees under UNC supervision.
7.4 Financial Assurances UNC considers that its depreciation policy, initiated in 1972 at time of its decision to consolidate Division operations in Montville, provides full security for cost of decommissioning.
Depreciation for the facility is on an accelerated basis, with the p),
main buildings to be depreciated to a 20% residual value in 20 years
(_
under the terms of UNC's supplemental agreement with the Department of Energy of April 6, 1972. At the expiration of the 20 year period, straight line depreciation will be charged until the book value is reduced to zero.
The facility is of modern, one-story construction with excellent rail and highway access. Replacement cost for the Montville buildings at March 31, 1978 was $25,314,000 and net book value was $5,809,000. UNC considers that the excess of replacement cost over book value provides an ample surety for the $1,180,000 decommissioning cost, and that the accelerated depreciation method, with book value to be reduced to zero, will provide continuing assurance of assets well in excess of the small decommissioning cost.
Page 7-5
UNC NAVAL PRODUCTS License SNM-368 Chapter 8 Page 8-1 Date:1/22/86 Docket No.70-371 Rev.0 CHAPTER 8 RADIOLOGICAL CONTINGENCY PLAN 8.0 UNC shall implement, maintain, and execute the Radiological Contingency Plan, except for all classified subsections (1.2.2.1, 1.2.2.2, 1.2.2.5, 1.3, 2.1.1.1, and 2.1.1.2) transmitted by letter dated November 12, 1981. UNC shall prepara and maintain implementing procedures for the Radiological Contingency Plan. In addition, UNC shall make no change in the Plan, without the approval of the Commission, if the char.ge would decrease the effectiveness of the Plan.
UNC may make changes to the Plan provided the changes do not decrease the effectiveness of the Plan. UNC shall maintain a record of such changes for a period of 2 years. In addition, UNC shall provide a description of the change to the Director, Division of Fuel Cycle and Material Safety, U. S. Nuclear Regulatory Commission, Washington, D.C., 20555 with a copy to the Administrator, Nuclear Regulatory Commission, Region I, 631 Park Avenue, King of Prussia, Pennsylvania 19406.
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Page 8-1 i
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i UNC NAVAL PRODUCTS i
License SNM-368 Chapter 11 Page 11-1 Date:1/22/86 Docket No.70-371 Rev.0 CHAPTER 11 - ORGANIZATION AND PERSONNEL 11.1 Orcanizvtional Resconsibilities i
The managerial responsibilities and qualifications relative to the Nuclear Health and Safety aspects of the facilities are presented in Chapter 2 paragraph 2.1 and 2.2. Organizational charts are presented in figures 11.la and 11.lb.
11.2 Functions of Kev Personnel These functions, responsibilities and authorities are presented in Chapter 2, paragraph 2.1.1. Provision for succession to responsibility for operation of the plant under normal conditions l
(absences, incapacitation) is~provided for by direct delegation, and under emergency conditions by the emergency plan.
11.3 Education and Exterience of Kev Personnel Personal Summaries are attached in Appendix 11.3 for:
I President / General Manager - Glenn O.
Amy Exec.Vice President / Deputy G.M.
- George H. Waugh Vice President - Operations - James J. Vickary Vice President - Engineering - Joseph Andress Vice President - Quality Control - Joseph Olson 1
l Director - Technical Services.- Robert J. Gregg Manager, Nuclear & Industrial Safety - William F. Kirk 1
i specialist, Nuclear Criticality Safety - Thomas Gutman Specialist, Health Physics ~- Donald R.
Luster j
Specialist, Industrial Safety / Hygiene - Elmer A. Barton Manager, Nuclear Materials - Thomas J. Collopy 11.4 Oeeratina Procedures 11.4.1 General i
\\
NPD Management requires supervision at all levels to assure i
themselves that all handling, processing, storing, or shipping of fissionable material shall be given prior review and approval by 1
the Nuclear and Industrial Safety Department, that suitable control' measures shall be prescribed, and that all pertinent regulations, controls'or procedures relative to nuclear criticality safety or radiological safety shall be followed by supervision and all operating personnel.
6 j
Page 11-1 i
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UNC NAVAL PRODUCTS 4
G 1 AN R
I I
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4 l MATERIALS f l QUALITY CONTR0LI kRVICES IFINANCFl EXECUTIVE CONTRACT
~
TECil VICE PRESIDENT ADMINISTRATION liff tMAN RES0tlRCFS l 1
NUCLEAR AND d PRO.lFCT MANAGEMENT l T MDf fSTRI Af SAFETY i OPFRATIONS I
i
~~"
NUCLEAR MATERIALS CONTROL l FNGINEERING I i
SFCllRITY I M DATA PROCESSING l
FIGURE 11.1.a UNC NAVAL PRODUCTS DEPARTMENT ORGANIZATION Page 11-2 Date: 1/22/86 Rev. 0 i
)
O O
O UNC NAVAL PRODUCTS PRESIDENT AND GFNFRAI MANAGER I
DIRECTOR TECHNICAL SERVICES i
MANAGER NUCLEAR AND INDUSTRIAL SAFETY I
l 4
NUCLEAR CRITICALITY liEALTil SAFFTY PifYSTCs INDUSTRIAL SAFETY l MEDICAlI ilVGIENE, AND FIRE PREVENTION l CONSULTANTS l
FIGURE 11.1.b NUCLEAR AND INDUSTRIAL SAFETY DEPARTMENT ORGANIZATION Page 11-3 Date: 1/22/86 Rev. O
i 1
UNC NAVAL PRODUCTS License SNM-368 Chapter 11 Page 11-4 Date:1/22/86 Docket No.70-371 Rev.0 i
Approval by the Nuclear and Industrial Safety Department shall be l
in accordance with criteria established by the license which includes a review by qualified individuals.
i The mechanism of such approval is described in more detail in the following sections.
Records of such approval shall be maintained for at least 6 months after cessation of such operation.
11.4.2 oeerational Instructions Specific written operational instructions, reviewed and approved by NIS, shall be set up to control the handling of special nuclear material. These instructions shall be followed from the receipt of incoming material through all manufacturing phases of the products, up to and including shipment. The documents will l
contain nuclear criticality limit instructions and will be at 4
work stations.
Approval of operational instructions is by the NIS Manager, or authorized NIS specialists or engineers and the area shop manager or their designees. The operational instructions used are as follows:
11.4.2.1 Routine Instruction 4
These instructions list the process steps which apply to the manufacture and inspection of all components. Each worker must have the routing instruction present prior to performing any work on fuel components. He is instructed to review the work routing instruction which includes or references the applicable criticality instructions, working drawings, fixtures or tooling numbers, Manufacturing Operating Procedures and Quality i
Instructions or other process documents. At the conclusion of the operation step, the worker signs and dates his performance of the work. Because of the high visibility of the routing instructions and required worker use, NIS criticality control instructions are carried by this instruction.
11.4.2.2 Criticality Control Postina i
Criticality Controls are posted in work and storage. areas. These I
criticality control signs shall specify applicable requirements.
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i UNC NAVAL PRODUCTS-i '
License SNM-368 Chapter 11' Page 11-5 Date:1/22/86 Docket No.70-371 Rev.0 j
11.4.3 Radiation Protection Instruction i
Written instructions for personnel radiation protection shall be j
prepared, consistent with the requirements of 10 CFR 20 and shall be approved, maintained and adhered to for operations involving the potential for personnel ~ radiation exposure. Detailed work procedures may be accepted by the H.P. staff.
i l
11.4.4 Work Details i
This information is supplied to the worker in the form of
{
Manufacturing operating Procedures,. Quality Instructions, Standard Procedures, working drawings,and tooling. These items are listed on the Routing Instructions together with the 1
j criticality instructions. Any work performed must meet the i
criticality instructions. NIS does not approve " work detail" documents.
i 11.4.5 Health Physics Task Instructions The documents provide basic instruction to H.P. personnel for various tasks performed under this license. These instructions j
shall be reviewed and approved by NIS Management.
I 11.4.6 Document Control and Availability Criticality Centrol Postings are directly issued by NIS to Shop / Area Supervision.
i Routing Instructions are issued by the Operations Department (Production Control) with each part that is manufactured.
Work Details are made available to plant operators and inspectors
{
via a document control center as presented in attached Division j
Operating Procedure (DCP) No. 24. in Appendix 11.4.6.
11.4.7 Emelovee comoliance i
}
Work place adherence to criticality requirements is obtained through the following program:
l-1.
Initial indoctrination as a new employee.
1 l
2.
On-the-job training with supervision.
4
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Page 11-5 1
- p UNC NAVAL PRODUCTS License SNM-368 Chapter 11 Page 11-6 Date:l/22/86 i
Docket No.70-371 Rev.0 3.
Use of routing instruction in conjunction with posting.
j 4.
Area Criticality Limit posting.
{
5.
Processing thru work stations generally one component or safe quantity (S.Q.) at a time,or use of safe geometry fixt,uring where multiple components are j
processed.
i i
6.
Storage or movement in safe geometry or safe quantity lots.
7.
Problems or violations are discussed and corrective action taken in:
- a. Monthly awareness meetings held by local supervision.
f
- b. Notices of violation to specific supervision.
7
- c. Periodic inspections by NIS personnel.
8.
Re-orientation training is performed every two j
years (1 year for H.P. Techs. and B-South personnel).
9.
Verbatim Compliance and Malpractice programs with i
respect to operating procedures are effective i
programs for assuring strict compliance with the criticality control program (associated with strict compliance to routing instructions). Initial orientation and annual retraining of all employees I
j is conducted.
a
- 10. Internal inspection and audits by NPD operating i
departments and resident customer representatives (DCAS,BETTIS,and KAPL) for compliance with operational instructions and postings.
11.5 Trainine The training program for new and old employees is presented in paragraph 11.5.1. New or transferred employee training is 4
documented on the Employee Training Record shown on the next page.
Reinstruction of employees when changes are made to nuclear j
material processes, radiation protection procedures, fire protection or emergency procedures is given by the employee's
}
Page 11-6
}
i I
EMPLOYEE TRAINING RECORD' EMPLOYEE NAME EMPLOYEE f DEPARTMENT f JOB TITLE SUPERVISOR (h
C HOURLY Q NON EXEMPT O EXEMPT O NEW EMPLOYEE Q REHIRE C TRANSFER ] SHIFT 1.
NEN HIRE ORIENTATION gg,m Q tatroduettaa to UNC a..oure..
O co=p.ar rottet...ad troe. dure.
O sea te.
O t= port.ac. or cuatter.ad a. cord.
O cu co.r m.t.tton. win.
O radu.trt.1 nater.ette.
2.
NEN HIRE ORIENTATION EM Ort.attour O tadu.tri 1 s.r.tr courtrrro As carcxen Ocritic.ittys.t.tr e., toy..
On Ith rhrate.
In.tructor On.auteturiastree...show n.e.
O ADP Security Procedures 3.
DEPARTMENTAL ORIENTATION arMARxs Ono rou vork ror (CRAIN Or COMMANM Onour. t uork
- 5. tag on tia.
- a. gut r.et.nd.ac.
cattias ta stek nr km gk.)
coMrttren As curcrrn O rt=. k..etas/ cat sttrs y,
itule sonstimes ousAlcokeds In4toducC40s to cowo4Atte, matelvt00me, sup.rvt.or locktA4 and caftttsia.
D t.
4.
PERSONAL CONDUCT urtazNct: we rotter Maau.1 Hm a a..oue.. raptcy..
Othea. cit.
a.t.ttoa. x.au.1 O c.. or suit tta so.ed.
sue.rvt.or cuid.
O sot teit tas O r r a.t na tt O co=9.ar/D part=.at aut...ad a.sut.etoa.
O ct.etettnary rroc. dure.
coxrterza As citerrn O s=oktas e., toy..
sup.rvi.or D t.
5.
JOB DUTIES urruNct s we rottey M aust Human a..oute.. raptoye.
O 3ob c..cripetoa a.t.ttaa n au i O r.rt.r=.ne. M
.ur..
su,.rvt.or. cuid.
Otroottoa.
O cea. rat /n=rtt tacr...
coxrtrrrn As execxro Oovertt=.~
t rhP oy..
sup rvt.or D t.
O.
()
- Th...
it.a.
hould b. coverad by tam.d tat. up.rvisor,
.th.r item. a.y b. d t.cu...d u tth OJT spea.or.
AtV!s!ON 2 7/85 TD002 l
Page 11-7
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6.
QUALITY RzrEREscE: Dtvtston op2 rec tna Procedurea O Rsta.12=xhte ae ass to produee uNe rottey Manuit QWork quattty/ quantity REMAJUts Overbattu= co ettance g
Os tsaa ture
.t. ir te. ace coMrtETED is enEcxED O Records integrity Emptoyee OMateractice supervisor Date 7.
SECURITY RE FE RENCE : security Guide cor superatston Octas tried meertet ta Depart = eat coMrtETED As cnEcxtD O toc.e toa or Depart =e== ctassir te, Document storage gaptay,
Orunction or security rocce sup erv isor Date 3.
NUCLEAR AND !NDUSTRIAL SAFETY
REFERENCE:
UNC Pottcy Manuat QCENERAL Human Resources Emptoyee Retations Manuat Osaratyshoes/gtasses
/
supervisors Guide Q Reporting emergencies COMP!.ETED As CHECxED O Ev.euattoa procedure.
E.ptoy.e supervisor Data CRITICALITY RE FERENCE: NIs Booktet O storaie require =ent.
Area Postings O Area controt it=te.
ComETED As cHEcxED O cart controt it=tt.
roptoree O work. tat toa ttates supervisor O Controt stena =aantas and tocat toa Date NEALTH AND 1AFETY INFORMATION RZFERENCEI Health and saf ety Intersation ON MATERIALS USED IN PLANT
"*""*I O taror, e.,toyee or sub.tances
.ed ta work area.
COMrLETED As Q{ECKZD O Protective ctothing Emptoyee O Ratated seriency procedures supervt.or a
Date 9,
MRS APPROVED MATERIAL PROGRAM RZFERENCE: Prohibited Matertate Manual O Parpose of program.
O Function of Materials Review soard.
O Approved material ta ork ar'a-ccMrtETED As catCxtD Emptoyee sup ervisor Date
- 10. INTRODUCTION TO MANUALS, DOCUMENTS AND RZ.'tA2Xs PROCEyr 3 USED BY THE DEPARTMENT C Manuate 0 4=certat nanditns tracedures Q Procedures COMPLETED As CHICxtD O ror=s E=ptoree O Dra tess superv tear O custa.or spec titeation.
Date tNTRODUCTION TO MANAGEMENT Department Manager Date staf f Manager Date
- These items shoutd be covered by tamediate supervisor, othat itene may be discussed with OJT sponsor.
RETURN TO TPAINING FOR INCLUS!0N IN EMPLOYEE REC 00.D EvistoN :
nos
_ _=
UNC NAVAL PRODUCTS
- ()
License SNM-368 Chapter 11 Page 11-8 Date:1/22/86 Docket No.70-371 Rev.0 supervisor / manager or by appropriate specialists in the area of change. Notification of changes occurs by Engineering Change j
Notice (ECN), Monthly Awareness Notices, General Notices,or other means. The extent of training is determined by the magnitude and
)
importance of the change.
11.5.1 Trainina Procram outline i
{
The following are typical examples of the training that is provided for all employees:
j CRITICALITY A.
Introduction B.
N.P.D. Product 3
I j
- 1. Fissioning (principles)
- 2. Reaction due to fissioning i
3.
Criticality (reactor and non-reactor) j
- 4. Control / Protection j
C.
Film " Safe Handling of Enriched Uranium" l ()
- 1. Discussion
- 2. Questions and Answers
]
D.
Control / Production
- 1. Injury
- 2. Damage
- 3. Shutdown i
- 4. Cost 1
5.
Publicity E.
Accidents I
F.
Nuclear Safety Controls G.
Responsibility H.
Review 1
I.
Questions and Answers I
I J.
Quiz Page 11-8
!(:)
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1 UNC NAVAL PRODUCTS
()
License SNM-368 Chapter 11 Page 11-9 Date:l/22/86 Docket No.70-371 Rev.0 MEALTH PHYSICS j
A.
Introduction i
- 1. Purpose
- 2. NIS Department i
- 3. Radiation and Industrial Hazards i
B.
Health Physics Definition
- 1. Explanation of radiation, atom & nuclear arrangement
- 2. Concept of stability
- 3. Types of radiation and units
- 4. Natural radioactivity background (slide
" Normal Radiation Gamma - X-Ray")
4{
- 5. Properties of radiation (slide " Types of Radiation")
C.
Radiation Protection and Control
]
- 1. External (slide " Effects of Distance on Radiation Exposure)
- 2. Internal
- 3. Contamination
- 4. Control Program
- 5. ALARA Goals j
D.
Criticality Control & Monitoring
- 1. Nuclear Alarm System 2.
Blood Test
- 3. Emergency Monitors
- 4. Indium Foil in Security Badge s
4 i
E.
- 1. Slide (" Methods of Controlling Radiation j
Hazards")
- 2. Questions and Answers F.
Quiz i
INDUSTRIAL SAFETY A.
Basic Talk on Safety
- 1. Safety is Everybody's Job
- 2. First Aid
- 3. Workmen's compensation Page 11-9 1
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t UNC NAVAL PRODUCTS 1 ()
License SNM-368 Chapter 11 Page 11-10 Date:1/22/86 Docket No.70-371 Rev.0 i
i
- 4. Eye Protection Program
- 5. Foot Protection Program i
- 6. Protective Clothing and Equipment i
]
- 7. Emergencies i
Handling of Emergencies t
l Emergency Phone Number (333)
- 8. Nuclear Alarm Procedure to be followed in event of i
Nuclear Alarm i
- 9. Safey and Health Information on Materials i
Used in-plant
- 10. Safe Work Reminder Booklet k
- 11. Safety / Hygiene Policies / Procedures 11.6 Chances in Procedures, Facilities and Eauinment I
{
NIS review and approval of changes is controlled through many procedures at UNC. Typical procedures are attached as Appendix 11.6.
Policy Statement 13.02 - Nuclear Criticality' Safety Control I
System Operations Department Procedure CDP 300.21 Criticality Control Supervisor's Guide section VII, Policy #1 Criticality Safety i
Safety analysis, review, approval,and verification of j
implementation is documented as shown by Exhibit #1 to the above noted Supervisor's Guide Section VII, Policy #1.
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j Page 11-10 i
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License SNM-368 Chapter 11 Date: 1/22/86 i
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i APPENDIX 11.3 i.
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we--,w,-,em-e m -+- w ww,ew,-,,,,,w -m.
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4 1
1 GLENN O.
ANY j
OC PRESIDENT and GENERAL MANAGER i
f l
ABSTRACT:
[
Ten years of overall responsibility for financial and 4
l operational management of various business segments.
l Twenty-four years professional management and technical experience in nuclear reactor engineering and reactor plant I
operations, including two years in the manufacture of j
nuclear fuel products for the Atomic Energy Commission.
i EXPERIENCE:
1982 - Present President and General Manaaer Responsible for the management of over i
1300 professional and hourly employees j
with annual sales of $130 million.
Directly accountable to the Company's C.E.O.
for financial and operational results of the Division.
1 1980 - 1982 Executive Vice President Responsibility for Operations.
Engineering and Projects Management.
?
4 1978 - 1980 UNC Nuclear Industries I
President and General Manacer i
I Accountable for planning, organizing.
3 directing and coordinating the line and staff components of the Operations l
Division toward achievement of annual and long-range Department of Energy
{
contract and parent United Nuclear Corporation business objectives.
]-
t 1977 - 1978 Denuty for Onorations Act for and in support of the j
President. United Nuclear Industries, j
Inc., in providing leadership.
assistance, advice, recommendations and development of the overall direction sad achievement of objectives in the i
operational aspects of the Prime
.i Contract.
1 i
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i
O GLENN O.
ANY (cont'd.)
n EXPERIENCE:
(cont'd.)
1974 - 1977 General Atomic Company Manaaer. HTGR Fuel Manufacturina Manufacture HTGR fuel, capsule fuel and fuel ordered by other customers to specified engineering and quality requirements.
Direct control and movement of fuel in the manufacturing facility and maintain industrial and nuclear safeguards.
Administer scrap recycle and waste disposal programs.
1970 - 1974 Gulf United Nuclear Fuel Corocration Plant Manaaer. Chemical Operations Provided senior management of the overall activities and operations of the plant in the manufacture of uranium a
products and in the fabrication and assembly of light water reactor fuels and uranium-aluminum test reactor fuels.
1967 - 1970 Doualas United Nuclear. Inc.
Manacer. Manufacturina Encineerina Provide engineering and programmatic support to the Hanford reactors to maintain continuity of reactor operations, to ensure reactor life, and to improve product cost.
Manaaer. Fuels Manufacturina Manufacture fuel and target elements and special nuclear products for reactor use.
Procure necessary components and special materials to sustain fuels production and supply all reactor requirements.
Operate the Hanford Test Reactor.
Manaaer. Shon Operations Manufacture fuel and target elements in compliance with accepted quality and process specifications to be irradiated to the company operated single pass reactors.
O il
= --
I GLENN O.
AMY (cont'd.)
nc EXPERIENCE:
(cont'd.)
I 1949 - 1967 General Electric ConDaDY l
Various Engineering. Supervisory and Management positions associated with I,
the operation of N Reactor and related i
manufacturing facilities.
Achieved the position of Acting Manager. N Reactor Plant, responsible for the operation j
and maintenance of N Reactor and the facilities to produce the nuclear j
products.
1 I
EDUCATION:
BS Mechanical Engineering. University i
of Denver.
4 i
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C:)
i GEORGE H. WAUGH UrtC EXECUTIVE VICE PRESIDENT and DEPUTY GENERAL MANAGER ABSTRACT:
Extensive experience in the product design, engineering, manufacture and quality control of Naval Reactor components.
1 EXPERIENCE:
1982 - Present Executive Vice President and l
Deputy General Manacer Responsibility for Operations,
~
Engineering and Projects Management.
3 1979 - 1982 Vice President. Quality Control Line management of the Quality Control Department used to inspect and certify precision high tolerance components for the Naval Reactor Program.
Responsibility for assuring the Quality O
control System satisfies the requirements of MIL-Q-9858A.
i 1975 - 1979 Encineerina Manacer i
Responsible for management of the Engineering effort associated with the development and production of nuclear Cores.
1957 - 1975 Production. Enoineerina Assianments Previous positions' included Quality Control Engineering Manager, Project Manager and Production Superintendent, which resulted in experience in all phases of manufacturing from process development through production and i
inspection from both a line and staff perspective.
EDUCATION:
o BS, Chemical Engineering Massachusetts Institute of Technology 4
j o MS, Management i
Rensselaer Polytechnic Institute o Graduate of Bettis Reactor Engineering School - Bettis Laboratory l
PROFESSIONAL AFFILIATIONS:
Registered Professional Engineer i
l l
UAC JAMES J.
VICKARY VICE PRESIDENT, OP.ERATIONS s
ABSTRACT:
Twenty-seven years of diversified experience in the nuclear industry including production control and planning.
production. data processing and project management.
l EXPERIENCE:
1 1984 - Present Vice President. Operatione Manage the activities of Production Control. Production. Maintenance and Facilities Engineering to produce nuclear components on schedule and with effective utilization of resources.
1979 - 1984 Senior Proiect Manacer/ Data Processinc Manacer CE)
Managed all aspects of a contract from award to delivery to effectively relay details to and from the customer to the production floor.
Managed the Data Processing and Quality Control /
Engineering Mini-computer Systems.
1976 - 1979 Soecial Proiects Manacer i
Various manufacturing assignments under
- the General Manager's direction.
t 1973 - 1976 Plannino and Control Manacer i
Managed the Division's Planning Ind Inventory / Production Control Departments coordinating all aspects of Shop operation for a timely delivery.
1958 -1973 Various management and supervisory Positions for component manufacture.
assembly fabrication and project manager resulting in experience in all phases of manufacturing and customer interface.
()
EDUCATION:
MBA, University of New Haven
O JOSEPH C.
ANDRESS UnC VICE PRESIDENT. ENGINEERING ABSTRACT:
Twenty-eight years at NPD including sixteen years at Staff level positions.
Extensive experience in Materials.
Project Management and Engineering.
EXPERIENCE:
1985 - Present Vice President. Encineerine Responsible for the Engineering activities of the Division.
There are i
approximately 250 Engineers in the Department.
i 1979 - 1984 Vice President. Materials Responsible for purchasing and procurement of all materials and
()
structural components for the Division.
Procurements represent approximately 40% of Division sales.
1969 - 1979 Proiect Manaaer Responsible for the delivery of three different types of designs.
Two of the designs were prototypes including the
.l prototype for the present production j
units at the Division.
Also responsible for the Production startup at UNC for this unit.
1964 - 1969 Encineerine Supervisor Reporting to the Engineering Manager, 1
responsible for all production engineering and several aspects of development engineering.
Involved with management of Engineers and Technicians.
1957 - 1964 Encineer i
Various engineering responsibilities including production and development i
engineering for all types of nuclear O
1 i
components.
't
- O JOSEPH C.
ANDRESS (cont'd.)
Uf1C EXPERIENCE:
(cont'd.)
i 1954 - 1957 United States Navy a
-j 1951 - 1954 American Smeltina and Refinina ConDany 1
{
Metallurgical engineer responsible for j
open hearth smelting and refining.
4 j
EDUCATION:
BS Metallurgical Engineering
)
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JOSEPH V.
OLSON VICE PRESIDENT. OUALITY CONTROL ABSTRACT:
Several years experience in the materials procurement and 1
t manufacture of Naval Reactor components.
Also experience I
in nuclear reactor engineering and reactor plant operations.
EXPERIENCE:
1985 Vice President. Quality Control Responsible for Quality Control both in house and at NPD's subvendors.
The Department has approx. 350 personnel:
200 hourly inspectors and 150 i
professionals engaged in laboratory analysis, quality engineering, quality a
assurance, statistical analysis and systems development.
1984 to 1985 UNC Nuclear Industries Vice President. Fuels Operations Responsible for engineering, j
manufacturing and administrative functions required to provide nuclear fuel in support of N Reactor production needs (300 employees).
I j
1981 to 1984 NATCO Executive vice President. ODerations Responsible for all design engineering and manufacturing (650 employees).
1979 - 1981 UNC Naval Products Manacer. ODerations Responsible for all manufacturing, planning, production control, maintenance and plant engineering (450 employees).
e
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i
.4 JOSEPH V.
OLSON (cont'd.)
4 EiEERJENCE:
(cont'd.)
N 1976 - 1979 Manaaer Materials Responsible for-all procurement.
Procurements exededed $35 M annual including nickel based alloys and other sophisticated raw materials, as well as subcontracting.a number of machined components.
1971 - 1976 Olson Encineerinc & Manufacturine Co.
Started'from the ground up in a metal fabricating job shop.
Business Progressed to 34 full time employees and substantial profitability prior to sale in 1976.
1968 - 1971 United Nuclear CorDoration i
Various supervisory positions including O'
Contract Administrator, Manufacturing l
j Engineering and Production Superintendent.
1967 - 1968 Douolas-United Nuclear Senior Encineery Operational Analysis I
Reviewed requireme#nts and generated long-term operating plans for the optimum dual purpose operation of NPR.
1960 - 1967 General Electric Company Varioussupervisorypositibusincluding Mechanical Supervisor, Reactor Operations Analyst. Reactor Processing Supervisor. and Reactor Specialist, w
RDUCATION:
~
BSME, North' Dakota State University O
s i--,
,A.
m e
,w,.,
.,p.,,y.w
l UOC ROBERT J.
GREGG DIRECTOR. TECHNICAL SERVICES ABSTRACT:
Twenty-seven years of diversified experience, including eighteen years in increasingly responsible managerial positions in the nuclear industry.
Extensive experience in Quality Control, Project Management, Nuclear Materials and Process Development Engineering.
EXPERIENCE:
1984 - Present Director. Technical Services Responsible for Data Processing.
Nuclear and Industrial Safety, Nuclear Safeguards and UNC's Recovery Systems in Rhode Island.
1982 - 1984 Vice President. Quality Control Responsible for management of Division Quality Control activities including Inspection, Quality Assurance, Quality Control Engineering and Vendor Quality Assurance.
1980 - 1982 UNC Recovery Systems - Plant Manaaer e
Responsible for management of overall plant operations during facility decontamination and decoumissioning operations.
1977 - 1980 Manacer. Quality Assurance Responsible for management of Nuclear Materials Control. Quality Assurance Engineering, Analytical Laboratory and Nuclear and Industrial Safety operations of a facility engaged in recovery of uranium from unirradiated scrap.
O 9
_-.7
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4 O
ROBERT J.
GREGG (cont'd.
EXPERIENCE:
1977 Naval Products: Proiect Manaaer Reporting to the Division President, responsible for management and coordination of diversified activities
~
directed at development of a sophisticated new computerized NDA System for evaluation of naval components.
1975 - 1977 Manacer. Ouality Control Inspection Management of a department of over 150 salaried and hourly-employees responsible for inspection of naval components.
1967 - 1975 Various management and supervisory positions, including Assistant Engineering Manager Project Manager.
O-Development Engineering Manager and Engineering Supervisor. involving management of professional and
-i Paraprofessional personnel in the performance of multi-million dollar engineering programs.
1958 - 1967 Encineer EDUCATION:
o MS, Engineering Science o BS, Engineering Administration o BS, Metallurgical Engineering PROFESSIONAL AFFILIATIONS:
American Society for Metals
(
O WILLIAM F.
KIRK MANAGER, NUCLEAR AND INDUSTRIAL SAFETY ABSTRACT:
~
Thirty years of responsible experience in the design, development and manufacture of nuclear reactors.
Ten years of which has been related to nuclear safety, environmental control and industrial safety.
EXPERIENCE:
1976 - Present Manager. Nuclear and Industrial Safety Responsible for functions of criticality safety, radiological control, industrial safety and hygiene, environmental compliance, medical services, hazardour materials control, licensing and permits and emergency planning.
1973 - 1976 Manacer, Proiects,(with affiliate Os company, Transfer Systems. Inc.)
Responsible for design, development, procurement and manufacture of specialized commercial nuclear reactor equipment for rapid reloading and improved fuel performance.
Co-inventor of several patents.
1971 - 1972 Business Planninc Manager Responsible for development of the business plan, products suitable for diversification, plans for division consolidation, setting and measuring division management by objective goals.
Special consulting and trouble-shooting tasks in technical, organizational, profitability and environmental areas.
Responsible for preparation and submittal of environmental, safety and security reports to AEC for Naval Products Plant consolidation to Montville.
O
WILLIAM F.
KIRK (cont'd.)
EXPERIENCE:
(cont'd.)
1968 - 1970 Proiset Manacer e
Responsible for progress on manufacture of over $100M of naval nuclear reactor cores.
Set master schedules for components, development program and manhours.
Resolved problems and was a member of the customer negotiation team.
1967
- 1968 Ouality Control Manaaer Directed all quality operations.
The
~
department has about 200 people of I
which 40 were at a professional level.
1965 - 1966 Encineerino Manacer Responsible for integrated functions i
of facilities, equipment, development O
and manufacturing, including core assembly.
Directed efforts of approx.
50 professional people.
Developed, designed and placed in successful operation, (1) a reactive metal facility, and (2) inert gas shielded process facility in which personnel operated in space suit type equipment.
~
j 1961 - 1964 Technical Manager i
Directed engineers in advanced process 1
and equipment development, training of personnel in new methods, customer liaison on new designs, trouble-shooting manufacturing and quality problems in existing production.
Responsible for all technical and process aspects of bid proposals and contract changes.
Successfully developed manufacturing methods for n69 reactor designs on schedule.
L Responsible for criticality require-ments and enforcement during transition from BAPL/KAPL to AEC Supervision.
s O
WILLIAM F.
KIRK (cont'd.)
EXPERIENCE:
(cont'd.)
1957 - 1961 Olin Mathieson Chemical Corp., Nuclear Fuels Division. New Haven, Connecticut Proiect Superintendent. Proiect Enoineer. Technical Specialist Progressively increasing technical and supervisory responsibility in the manufacturing development of. naval reactors.
Was assigned responsibility for clearing up manufacturing problems of a major program, the development and production of the first two units were completed with a "well done" manage-ment commendation.
1958 to 1971 University of New Haven (New Haven College), West Haven, Connecticut O
Adiunct Professor and Instructor (Part time)
Taught evenings in field of physical metallurgy to undergraduates and graduates of other subjects.
1955 - 1956 New York University, Research Division New York, NY Assistant Enoineerino Scientist Metals research concerned principally with the physical metallurgy and alloy development of titanium and titanium alloys.
Also, laboratory supervisor directing the efforts of 10 to 15 people in service functions to metallurgical researchers.
Co-inventor of several patented titanium alloys.
Organized the first NYU Vacuum Metallurgical Conference which was nationally and internationally attended and continued to be conducted
()
for a number of years.
O WILLIAM F.
KIRK (cont'd.)
EDUCATION:
New York University. Collece of Encineerinc, New York, NY 1951 - 1957 Bachelor of Mechanical Engineering (Magna cum laude)
Master of Metallurgical Engineering (with equivalent of special masters in nuclear engineering)
'All course work and qualifying exams for doctorate in metallurgy.
PROFESSIONAL AFFILIATIONS:
o American Society of Mechanical Engineers o American Society for Metals o
American Institute of Mining and Metallurgical Engineers-o Tau Beta Pi (National Honorary Engineering Fraternity)
G) o Pi Tau Sigma (National Honorary Mechanical Engineering Fraternity) 8 O
s
O THOMAS GUTMAN Uf1C NUCLEAR CRITICALITY SAFETY SPECIALIST ABSTRACT:
Twenty-five years experience in the field of nuclear regulatory compliance, involving licensing. radiological safety and nuclear criticality safety.
In addition, has served as Technical Researcher to a nuclear evaluation council which was appointed by the Governor of the State of Connecticut.
EXPERIENCE:
1977 - Present Criticality Specialist Execute all aspects of the Nuclear Criticality safety Program at UNC.
1976 - 1977 Technical Researcher. Connecticut Temporary Nuclear Power Evaluation Council, Middletown. Connecticut i
Provided technical staff research to the
()
Council which was established by the Connecticut State Legislature to recommend' legislation relating to the use of radioactive materials in Connecticut.
1970 - 1976 Combustion Engineering, Inc.
Windsor, Connecticut Nuclear Licensinc & Safety Supervisor 2
Supervised all aspects of radiological safety, special nuclear material licensing and criticality safety within the Fuel Fabrication Facility.
These responsibilities included the supervision of shift technicians to assure compliance with OSHA regulations.
1968 - 1970 Westinghouse Electric Corporation Penn Center. Wilkinsburg, PA Nuclear Desion Encineer Assisted in establishing the design parameters for repeat PWR cores and provided consultation to the Nuclear Fuels
()
Division on all questions concerning nuclear criticality safety and fuel shipping.
v 4
O THOMAS GUTMAN (cont'd.)
EXPERIENCE:
(cont'd.)
1967 - 1968 Westinghouse Electric Corporation Cheswick, PA Nuclear Safety Encineer Established safe operating limits which governed the design and spacing of fissile material handling equipment in new nuclear fuel processing facilities.
1963 - 1967 Nuclear Materials and Equipment Corp.
Apollo, PA Nuclear Safety Encineer Establ5shed operating nuclear safety limits for all fissionable materials.
Also l
designed, tested and evaluated shipping packages for special nuclear materials.
1960 - 1963 Atomic Energy Commission
()
Germantown, Maryland Technical Reviewer Reviewed applications for radiography isotope licenses.
EDUCATION:
1959 Rochester Institute of Technology, Rochester, New York, Bachelor of Science in Mechanical Engineering 1960 University of Arizona, Tucson, Arizona Graduate work in Nuclear Engineering 1961 Robert A. Taft Sanitary Engineering Center, Cincinnati, Ohio Radiological Health (10 week course)
, PUBLICATIONS AND PRESENTATIONS:
Published two technical papers in Nuclear Technolocy, a journal of the American Nuclear Society, chaired a session of a national ANS meeting, and participated as an invited speaker at several technical symposia.
O
O Uf1C DONALD R.
LUSTER SPECIALIST. RADIOLOGICAL AND ENVIRONMENTAL CONTROL ABSTRACT:
4 Twenty-three years of experience in the field of radiation protection and associated SNM and By-product licensing activities.
Includes extensive experience in laboratory management and application of health physics principles to a wide variety of facility and equipment engineering projects.
EXPERIENCE:
1973 to Present Specialist. Radiolocical and Environmental Control Responsibilities expanded to encompass Division licensing requirements, regulatory requirements and the Environmental Monitoring Program.
1970 - 1973 United Nuclear Corporation. Naval Products Division New Haven, Connecticut Health Physics Specialist Plan and implement the Divirion's Health Physics' Program.
1968 - 1970 United Aircraft Research Laboratories Radioisotope Laboratory Research Engineer Application of radioisotope techniques to turbine engine research and development.
Licensed as user on Lab's by-product material license and as a radiographer on the radiography license.
1966 - 1968 Syracuse University Research Corporation Syracuse, NY Research Enqineer Medical radiological studies in renal Physiology.
v O
DONALD R.
LUSTER (cont'd.)
SPECIALIST. RADIOLOGICAL AND ENVIRONMENTAL CONTROL EXPERIENCE:
(cont'd.)
1961 - 1964 U.
S. Army Biological Laboratories Fort Detrick, Frederick, MD Radiation Technician (Military Service)
Nuclear radiation effects test program on biological material.
Radioactive tracer studies.
Completed Basic Radiological Health Course, Rockville, MD, 1963.
EDUCATION:
B.A.,
Biological Sciences, 1961 Johns Hopkins University M.S.,
Environmental Engineering, 1966 Rensselaer Polytechnic Institute, Public Health Service Radiological Health Traineeship PROFESSIONAL AFFILIATIONS:
Health Physics Society 9
O
ELMER A.
BARTON SPECIALIST. INDUSTRIAL SAFETY AND HYGIENE ABSTRACT:
Twenty-seven years of experience in the field of nuclear and industrial safety.
E7PERIENCE:
1974 - Present Specialist. Industrial Safety and Hvciene Execute all aspects of the industrial safety, hygiene, hazardous wastes and fire prevention programs.
1973 - 1974 Criticality Encineer (Actina)
Responsible for drafting NCS authorizations, inspections,. reviewing operating documents and manuals for conformance with License requirements.
()
1965 - 1973 Nuclear and Indus_ trial Safety Representative 1
(GUNFC). Fuels Fabrication. New Haven, Connecticut and (UNC) Fuels Recovery Operations, Wood River Junction, R.
I.
Experience includes administering operational health physics, nuclear criticality and industrial. safety progr&ms at chemical recovery and fuel component fabrication plants.
Health Physics experience includes developing and implementing policies and procedures, supervising health physics operations.
Nuclear Criticality Safety experience includes drafting of NCS authorizations, inspections, reviewing operating documents and manuals for conformance with approved licenses for the Rhode Island, New Haven and Montville facilities.
1961 - 1963 Health Physics and Safety Technician Fuels Division, United Nuclear Corporation, New Haven, Connecticut Responsible for routine sampling, monitoring, inspections, reports and records keeping.
O 1
O ELMER A.
BARTON EXPERIENCE:
(cont'd.)
1958 - 1961 Materials Control Technician, Nuclear Fuels Operation, Olin Mathieson Chemical Corp.,
New Haven, Connecticut Nuclear materials experience from 1958 to 1961 included routine records keeping, auditing, inventory, criticality control monitoring and other associated duties.
EDUCATION:
1955 - 1957 Lyndon Teacher's College, Vermont PROFESSIONAL AFFII,IATIONS:
o.American Industrial Hygiene Association o
American Society of Safety Engineers o
International Society of Fire Service Instructors O
o Certified Hazard Control Manager No. 403 (Board of Hazard Control Management, Bethesda, MD) e O
(S)
TH MAS J.
COLLOPY UrHC MANAGER. NUCLEAR MATERIALS ABSTRACT:
i Thirty-five years of experience in the nuclear industry.
Seventeen years managing regulatory compliance programs with collateral duties of Analytical Laboratory and SNM Scrap i
Reprocessing Supervision.
Eighteen years research and development in uranium solution chemistry, uranium purification by solvent extraction and uranium compound j
production.
Assisted in-plant startups and plant process support.
EXPERIENCE:
1981 - Present Manacer. Nuclear Safeguards Has responsibility for managing the Special j
Nuclear Materials and Plant Protection Program.
Responsibility includes managing O
compliance to these programs.
Responsibility included a major upgrade to the Plant Protection Program and a current j
upgrade of the Nuclear Material Management Program.
1977 - 1981 Manager Nuclear Safecuards (Actine) l Was responsible for managing regulatory compliance program at Naval Products.
This included the Nuclear Material Management function, the Plant and SNM Security function, the Nuclear and Industrial Safety function, and the Medical function.
All these functions were upgraded to meet NRC.
DOE, State. Federal and Public responsibility requirements.
1975 - 1977 Manacer. Nuclear Material Manacement Was responsible for managing the safeguards program for strategic special nuclear materials.
This involved the nuclear material management function, the plant security function and employee screening.
Present plant security program was being
(]
upgraded by improved physical features and v
devices and upgrading the patrol and the patrol supervisory force.
4
,m-
h THOMAS J.
COLLOPY (cont'd.)
i EXPERIENCE:
(Cont'd.)
1973 - 1975 Supervisor. Nuclear Materials Manacement Responsible for organizing the Nuclear Materials Control program at Montville plant, including personnel staffing and program organization.
Relocated SNM and Nuclear Materials Control program from New Haven to Montville.
1969 - 1973 United Nuclear CorDoration and Gulf United 1
Nuclear - Hematite ODerations Supervisor. Nuclear Materials Control Was responsible for establishing a-formalized Nuclear Materials Management System including five Material Balance Areds and a control system for each area.
In 1972, also assumed responsibility for laboratory operations and in this role, improved accuracy of SNM measurements, 4
which was required by more stringent accountability requirements.
)
1964 - 1969 United Nuclear CorDoration - Hematite Operations i
Group Leader. Chemistry and Scrap Recovery i
1 Responsibilities included assistance in startup of uranium scrap recovery (solvent extraction) and production of uranium oxide from uranium hexafluoride.
1953 - 1964 National Lead Company o'f Ohio Cincinnati. Ohio 4
Developed processes for solvent extraction of uranium from ores.
Directed projects 4
concerned with applied research for uranium processing.
Supervised infra-red and spectroscopic laboratory.
Provided process engineering support to laboratory and plant operations.
I(:)
a 4
,_-._--__.,,,,.,,-,.n..-.-,
O THOMAS J.
COLLOPY (cont'd.)
EXPERIENCE:
(cont'd.)
1951 - 1953 University of Cincinnati - Ohio Research Associate Performed physical - chemical measurements on liquid metals for use as heat transfer media in atomic reactors.
EDUCATION:
Bachelor of Science in Chemistry, Xavier University. Cincinnati, Ohio.
Graduated cum laude, first honors in Chemistry.
Thesis was on organic synthesis.
Master, of Science in Chemistry, Xavier University. Cincinnati, Ohio.
Additional graduate credits from the University of Cincinnati.
PROFESSIONAL ORGANIZATIONS:
American Chemical Society Institute of Nuclear Material Management PHI LAMBDA UPSILON CERTIFICATION:
Certified Nuclear Materials Manager TECHNICAL PUBLICATIONS & PATENTS:
Equilibrium Constants for the System Tri-n-butyl Phosphate-Water-Nitric Acid: J.
Phys.
C' hem.. 64 1328 (1960)
Spectrophotometric Evidence for Complex Formation in the Tri-n-butyl Phosphate-Water-Nitric Acid System:
J.
Phys. Chem.. 64, 1324 (1960)
Production of UF-4 from Refinery Scrap Materials; J. Metals. 12. 866 (1960)
Zirconium Mandelic Acid Complexes in Ethanol:
J.
Inoro.
Nuclear Chem.. 18, 184, (1961) (M.S. Thesis)
O e
l 1
7-THOMAS J.
COLLOPY (cont'd.)
TECHNICAL PUBLICATIONS & PATENTS:
(cont'd.)
The Chemistry of Uranyl Nitrate-Hydroxide-Urea System:
J.
Inoro., Nuclear Chem.. 10 113 (1959)
Some Evidence for the Presence of Uranic Acid in Uranium Trioxide-Water Systems:
J.
Inoro. Nuclear Chem., 10. 110 (1959) i Evidence for the Existence of Peroxyuranic Acid:
J. Am. Chem. Soc.. 81. 4167 (1959)
Gregory M. Reinhart and Thomas J. Collopy, Continuous Precipitation Method for Conversion of Uranyl Nitrate to Uranium Tetrafluoride - U.S.
Patent 3.063,592 assigned to USAEC November 13, 1962 Thomas J.
Collopy, John H. Mueller and Wendell S. Miller, Use of Nickel Aqsenides and Nickel to Promote Phase Separation in Liquid-Liquid Extraction - U.S.
Patent 3.202,476 assigned to USAEC August 24, 1965.
Nuclear Materials Control System in a Multi-Enrichment Processing Plant, Proceedinos from Twelfth Annual INMM
)
Meetinc. 233, 1971 O
e e
~ _
l l
License SNM-368 Chapter 11 Date:1/22/86 l
1, f
Appendix 11.4.6 1
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A Unc RESOURCES Comcany Uncasvine. Connecticut 06332 4
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t DIVISION OPERATING PROCEDURE DOP-024 REVISION NO. 3 DATE:
1/25/83 TITLE:
DOCUMENT CONTROL SUB-CENTER
- 1.
PURPOSE To escablish a system whereby production, testing and inspection l' personnel may withdraw controlled documents from an Area Document Control Center, via,the authorized PICC Withdrawal System, for use in a particular area of concern, and to maintain such documents within the confines of the area.
2.
SCOPE j
This procedure applies to Document Control Sub-Centers
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inspection for the purpose of maintaining only those controlled documents applicable to that particular area.
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- 3.
REFERENCES 3.1 CMC-49 l
3.2 MIL-Q-9858A 3.3 DOP's 006, 025 and 026 l
3.4 UNC's Security Procedure Manual e
]
INFORMATION CATEGORY UNCLASSIFIED
~
ill"M82.
.L AUTHORIZ~ED CInSTpIFIER DATE
- Denotes change.
.)
i i
- UNC NAVAL PRODUCTS MANAGERS -
VICE PRESIDENT
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-A 1
OPERATIONS QUAL. ASSUR. QUALITY CONTROL TERIALS NG NfRI 7W5*
Y"D YTK n elS-i Date:/ /
Date:
Date/At / G f
Date Dhtes
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Prepared by: V.F. Anthony; Revised by:
L. Mandelbe'rgfir Date: 11/24/82; R. Wilson /G. Grimm rsss::: ;
Page 1 of 7 i
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REVISION NO. 3 2
4.
DE FINITIONS 1
- 4.1 Process Information Control Center (PICC) - Primary control center charged with the responsibility of preparation and issue of controlled documents required by Document Control Centers.
4.2 Area Document Control Center - Main control center established within a manufacturing site for the purpose of supplying and recalling controlled documents as required
{
j during manufacturing, testing and inspection operations.
l 4.3 Document Control Sub-Center - Sub-Center of an Area Document Control Center established in manufacturing, testing and inspection areas for the purpose of maintaining only those controlled documents applicable to the particular area.
4.4 Document Custodian - Personnel assigned the responsibility of maintaining established document control centers.
3 4.5 Document Withdrawal Notice - A sign-out card used to record the withdrawal I.nd return of controlled documents (see Exhibit II).
5.
LIMITATIONS - None 6.
RESPONSIBILITIES L
- 6.1 Process Information Control Center (PICC) - Prepares and distributes, to Production Control, all contrclied documents and revisions thereto, as directed by means of the ECN System (DOP-006).
- 6.2 Area Document Control Center Custodian ( ADCCC) - Maintains,,
l issues and recalls controlled documents required for use in the manufacturing, testing and inspection area.
Custodian is responsible for destruction of obsolete documents.
I 6.3 Document Control Sub-Center Custodian - Maintains controlled
]
documents required for use in the area in which the sub-center was established.
(
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v Page 2'of 7 i
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UnC DEVRL PRODUCTE i.e.
Oms;on of Umte Nu;' ear Corcorston iET Sant:v Cest tAca:
- e'ecacee 2C3 $431511
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A UAC AEsOURCES C:?pany cr caswue. Conrect. cat 06352 DIVISION OPERATING PROCEDURE DOP-024 a
REVISION NO. 3 7.
PROCEDURE 7.1 Document Control Sub-Center
- 7.1.1 The Supervisor of a Document Control Sub-Center shall post names of the Document Custodian and alternate (s) to maintain documents in his area of responsibility.
Security Repository Access Control Form may be utilized in place of separate posting.
7.1.2 It shall be the responsibility of the document custodian of each sub-center to determine what documents are required for his particular area)
This may be accomplished by either of two methods:
()
a)
Compile a list of the documents required per the Manufacturing Route Card and withdraw the documents from the Area Document Control Center located within the area of operation (see DOP-026).
b)
Withdraw the documents from the Area Document Control Center, as required.
7.2 Maintainino the Document (s)
- 7.2.1 File cabinets (security approved if any of the documents are classified) shall be used for controlled documents.
The front of each file cabinet shall be labelled to show identity of the types of documents contained therein.
Example:
Drawings, MOP's, etc.
7.2.2 Documents shall be placed in individual folders showing the document identification and shall be filed sequentially for rapid retrieval.
- 7.2.3 Where file space is not available, documents other than drawings may be maintained in loose-leaf binders, provided the binder is plainly marked, showing the type of document contained.
Different types of documents, such as MOP"S, SP's, etc), must Os i
not be intermixed in the same binder.
i Page 3 of 7
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DIVISION OPERATING PROCEDURE i
DOP-024 4
REVISION NO. 3 a)
Binders containing classified information must be ~
so marked and stored in an approved security cabinet.
P 7.2.4 All security cabinets must be locked when unattended (except in approved opened storage' areas).
7.2.5 Auditing personnel shall be allowed access to all control centers for the purpose of conducting periodic audits.
7.3 Doerading of Documents l
- 7.3.1 When a document has been revised, the Custodian of the Area Document Control Center shall immediately notify the Custodian of.the sub-center having the i
1 previous issue.
a)
The Area Document Control Center Custodian
( A DCCC ) shall deliver the revised document (s) to j
the sub-center and retrieve the obsolete document ( s ).
The ADCCC will then destroy the obsolete documents.
l 7.4 Control of Obsolete and/or Lost Documents j
- 7.4.1 The Supervisor (s) of the Document Control Sub-Centers are responsible for every controlled document received and must yield all copies of obsolete document (s) to Area Document Control Custodian before revised documents can be released to sub-center (s).
a)
Exception:
Disposal of documents issued to " hot" areas will be the responsibility of the cognizant supervisor of the sub-center.
Notification in writing (Exhibit III) will be given by the supervisor of the sub-center to the Area Document Control Custodian when a controlled document is destroyed.
O 7.4.2 If a document cannot be located, an intensive search will be conducted.
A replacement shall not be released to the sub-center except upon written
.w Page 4 of 7
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a)
A " Lost Document Report Form" (Exhibit I) shall be prepared and delivered to the Area Shop Manager.
b)
If the missing. document is classified
" Confidential," a copy of the report form shall-be sent to the UNC Security Director by the Area Shop Manager.
c)
The Security Director will issue a " Security O.
Infraction" to the individual responsible for the loss if the Confidential document cannot be located within a reasonable time period.
7.5 Withdrawal and Return of Documents 7.5.1 Withdrawal of Documents a)
The " Withdrawal Notice" (Exhibit II) shall be prepared by the Custodian of the sub-center for each new document that will be maintained in the sub-center.
b)
Personnel wishing to withdrav documents from the sub-center may do so by signing and dating the Withdrawal Notice.
- NOTE: The documents may'be withdrawn from the sub-center without signature provided that they remain in the area of the sub-center and are under the responsibility of the applicable supervisor.
c)
The withdrawal Notice may be filed in the same jacket, folder, binder, etc), from which the document was removed, or maintained as a group in a separate file.
O
.l Page 5 of 7
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DIVISION OPERATING PROCEDURE DOP-024 REVISION NO. 3 7.5.2 Return of Documents a)
When documents are returned to the sub-center, the individual returning the documents or the J
Document Custodian shall sign and date the Withdrawal Notice in the spaces provided for the return of the documents, b)
If any document is found to be shop worn or torn, such that it is no longer legible, the Custodian shall return the document (s) to the applicable Area Document Control Center and request replacement (s).
)
7.6 Maintainine Active Withdrawal Notices 7.6.1 Active Withdr'awal Motices for documents that are removed from Document Control Sub-Centers may be maintained as a group in a separate file.
At least once each week, the Custodian shall check the Withdrawal Notices and contact any borrower who has l
held a document longer than one (1) week to determine the status of usage.
(This is a precautionary j
requirement to prevent loss of controlled documents.)
{
l 7.6.2 Documents that are unaccounted for in the weekly check shall be formally reported to the Area Document Control Center Supervisor.
7.6.3 Documents that are used continuously in such areas as Gamma Scan, Radiography) Weld Probe, Welding, etc),
may be held in those areas until they become obsolete.
However, the Supervisor of the area holding the documents shall be responsible for the security of those documents.
7.6.4 When controlled documents are no longer required in a Document Control Sub-Center, the Custodian shall return all copies to the Area Document Control Center.
O The Custodian of the Area Document Control Center shall check the returned copies against the Withdrawal Notice to assure no copies are missing,
=
l Page 6 of 7
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M o., f ree of Umatec Nyctes* Corcergt on
$* Sancy Desed Acac Te'e:ncee 2034D$ 15*
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a une assouness comes,y uncas<.iie. connect c.t ces *2 DIVISION OPERATING PROCEDURE DOP-024 REVISION NO. 3 a)
Missing documents shall be handled per Para.
7.4.2.
8.
NOTES 8.1 The following Exhibits are typical formats used in UNC's Document Control System and may be altered as necessary without formal revision to this DOP.
8.1.1 Exhibit I
- Lost Document Report Form 8.1.2 Exhibit II - Withdrawal Notice
- 8.1.3 Exhibit III - Disposal Notification i
9 4
i O
Page 7 of 7
n 4
O LOST DOCUMENT CONTROL FORM PART A
(
i DIRECTIONS:
1)
THE AREA DOCUMENT CONTROL CENTER CUSTODIAN SHALL COMPLETE PART A CF THIS FORM PRIOR TO ISSUING A REPLACEMENT OR A REVIEWED COPY OF A CONTROLLED DOCUMENT THAT CANNOT BE LOCATED.
l NOTE:
FAILURE TO PRODUCE THE MISSING CLASSIFIED DOCUMENT (S)
WILL RESULT IN A SECURITY INFRACTION FOR THE EMPLOYEES CHARGED WITH THE LOSS.
2)
AREA DOCUMENT CONTROL CENTER CUSTODIAN THEN DELIVERS FORM TO EMPLOYEE'S SUPERVISOR WITH A COPY OF WITHDRAWAL NOTICE ATTACHED.
t l
3)
SUPERVISOR BECOMES CHAIRMAN OF TASK FORCE TO SEARCH FOR MISSING i
DOCUMENT (S) IN ACCORDANCE WITH ODP 400.37.
SUPERVISOR HAS TWO (2)
WORKING DAYS TO COMPLETE "PART B" OF FORM AND SUBMIT TO COGNIZANT DEPARTMENT / SHOP MANAGER.
1 4)
TO:
AREA SHOP SUPERVISOR DATE:
FROM:
i DOCUMENT CUSTODIAN
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DOCUMENT CLASSIFICATION:
CONFIDENTIAL l
l UNCLASSIFIED l
l CUSTODIAN REPORT LOSS:
CONTROL CENTER (SIGN)
NO.
DOCUMENT IDENTIFICATION NO.
REV. NO.
CONTROL CENTER NO.
i
)
DOCUMENT ISSUED BY:
SHIFT DEPT.
DATE (PRINT NAME)
DOC. WITHDRAWN BY:
SHIFT DEPT.
DATE e
5)
SEE* REVERSE SIDE FOR PART B.
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l DOP-024/026 EXHIBIT I 11/82 i
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UGC OAVAL PRODUCTS COPY NO.
l DOCUMENT I.D. NO.
i REV.
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DATE WITHDRAWN EXT.
SHIFT NO./ WITHDRAWAL ISSUED RETURNED RETURNED OR BY NO.
DEPT. NO.
DATE BY DATE RECEIVED BY
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The document listed below has been destroyed due to illegible condition, contamination, or revision changes.
f The remains of the confidential document have been dis-l carded into the security' type confidential repository.
DOCUMENT NO.
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DESCRIPTION r
REVISION NO.
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DEPT. NO. & NAME i
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EXHIBIT III DOP-024 /026 12/82 I
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Appendix 11.6 0
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I Cf-i UnC NAVAL PRODUCTS
. I Onnsen of Unded Nuclear Corcoraten 67 San @ Oeun Acad Tetepnene 23'848 1$M i ggg A Unc RESOURCES Company Uncasvdie. connecticut C6382 I
NPQ ORGANIZATION AND POLICY MANUAL i
POLICY STATEMENT 13 02-2 11/19/80 APPROVAL:
' NUCLEAR CRITICALITY SAFETY CONTROL SYSTEM PURPOSE:
To cefine THE CONTROL SYSTEM used to assure snat a criticality
~
incident coes not occur at this facility.
j t
SCOPE:
I All personnel anc operations or construction that ci r ectl y affect or could indirectly affect uranium-containing materials, components or wastes.
I POLICY:
h 1.
All operations or construction cirectly involving or
[~l(,
\\-
I potentially affecting uranium containing items shall ce I
reviewec ana approvec Dy tne Nuclear L Incustrial Safety Department.
2.
All non-fuel components which appear similar to fuel components (e.g. fillers, elements, sectionec element pieces, j
assemolies, some ena plates) snall oe nandlec anc stored as fuel Dearing components unless autnorizec other ise oy Nuclear anc Incustrial Safety.
All personnel sna11 00 trained in baste ano specific l
3.
criticality control safety.
l t
4.
Enforcement of criticality safety rules snall be the l
responsibility of every memDer of UNC Naval Products.
i I
S.
Every criticality safety violation or unsafe procecure shall Ce reported in writing.
f j
i OdFINITIONS:
g CAITICALITY INCIDENT - The accumulation of a s'ufficient mass of enricnec uranium material iconsicering moceration concitions) to l
1 produce uncontrolleo radiation and neat.
<s RdSPD4SIcILITIES:
k /' i Jot 6tn NIS i
P4CJECT MANAGERS CC:, TRACT Av.MINISTAATIuN
[. _
evaluation of proposec work anc of any contract cnanges.
Page 1 of 3
,3 3n=,
UnC MAVAL PRODUCTS C*
Omsson of United Nuclear Corporation 67 Sancy Desert Acad Teleonone 203/8481511 i gg A Unc RESOURCES Corncany Uncasville. Connecticut 06382 l
NPD ORGANIZATION AND POLICY MANUAL POLICY STATEMENT 13.02-2 11/19/80 APPROVAL:
NUCLEAR CRITICALITY SAFETY CONTROL SYSTEM ENGINEERING / FACILITIES / DESIGN & TOOL ENGINEERING / QUALITY CONTROL / MANUFACTURING - ODtain NIS, review ano approval of operations, facilities, equipment, tooling, construction or any modifications / changes thereto prior to implementation.
TRAINING / PERSONNEL - Provice initial and re-orientation training to all employees in criticality control.
AL L DEPARTMENTS Provice on-the JoD familiarization anc training to all new or transferreo personnel in criticality Control.
Verbatim compliance witn all NIS criticality Controls.
NUCLEAR C INDUSTRIAL SAFETY DEPARTMENT - Review anc make oisposition on all suDmitted items associated with NIS i
requirements.
ii Develop anc maintain programs of criticality prevention.
f l
ODtain auclear Regulatory Commission license, approval.
I e
Avoit compliance of all oepartments.
l RdFdRENCES:
i Employee. Relations Policy 01019d Criticality Safety i
e i
j Supervisors Guide Section VII, Policy #1, Criticality Safety l
Operations Department Procecure CDP 300.20. Request for NIS I
Autnortzation l
l Operations Department Proceoure 200.40 " Reporting of Unusual Incacents" Engineering Department Proceoure 0102 " Preparation of j
Manuf actur ing Route Caros" l
Engineering Department Procecure 104 "Cocument Review" Pa;e 2 of 3
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unc nnvnt pacoucTs t!
Division of United Nuclear Corporation 67 Sancy Desert Acad Teisonone 203/848-1511 l gg A USC RESOURCES Cornoeny Uncasvine. Connecticut 06362 l
i f
NPO ORGANI4ATION AND POLICY MANUAL POLICY STATEMENT 13.02-2 11/19/80 APPROVAL:
NUCLEAR CRITICALITY SAFETY CONTROL SYSTEM Division Oper,ating Procecure 00P-023 " Storage and Control of fuel i
bearing Components".
I I
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Page 3 of 3
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UDC MAVAL PR. ODUCTS v
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yg Oms.on of Umted Nuc! ear Coreo at:on 67 Sancy Cesert Acac Teieonone 203/8441511 A UAC RE5oURCES Company Uncasvine. Connect cut C6382 1
GPERATIONS DEPARTMENT PROCEDRUES OOP 300 21 Revtston No.
O September 22, 1980 TITLE:
CRITICALITY CONTROL 1.0 P,oRtQ56:
Tne purpose cf tnis procecure is to cefine where Criticslity Controls are usea anc how tney are enforcec.
2.0 S(GP1
Tne orccecures in tnis document are applicaole to all Operations personnel.
3+3 E55555$E51:
q 31 Organization anc Polacy Monu3) Procecure No. 13.J2 -
l C
Nuclear Criticality Safety Control System j
i 3.2 imoloyee Relations Policy Manual, Procecure No. 1019: -
Criticality Safety i
3.3 Division Operating Procecures. No. 00P 023 - Storage and i
Control of Fuel Searing Components 3.4 dequest for NIS Autnorization J09 200.40
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GAERATION5., EPA 4T 4ENT AsPnCyats PROG.
PRO 3.
PROD.
PAC,.
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unc navm. pnooucrs gg Division of United Nuclear CorporaDon 67 Sancy Desert Acac Te4eonone 203/848 1511 A UOC RESOURCES Company Uncasville. Connecticut C6382 OPERATIONS DEPARTMENT PROCEORJES GOP 300.21 3.5 Criticality Controls Lis; of Authorization 3.6 Engineering Gepartment Procecures 102 anc 10*
3.7 Supervisors Guide,Section VII, Policy #1 - Criticality Safety
'.. o giE13111g31:
CRITICALITY CONTROL involves har'dling movement, processing and' storage of fuel or fuel-bearing components. Criticality Controls are oesignec to assure a Criticality acc i ders t cannot occur.
5.0 LIMITATIONS
Tnis procecur e outlines Cri tical i ty Procecures mesec on referenced cocuments, cut coes not supersece any Nuclear
(
Incostr al Safety Document.
o0 11129'illiis11111:
i t
61 It is the responsiDil tf of r,uclear Incustrial Safetr Gesartment. to provice carection, epprove anc provice incoctrination training to eli ut.C e.npl o y ees anc cersonnel ass i gnec to tne Montvill e Pl ent.
o.l.1 NIS Department provtoes Criticalaty f a.n I a r t t y tnrough incoctrination traint1; ta all rie.
employees.:tn a refresner s e.s s t e n for 23cr emcloyee as cetermined snJer tne civtaten p r ogr o;n.
Continuec sgecit c soarenes5,v:jects are presentee pertocically at daareness sessicns.
o.1 2
.',15 approval is requirec for all fuel l
nanaling/storege fixtures (locattens anc gesign
[
of).
I j
o.l.3 N;5 Deparement srall ate ana revie, ai1 reasests far Cri tical t ty cndn9=s.
t l
- . 2
- e as tne respotissai1
- ty or spe r a t i on s
.,ep ar tc.ent 5 aesevision tc en.n riister s e r ;,a t tr:: cams 1 ance to t e O :!
ap;rovse Criet.:al ty Controls.
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. OPERATIONS JePART:4ENT PROCEORuE5 OuP 300.21 o.2 1 Operations department Supervision sna11 insure tnat each person in tneir area uncerstancs ano follows tne approvec Criticality Controls.
Empnasis snell ce given to riew or transferrec employees.
o.2 2 Operations empicyees are responstole for complying witn tne Criticality limits, anc controls as prescrioec oy criticality control cocumentation.
i o.2 3 Area Supervision is responstole for naving approvec floor merkin,s in place.
o.2.4 Area Managers anc NIS estaolish marxings ana icentify requirements for morn anc storage
! (q locations anc equip nent use.
i o.3 It is tne responsioility of tne Support Grou s to follow I
approvec Criticality procecures ano to secure ap roval g
at stems involving Criticality tnrougn tne r3: S Jepartment anc tne Snop Panagers.
j i
i j
o.3 1 Area supervision sna11 cocain tils revtea anJ
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approval of any enanges in eqatament, la,oct or procecures for fuel c on t a i n i ng co.npanen t s.
1 l
o.4 all c o.npone n t s, ansen appear as a fuel icen cr 5: talar i
to a fuel i t'e m (e.,..
ourmy a s s e;no l s,e s / non-f ue l elements) must ce treete; as f.e1 1
o.4.*.
All non-fuel components wn cn aope.sr similar to fuel c o.n po r.e n t s (e.g..
fillers, elements.
assemolies) snali ce n.3nclec anc storec ai fuel searing components uniass autnorizea seneratse oy feuclear a fl0 Incustrial Safet/ in wr4ttern for....
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g Dnnsion of United Nuclear Corporation 67 Sancy Desert Road IeleDnone 203/848 15 A Unc RESOURCES Compar y Uncaswise. Connectreut 06382 l
OPERATIONS DEPARTMENT PROCc'dRVES COP 300.21 o.4 2 In any NON-RCUTE CARD operation for ell non-fuel components unicn appear similar to fuel. ene component snall De nandled as fuel unless proven to oe non-fuel.
PROJF to be non-fuel is by acceptacle instrument measurement AND oy cocumentation cnec4 to se non-s i
fuel.
o.4.2.1 ACCEPTABLE INSTRUMENT MEASUREMENT Determination nach ractation instrument (e.g. Security nM-3 or Heal tn Physics Geigar tube type) Dy. Security trainec anc approved personnel Cr medith PhystCs personnel.
6.5 It is the responstotitty of anyone ano ooserves a cr i tic al i ty violation to report it to area supervision.
c.5 1 Any possiolv violation must ce correctec immeciately.
o.5 2 Area supervision, upon notifscation of e l
criticality violation.
311 concuct an investigation to cetermine tne incava:ual ts)
?
responsiole for tne violation.
A formal.ritten reprimanc will oe issueo to tne inciv Jual(s) resconsiole for tnat violation, s
7-ii$152dii 4
l Tne orocecure for Crittcalty Control:
l l
71 ine Nuclear anc incustrial Safety Department nas approval responstbtlsty for any op e r e t i on s n i c n
.r. 3 y l
effect fuel-oearing co.9ponents.
7. ;. '.
All route ceras. (includinc repair; must ow routec enrougn ali for tnear a;;raval.
t 7..'. 2
- ecuest ta.4!i ror cnanges or nea arcce.ses m.st De in ortti9g a3 Gutlinec in Form NJi 4 4
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t Gv UnC NAVAL PRODUCTS g
Desion of Unitec Nuclear Corporapon 67 Sancy Desert Acac Te.ecnone 203/848 1511 A UnC RE5ouRcE5 Corncany Uncasmile. Connectrcut 06382 1
GPERATIONS DEPAKTMENT PAOCEORJES OOP 300.21 a
7.1 3 Tne originator of a request for NIS authorizatton snali submit tnat request to nas/ner Snop Manager.
7.1.4 Tne Snop Manager will revien the request snc approve or cisapprove.
It approvec, ne.t11 senc it on to NI5.
715 r415 will review tne request eno rescono to tne originator.
7.2 Crittcality Control Autnorizdtions:
7.2 1 Criticality Control Autnortzation is assvec cy I
means of NI$ Authortzations D/ route Cdrd approval, anc/or oy written cucament or signature approval.
l
\\
7.2 2 NIS Criticali ty Control Autnorization forms ere postec in standard Criticality Control s gn-j nolcers anen requirec.
i 7.3 Criticalsty violations - General Prececues:
I 7.3 1 Notice of a violation or unsafe procecur e is given to tne cognizant suuervisor of tne arwa concernec.
7.1 2 7ne violation is ccrr ects; s c rea t a tel f onen xnc n.
7.3 3 written ans.er to an 15 Je,artment i.atice af
'i Safety /tclation or uns.nfe -racecure, ststin, tn*
l corrective ac tion ta<en or to ce taxen ( itn cu+
j j
oete) to prevent recurrence, is pre;are: of t..e l
Suoervisor ana enoorsec of nigner 1sval er a
Supervision er oy tre area 4ana,er.
- ine.
CrittCallt CJorcinatJr) f 7.3.-
After ca: art 44nt supervis
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- etarni ne
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.43s respor.stule for t:e violation, e t o r..a i wratten e spr i nanc.51 ! Le issue;.
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g Onnsion of United Nuctear Corporation 67 $anov Desert Acad Teleonone 203/848-1511
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A UnC RESOURCES Company Uncasvule. Connecticut 06382 OPERAT. IONS DEPARTMENT PROCEURUES ODP 300 21
- 7. 3 5.1 If satisf actor y resolution cannot ce reacnec, tne matter is referrec to tne Operations Manager for cecision.
7.4 Color Codes and floor Markings:
7.4 1 Color Coces anc Floor Mar 4tngs are usec to cesignate fuel work zones anc fuel storage areas or cevices.
7.4 2 Requirec Floor Markings are postec on cisplay coarcs in tne snops ano are given in written procecures.
7.5 Movement of Fuel Components:
7.5.1 All fuel aill be movec uncer approvec critical'ity procecures.
7.5 1 1 Li.e.ics are postec in eacn area.
7.5 1 2 naivers to postec limits must ce approvec oy NIS in -rating.
i I
! 63 ilt!! alii:
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31 edotice of Safety V i o l.3 t i 0 n or Jnsore Proce:ure i.4 Cr1 tic 31 It-f Contrcl '4I5 utr.Orttit1 in i
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ODP 300.21 EdM:
rwca, tnc.rea E Ieeusmix. Sum Deamen Exhibi 8.1 Cm lGIE & S;EiY v!Q.Ai!Of m 06/E PPEUE - !bc. Oti.
H. Nrsics Itc. Sucy _. One CATE & OCC. RTE
?GIE PC.110 IRTE OF ISST i
ltr'JKi::) 3Y:
IIILE PEEHNE DISCESIGl:
I I?tGIATE / Gift 17;Ei:
Within 3 wk.ir4 faye f.rs: the data of this retice. ca 5@eMaor of t?m area er operatiest ct.4er ad is to f=rart a seit.an armer ce the :C5 Depar=ent ' Wager ccntair.ir4 tr.*creatica specified bolcw. Mader is to te endorsed by a hiw== level of espar=ent supervisten er my the p:meactien sno, nanagereeriticality c..t are. c:ss:e.L=cer.
TO: ?.vaca, !!!$ Cuanec 50M:
! ATE:
9J 70 IEIE 7 S/ETY VIRAi!Of M LhSAFE Pf05UE MiiOM C1PECTIE ;GIOi (IF MO:
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hec 1v tv t-t17.tz.a1fsi *.-ve1*M r By initials P.erecc.. eeen L*u11vid:;a.1 listad belcw actrewledens his bei.4 trJc: ed of tr.is *.clatten er esafe procedure A.*3*. Pois ".*."d.erstandi.*q a.a i adereness af hi.3 res5crJ2tlity 12 FreWnt sm.a.wge.
s L-/.ividual!si ta*:- ed 1.1taals f
No. Of Any *verg W MJest Adeociated WitP. h.AW Ac=.; n
- ata c:rytete.r t= te C:rsisted swaar rt un.e.ien she,.varacar
~
- CRillCAlllY CONIMUL "
NIS AUTHORIZATICH NUMBER:
REV(DATE):
SUBJECT:
EQUIPMENT / TOOL:
AREA:
RETERENCES:
CAUTION: The processing of fuel iterns under this Authorization is prohibited unless the Authorization is posted in o visually accessible location.
O i
i APPROYAL BLOCK IHf0RWATl0N CATEGORY UNCLASSIRED NIS:
AUTHORIZED CLASSinER DATE This authori:otion expires autornatically on changes in equipment, location, materiab, or if limit and controls do not reflect work operoUons being perforrned.
o
doyfj u t @ l y l_ I de1
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e O
C' SLJIION POLICY REVISION
(
SUPERVISOR'S GUIDE vu 1
o SUBJECT
.#^
y CRITICALITY SAFETY purpos e To present the Criticality Safety program.
Seone A.
Applies to all employees at all times.
Resoonsibilities A.
Nuclear and Industrial Safety establishes and administers the program to effect criticality safety and provides technical direction and support in areas relating to nuclear safety.
B.
Department heads assure that activities under their jurisdiction or control are reviewed by NIS and work is conducted in accordance with approved nuclear criticality control procedures.
{
C.
Supervisors shall train personnel, observe their performance and enforce criticality controls.
D.
The employee must strictly adhere to criticality controls and conduct his/her l
actions so as not to create a criticality hazard.
I polley A.
All work processes, use of equipment, types of materials and designs and installations of facilities shall be evaluated for criticality safety.
Criticality controls must be established prior to use uith fuel materials or n:n-fuct ite:ns that look similar to fuel items.
Criticality controls are established so that no single credible equipment B.
failure or human error would permit a criticality accident.
C.
Criticality controls, approvals and requirements shall be evidenced in written form (generally as a Route Card and Area Criticality Control posting).
3 1.
Supplemental written procedures shall be issued as necessary to implement criticality controls and/or increase the effectiveness of the program, t
D.
Inspections, audits, orientations, instructions and testing of employee knowledge relative to criticality controls shall be performed by authorized personnel.
o Any violation of criticality controls or conditions deemed unsafe are cause for E.
icmediate correction or shutdown of the unacceptable condition.
DATE 9/24/84 PACE 1 or 6
hd IM Il hMM;IgNQl:
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They say a lot about our PEOPLE and our PRODUCT Ok
}.
SECTION POLICY REVISION i
SUPERVISOR'S GUIDE o
SUBJECT
,/.
CRITICAt.ITY SAFETY Poliev (continued):
F.
Requests for authorization and/or approval for fuel operations shall be directed to Nuclear and Industrial Safety. Approval must be obtained prior to startup of such operations involving fuel or fuci "look-alikes."
G.
Nor-fuel bearing parts or materials which are similar in shape and/or appearance to fuel-bearing parts or materials (such as dummies, mockups, etc.) shall bc treated as fuel-bearing unless specifically excepted.
H.
Fuel-bearing material is controlled during all handling, processing, and transport operations and at or in all storage locations.
I.
Fuel-bearing materials are moved by personnel at the direction of the Supervisor of the areas concerned.
J.
Fuel-bearing mateelais are properly stored in approved racks, containers, or carts when not being worked on.
J K.
Changes in equipment laywut, fixturing, equipmett, process, etc., potentially af fecting criticality safety limits or contre'.s require NIS approval prior to making change.
Requests for Criticality Safety Review and/or Aporovals A.
Employees designs, tooling, plans for installation of facilities or equipment involving fuel-bearing material shall be submitted to NIS for approval using Form N05-1 as appropriate.
B.
All Route Cards and revisions (fuel or non. fuel) shall be approved by UI3.
Criticality controls and/or approval are provided by hlIS in response to the C.
requested review.
Criticality Control Authorizations A.
Form NCS-0-B-1-0 is designed to be used both as an authorization for publication in the Celticality Control Manual and as a posted sign or instruction. ~ '
B.
The authorization is prepared by NIS in cooperation with operating supervision and issued under approval signatures of NIS and the Shop Criticality Coordinator (i.e. Shop Manager).
C.
Changes in an authorization are made under the same general procedures as indicated in section titled " Requests for Criticality Safety Review and/or
(
Approvals".
D.
Authorizations shall be posted in standard Criticality control sign holdors at approved locations when practicabic.
DATE 9/24/94 PAGE 2 of 6
M f__l_i! d.uI @ l0II (ri*i!B,M *}*f9*43_ N Afi_Q M *Il* A 5
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SECTICN POLICY REVISICN
(
SUPERVISOR'S GUIDE VII 1
o SUBJECT
~
J CRITICALITY SAFETY Criticality Safety Violations or Unsafe Procedures A.
Notice of a violation or unsafe procedure is given verbally to the cognizant supervisor of the area concerned.
B.
The violation or unsafe procedure is corrected imediately if practicable.
C.
If the immediate floor supervisor is not available, each successive level of supervision is contacted in turn until an operating supervisor is notified.
D.
The notice of a violation or unsafe procedure shall be confirmed in writing within three (3) working days by a Nuclear and Industrial Safety Department member. These notices are issued by or with the concurrence of the Safety Specialist or Nuclear and Industrial Safety Department Manager.
E.
A written answer to the violation or unsafe procedure notice stating the corrective action taken or to be taken (with due date) to prevent recurrence, shall be prepared by the supervisor and endorsed by a higher level of Supervision and by the Ar'ea Manager. This endorsed answer should be transmitted I
within ten working days from the date of the notice to the Nuclear and Industrial Safety Department for review and concurrence.
F.
Corrective action satisfactory to Nuclear and Industrial Safety is recorded. If satisfactory resolution cannot be reached, the matter is referred to the General Manager for decision.
C.
Form NIS-6 issued to report criticality violation and unsafe procedures.
Marking and Identification A.
Identification of Criticality Zones and Boundarics 1.
Floor Markings - White dots - Ncn-fuel, Red Dots - Fuel - minimum 2" diameter at maximum 18" separation. A slightly small red dot with a thin white rim is used on the red floors in "B" South.
2.
Use of physical barriers, dividers and walls are used where appropriate.
3.
Signs are used where appropelate.
4.
Boundaries are readily visible and apparent and take traffic into account.
Such boundaries are intended to allow passage by zones to other zones without passage through zones.
B.
Identification of Fuel Storage Racks and Areas, and Non-fuel Areas 1.
Boundary Floor Marking - Red dots with minimum 2" diameter at maximum 18" separation.
DATE 9/24/84 PACE 3 of 6
~
w P
' They say a lot about our PEOPLE and our PRODUCT...
/.
SECTION POLICY REVISION f
SUPERVISOR'S GUIDE l
vtt 1
o
"""3
LJric:
CRITICALITY SAFETY Marking and Identification (continued):
2.
"Non-Fuel Parking" or Fuel Exclusion Arcas Marking - white dots or white strips nominal 0" wide as diagonal markings, between storage boundary and fuel locations.
3.
Boundaries are located with consideration as to traffic patterns and use of markings as aisle boundaries allowing passage and regulation of fuel-bearing materials.
4 Legends such as " Fuel Storage", "For Skids Only", "No Parking",
etc., are
~~~'
used for clarification in areas concerned as necessary.
C.
Color Coding 1.
Color coding may also be used to identify approved fuel transport and storage devices.
(,
I 2.
For this purpose, red oxide, red, or maroon red color as pa* int, tape, er similar marking means meeting prohibited materials specifications may be used if practicable. Similarly, white color can be used to represent non-fuel transport or storage devices, Application may be as a label or target, visible, from all angics, or a.
as complete coloring of the item.
(For exampic, fuel racks and carts may be painted all red.)
D.
Identification and Storage of Empty Fuel Containers 1.
At any location wherc empty containcrs normally used for fuel are not to be handled or stored as fuel-bearing, the measuccs be' low shall be followed:
a.
" Birdcages", storage &
Attach an "MT" or " Empty" tags or shipping drums or labels to each container in containers and large readily visible locations. The units.
identified empty containces can be in other than fuel storage arcas.
b.
Filler trays, clement Either identify as " Empty" with Las boxes and portable or labels or turn upside down or containers.
on side with cover open. Store in specific location separated from fucl storage in arca designated as 1
empty container storage location.
2.
When needed for fuct use, remove the "MT" identification and store as approved for fuel.
DATE 9/24/84 PACE 4 of 6
b 5-II bMD !9bNN They say a lot about our PEOPLE anc our PRODUCT...
n SECTION POLICY REVISION
(
SUPERVISOR'S GUIDE g vu 1
o g
SUBJECT l
CRITICA1.ITY SAFETY E.
General a
1.
When fuel transport or storage devices or criticality zones are voided by relocation or no longer used for fuel, color coding or other markings and identification shall be removed or volded.
2.
If devices such as racks and carts normally used for fuel and so color coded are converted to other uses, each device shall be completely recoded all white and marked for "non-fuel" use.
F.
Criticality Control Signs and Holders 1.
Sign holders used for criticality control authorizations or instructions will normally feature blue and yellow colors and be standard in form and content.
2.
Inserts or other signs containing criticality control information are designed for maximum effectiveness as a sign and may feature red lettering O
for emphasis, d
Signs and sign holders shall be provided by NIS Criticality Safety 3.
Engineering.
Permanent signs are posted under the direction of area management with 4
criticality safety concurrences in accordance with the following guidelines:
Review the criticality control sign for content and select a location a.
for posting which meets the following requisites:
(1)
Appropriate to the content of the sign for the area or operation.
(2)
Readily visible.
~
(3)
Non-interfering with zone or area activities.
(4)
Not readily susceptible to damage or destruction.
(5)
Not causing a nuisance or hazard.
i b.
Securely attach, affix, or hang, etc., the sign or holder.
If a sign or holder becomes outdated, unsightly, or in need of c.
revision, call NIS for upgrading.
d.
If a sign becomes obsolete and no longer applicable, remove sign and contact NIS for disposition.
Signs exposed to the weather or unusual humidity conditions must be e.
made to stand up to this environment by NIS.
DATE 9/24/84 PACE 5 of 6
bWfN.b N~Y YY.,.h' h\\
_ S'?
r They say a lot about our PEOPLE and our PRODUCT.
O SECTION POLICY REVISION SUPERVISOR'S GUIDE vt1 1
o SUBJECT y{
)
CRITICALITY SAFETY C.
Responsibility l.
Area Managers and NIS shall establish marking and identifying requirements for work and storage locations and equipment use.
2.
Area Supervision is responsible for initiating actions to mount markings in location and maintaining access and legibility.
e 4
1 e
O DATE 9/24/C4 PAGE 6 of 6
T i
T.xhibit 1 Pg. -1 cl 3 O
CPJTICAI.ITY S ArrTY PROCIDURI
(
NO.
I of 1
- ~I.I:
PROCIDURI FOR OBTAINING RIV.
1
~
CRITICAI.ITY S '"g RIVIEW/
APPRCvAt/A RIIATION
. DATE:
9/22 /83
,./
PAGE 1 of 1 I
Prepared By:
g/((gs g
Approved:
{l' f
N 1 S Dept.
f 4.
The following proc )7
. ure is to be followed for requesting review, revision or approval of criticality controls or limits:
(1) Review current ree,uirements to determine what criticality controls apply j
or which might be appropriate.
}
(Contact local supervisors and engineering personnel for specific details ard concurrence prict to initial discussion with Criticality Safety per-i sonnel.)
I (2) Prepare Request for Criticality Centrol Review / Approval /[uthorization j
(Form NCS-1), Items I, II and III. Use sketch (Form NCS-1A), or other supplements where appropriate.
(3) Obtain signature approval cf the appropriate area Criticality Control Coordinator; (1ter. IV of Form NSC-1).
j Assigned heas of Coerdinators are:
Criticality Control Assigned Areas of l
Coordinator Resconsibility Producticn Manacer 3
Shop I Bldg. B (ent' ire) & western portion of Bldg. A l
,as bounded approsdmately by Columns B-24, F-24, F-22, J-22, 7-18, X-18 & asscciated yard operations Shop II Easterly pcrtion of Bldg. A as bounded by I
above columns plus Bldg. M (entire) &
associated yard operations.
Shop III & IV East Building and annexes (entire) ard 3
l associated yard operations.
}
(4)
Forward the completed request (Form NCS-1) to the Criticality Safety l
Section.
(5) Preride :dditica:1 irtfo.c3 noc:3, sap / to,ascist in review ned resolution of the reque'sf and issde o!' approval or criticality control authori=ation (see i-O for example, Criticality Control Authorizatten form).
i i
CRITICALITY CONTROL REQUEST NCS-1 7_1-85 I.
Originator Date Date Needed Subject of Request II.
Brief description of proposed fuel or fuel look-alike handling or storage.
Include a description of the fuel form, the operation to be performed, and provide appropriate fixture or layout drawings. Also reference any special procedures which will apply, s
III. Desired criticality limits / controls i
Signature of Shop Manager of area concerned NCS SECTION ONLY IV.
CCR No.
Date Rec'd.
p Ref:
Nucl. Alarm Coverage: Yes No b
Basis for approval, including references and necessary controls.
J mrs osn. concEnss Action
_subinet kee'd.
Met kee'd.
Comoteted HP.Ehr.
1s.In,rr, Heenth Medical wrs MGE:
Lisense Reviewers Checked By:
Deslan Installation and zones verified by:
[r!*1' Date 3.r.,,,,4.
_ Phys. Prot.
usnec i
i
SKITCM S UP P.I::I::: 70 NCS Te n N h
v P a c e., c.
3,
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" CRillCAulY CONIMUL "
NIS AUTHORIZATION NUMBER:
REV(DATE):
SUBJECT:
EQUIPMENT / TOOL:
AREA:
REFERENCES:
CAUTION: The processing of fuel items under tNs Authorization is prohnited unless the Authorization is posted in a visually occessible location.
i
'O
]
- (
I j
t APPROYA!. BLOCK INFORMATION CATEGORY 3
UNCLASSIRED I
NIS:
i AUTHORIZED CLASSirlER DATE 2
This authorization erpires cutomatically on changes in equ'pment, locction, materials, or if limit and controls do net reflect werk eperations being performed.
l
M:
.f]
fict:
twas, ttc.rsa uc I,omin. Sam Deanter k
tGIE & S#E1Y v!Q1,T101 m LFC/E MCSE - !tr. Cn:7.
H. PWsics tre. Sam _ One TATE & Occ R E E rGIE to. #0 DAE 7 ISSJ i
E GID BY:
TITII MR'D G D!SQSSIGI:
l 1.'fGIATE Kil0174St:
Wie.ta 3 tarkisq days !.se the data of this redme. the SW of tra arme er operaticsi enregreat La to forterd a tettsan anster to tre IC5 Depar-mest, tenager assauusar intcreatim specified belos. Armor La in he endorsed ty a hipint.*swal of depagt:!st agervLaim er nur the Pseiksticra Dep Manager /Mticality Cent:31 Area Canttinator.
IO: a"AMAGG, tit $ MAantvr FiD'a CATE:
rRY T0 tG12 7 SkTiY v! QED m trENE P0ELPE ET!OW. C;P.oECIM KTIci (!F #f0:
Amelv be *.regiv. g tot *.w t.ede W &Attiale Mesen, eacn udav".d al listad belos somniedoes Me bekrg ' ** ud of tsa *r.alataan at useafe procedure j
and MS 'EderstandL/q arul pue#4reee af MJ fTegurJaatl&ty to pre %wt te=Cr?.T;engg,
- ,-e aealise.rsn f m
)
J
% of Acy ws cesar P q.ast Aseeezated wte. ha Ar.4sn
- sta Carotete er is H ccrsaetse j
leer Ases Pre e ste c.co warmour
._____ _-~__
r I
i UNC NAVAL PRODUCTS
()
License SNM-368 Chapter 12 Page 12-1 Date: 1/22/86 f
Docket No.70-371 Rev.0 CHAPTER 12 RADIATION PROTECTION I
j 12.1 Program p
i It is the policy of UNC Naval Products to avoid any unnecessary
{
radiation exposure; to prevent the entry of radioactive
{
material into the body; and to contain contamination within controlled areas.
i j
In order to adhere to this policy, considerable time and effort is expended not only by the Nuclear and Industrial Safety j
Department, but also by the Equipment Engineering and Plant Facilities Departments in an overall program to eliminate or I
j lessen the potential exposure. These efforts and equipment are j
clearly visible to all who frequent the controlled areas. Among j
the monitoring programs and administrative controls are the familiar surface contamination checks, air samplin,g, and hand i
monitoring upon exiting. The possibility of internal' contamination of personnel working with radionuclides is minimized by enclosing processes, use of local exhaust ventilation, and maintaining environmental contamination at a low level. Surveys of surfaces and airborne contamination are l
made to confirm that necessary standards of contamination control are being met.
1
{
The elements followed to accomplish this overall policy are discussed in the following sections.
i i
12.2 Postina and Labelina I
Radia*. ion areas are posted as required by 10 CTR 20.203(b). The only radiation areas that are in the facilities are associated I
with the use of sealed' sources used in nondestructive testing i
j by Quality Control.
i l
The entrance to B-South is posted as required by 10 CFR I
20.203 (d) (2).
i
}
Within B-South, entrances to controlled areas are posted with j>
magenta and yellow " CAUTION-CONTROLLED AREA" signs bearing the radiation symbol. Similarly the entrances to limited control I
areas are posted with magenta and yellow " CAUTION-LIMITED j
CONTROL AREA" signs bearing the radiation symbol.
Normal entrances to the plant are posted as required by 10 CFR 20.203 (a).
e
[]}
Page 12-1 4
i
l UNC NAVAL PRODUCTS License SNM-368 Chapter 12 Page 12-2 Date: 1/22/86 i
/~T Docket No.70-371 Rev.0 1 Q Labeling of containers is generally performed as required by 10 CFR 20.203 (f) but may be supplemented by a sign posted at B-South entrances bearing a generic statement: " Caution Radioactive Materials - Any Container Within This Area May contain Radioactive Materials". The sign shall include the standard radiation symbol.
12.3 External Radiation - Personnel Monitorina All employees wear a TLD (Thermo-luminescent dosimeter),
l visitors and subcontractors going to certain designated plant i
manufacturing areas also are issued TLDs.
l l
The TLDs are read out by a vendor (currently Teledyne-Isotopes, l
Inc.) annually for employees and approximately quarterly for visitors / subcontractors and terminating employees.
As noted in paragraph 3.2.5.1.e, certain personnel are also supplied film badges which are processed monthly by a vendor (currently R.S. Landauer, Inc.).
Ring, wrist, or other special located film badges are used in i
l specific evaluations of handling, work, or inspection
(}
operations.
As noted in paragraph 3.2.5.1.e, p+; lodic gamma /x-ray facility l
surveys are conducted to detect potential personnel exposure situations due to materials in process or storage, and NDT inspection equipment and operations.
Paragraph 3.2.4.2 presents technical information on the dosimeters.
l Results of the program are evaluated for potential ALARA considerations.
12.4 Radiation surveys - Maintenance oeerations.
l Most all maintenance operations involving exposure to I
radioactive materials have been performed for a number of years and are well documented with respect to exposure. New operations are evaluated by Health Physics personnel for possible problems prior to performance. Protective equipment (see attached Health Physics Special Work Permit Form, Figure 12.4) is conservatively specified for new operations until exposure information is collected. Radiation exposure measurements may be made during the maintenance work l
operations.
()
Page 12-2 i
8
UnC NAVAL PRODUCTS 6
Health Physics Special Work Pennit l
Jinator Name Work P,ennit No.
c Maintenance Service Order No.
I C Engineering i
o Production /QC Date o Labs Part I To be completed by Originator of Attached Service Order (1)WorkLocation(BeSpecific)
(2) Description of Problem or Job (3) Will outside Contractor be involved No Yes j
Name of contractor j
Part II To be completed by Maintenance or Engineering lt 1
(1) Scope of specific Repair / Work to be Done (describe in sufficient detail to permit Health Physics evaluation of proposed work)
~
{
i Q (2) Scheduled Starting Date and Shift Estimated Time Required j
.(3) Signature for Maintenance or Engineering 1
i Part III To be Completed by Health Physics j
(1) Advance Notice of Health Physics Required Before Starting This Job. Yes No (2)BioassaySampleRequired:
Before Starting Job-Yes No Af ter Work Complete-Yes.,,,,,No,,,,
i (3)ProtectiveEquipmentRequired i
I r
Coveralls Gloves Shoe Covers Lab Coat R'espirator i
f Cuff Taping Head Cover
'Other I
(4) Special Health Physics Monitoring Required No Yes l
(NOTE: Self-Monitoring Required When Exiting)
(5) Precautions /Special Instructicas j
(6) Signature of Understanding Required
- Not, Required i
- To be signeo oy people coing worx, E UNC representattve for Joo.
l HEALTH PHYSICS USE Job completed on Cross Reference Recorcs Retention for Health Physics i
Bioassay Yes. No I
Lapel Sample Yes. No Process Air sample fes. No Rev.0 Names of Personnel involved in horK Date:1/22/M
}
FIGURE 12.4 E'
l
UNC NAVAL PRODUCTS License SNM-368 Chapter 12 Page 12-4 Date: 1/22/86
\\
Docket No.70-371 Rev.0 12.5 ReDorts and Records - Radiation Protection r
i
.. e Records & ReDorts Reference Retention Period (Paragraph)
Health Physics 3.1.2 24 Mos.
(Special Work Permit) 12.4 r
Abnormal Incid'ents 2.8 12 Mos.
r i
Change Requests 2.6 Operation Shutdown +
11.6 6 Mos.
f Inspections & Audits 2.7 24 Mos.
I HP Instrument Calibrations 3.2.4 12 Mos.
1 ALARA Report 3.1.1 24 Mos.
'e 24 Mos.
Indoctrination 2.5.2
/
Employee Re-orientation 2.5.3
/
12 Mos.
l
~
Personnel Exposure Film Badges 3.2.5 NRC Approv.
TLDs 12.3 24 Mos.
Whole body count 3.2.7.3 NRC Approv.
i i
Urine Sampling 3.2.7.1 NRC Approv.-
c Work Station Air Samples 3.2.3 24 Mos.
j
)
Removable Contamination 3.2.6 24 Mos.
Surveys 12.6 Instruments Instruments used and quantities normally available are listed i
in paragraph 3.2.4.2. Selection criteria used were range, sensitivity, ease of use, ruggedness and durability and l
experienced judgement of professional' personnel.
l Page 12-4 I
UNC NAVAL PRODUCTS License SNM-368 Chapter 12 Page 12-5 Date: 1/22/86 O
Docket No.70-371 Rev.0 on-site maintenance capability is maintained. On-site calibration is performed as needed except for the high level emergency survey meters which are calibrated at State facilities.
2 The Health Physics laboratory is a 400 ft air conditioned area further subdivided into three work areas: a general clean room housing bench radiometric counting instrumentation, instrument cabinets and office space; a room for potentially contaminated items with laboratory hood, sink, and support equipment; and an' environmental analysis area with independent hood, sink, and support equipment. Separated from the lab, but adjacent, is an additional 300 square foot area available for equipment storage, records, and radioactive source storage. A large area outside the office can be completely isolated when.
needed for use during instrument calibration.
12.7 Protective Clothina Individuals conducting work in the sectioning area are issued complete company clothing. Individuals conductine work involving the potential for high surface contamination levels (such as filter changes, maintenance repairs, and cleanouts) are issued special work permits which evaluate the job and then O
specify proper protective clothing (e.g. coveralls, lab coats, gloves, shoe covers, head covers, cuff taping, respirator). In these cases, the protective clothing is not reworn and is either discarded to burial or placed in the nuclear laundry.
The respirator is appropriately cleaned.
Normal work operations conducted in other controlled areas are under process, engineering, and health physics contamination control such that loose contamination, if present, is not of sufficient quantity to present an ingestion or inhalation hazard via transfer to protective clothing followed by subsequent resuspension during removal.
Emergency fire protection clothing and SCBA breathing apparatus is maintained for use when needed.
l l
{}
Page 12-5 i
UNC NAVAL PRODUCTS-It License SNM-368 Chapter 12 Page 12-6 Date: 1/22/86 Docket No.70-371 Rev.0 12'.8 Administrative control Limits,
_~
12.8.1 Occucational Execsure (internal & external)
Informaci~on has previously been presented in paragraphs 3.2.5 and 12.3.
12.8.2' Airborne Activity (area and stack or vent monitors)
Informatihnhaspreviouslybeenpresentedinparagraphs3.2.3, 5.1.1, and 10.3.
An always-in-operation r.ir sampling network covers all process areas and consists of open-face filter paper sample heads manifolded..to a central vacuum system with backup vacuum pump.
]
i Approximataly seventy air stations are on line at any one time i
with a capability of selectively running an additional thirty for change-in-operation evaluation as necessary. These stations are a mix of breathing zone, general room air, andyprocess air samplers. (A process air sampler at this facility is'ene which' monitors an operation but is not close enough to the operator to be considered a BZ sampler.).
Q Monitoring and sampling locations are selected by considering i
i the quantity of radioactive materials in the production and Q.C. process, the potential for release of radioactive i
materials into the working environment, and the proximity of r'adioactive material to the worker.
The potential for airborne radioactive materia shall be determined by,an in-depth review of.the qdantities of uranium, the surface contamination results, the equipment and the process avafuated for ths. degree of contamination confinement.
This evaluation, when mada shall be in writing.
g 12.8.3..Licuid Activity (effluent monitors) l Information has previcusly been presented in paragraphs 5.1.2 and 10.4.1.
([)
Page 12-6 i
.mu,
4 UNC NAVAL PRODUCTS
()
License SNM-368 Chapter 12 Page 12-7 Date: -1/22/86 Docket No.70-371 Rev.0 i
12.8.4 Surface contamination (work areas, release of equipment or packages, skin contamination) 4 j
Information has previously been presented in paragraphs 3.2.6, 6.4, and 10.4.2.
4 Currently enforced administrative control levels for surface contamination, personn<.1 release, protective clothing, and i
salvageable scrap are presented in Table 12.8.4.
12.8.5 Effluent Discharaes Sampling methods, sampling frequency, analyses, limits of detection,and instrument calibration and testing have been i
previously presented in paragraphs 5.1.1, 5.1.2, 10.4.1,and 3.2.4.2. Table 12.8.5 summarizes the affluent monitoring program.
f 12.8.5.1 Gaseous Effluents
~
There are 15 exhaust stacks from UNC Naval Products with i
fs potential for radioactive gaseous emissions. These stacks are listed in Table 12.8.5.1 and their relative locations are shown in the plan view on Fig. 12.8.5.1 Exhausts from operations that could potentially produce radioactive effluents have HEPA filters and/or gas scrubbers.
The HEPA filters have an efficiency of 99.95% for removal of particles 2 0.3 micron in diameter. The detection limit for gross alpha is 2.2 x 10-14 micro Ci/cc.
d G
t Page 12-7
UNC NAVAL PRODUCTS Chapter 12 Page 12-8 Date: 1/22/86 O
License SNM-368 Rev. O Administrative Control for Surface Contamination Table 12.8.4 Direct Survey Smear Survey
. Unrestricted Areas c/m Probe Area d/m/100 cm2 CLEAN Facility & Equipment 150*
30*
Surfaces, Personal effects, and shipment packages and vehicles
. Restricted Areas Limited Control 1,500 100*
Exposed Work Surfaces only; all others, same as clean Controlled A.
Production Zones (1) Floors & Work Surfaces 10,000 300*
(2) Desks & Table
' Tops used for clerical purposes 1,500 100*
8.
All Other Surfaces (1) Floors & Exposed Surfaces 3,000 300*
(2) Desks, Benches &
Lockers 1,500 100*
1 O
Page 12-8 4
j
= UNC NAVAL PRODUCTS O
License SNM-368 Chapter 12 Page 12-9 Date:1/22/86 Docket No.70-371 Rev. O Table 12.8.4 (Continued)
Direct Survey Smear Survey c/m/ probe area d/m/100 cm4 l
C.
Personnel Release Skin and/or Hair after washing 0*
10 l
Personal clothing worn outside restricted areas 100 30 j
D.
Protective Clothing l
Protective clothing worn only in controlled areas 500 150
)
E.
Salvageable Scrao For re-rr,it (junk metal)
'5,000 500 Reuse or Salvage 1,500 100 4
i
- Authorization for higher values requires written approval by the Manager, Nuclear and Industrial Safety Services or the Health Physics Specialist.
l 4
4 k
O Page 12-9
,~r
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e r
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i O
O O
Jl Table 12.8.5 Operation of the radiological effluent monitoring program Sample Number of Collection Analysis Analysis 2
medium Samples frequency frequency parameters taken Air effuents Air i
Stacks Particulates 15 Continuous Varies from Gross alpha 1-4 days i
Liquid effluents Rad waste Water 1
Continuous Daily and Gross alpha per batch monthly release coinposite 4
}
l I
Pagel2-10 Hev. 0 Date: 1/22/86 i
i
. l
UNC NAVAL PRODUCTS
(
License SNM-368 Chapter 12 Page 12-11 Date: 1/22/86 Docket No.70-371 Rev.0 Table 12.8.5.1 Stacks evaluated as cessible sources of emissions" Equivalent Exhaust Stack diameter Height rate Function 3
(m)
(m)
(m / min) 1 1.64 0
299 Chem Laboratory 2
0.73 6.7 142 Met Laboratory 3
0.54 7.0 59.5 Met Lab Hoods 4
0.59 0.61 32.6 Fuel Vault 5
0.64 4.3 62.3 Unit 2 Facility 6
0.68 0.76 80.7 Unit 1 Facility 7
0.82 0.76 119 Decontamination Area 8-1 0.59 0.61 28.3 UnitI1, Clean Room 8-2 0.59 0.61 27.6 Unit 2, Clean Room 13 0.77 0.61 26.7 Unit 1, Change Room 16 0.25 0.61 26.7 Unit.2, Change Room
{ss'} 28 0.64 0
68.0 Health Physics Lab i
29 1.18 0
136 Radioactive Waste Area 30 0.77 0.61 27.6 Assembly Area 46 0.91 0.61 143 Sectioning
- All stacks are vertical except stacks nos. 28 and 29, which are horizontal.
BLDG 8 13 4
30
' 6 ' 5 16 2.
3 g
46 8.i
- 28,,29 8-2
.7 Fig. 12.8.5.1 Plan view of exhaust stack locations.
Page 12-11
UNC NAVAL PRODUCTS O-License SNM-368 Chapter 12 Page 12-12 Date: 1/22/86 Docket No.70-371 Rev.0 12.8.5.2 Licuid Effluents All liquids that potentially could contain uranium (the only radioactive material processed at the UNC facility) are piped to collecting tanks in Building B. The liquids from process operations expected to contribute uranium waste are centrifuged and filtered to remove uranium solids before transfer to a (2500-gal) detention tank for sampling. Liquids from change-room showers and the chemical laboratory that could potentially contain uranium are filtered into a separate retention tank for sampling. Six (2500-gal) retention tanks are available, with transfe-possible between tanks. Depending on analytical results, the liquids may be given further filtration or passed through an ion exchange column until the uranium concentration is below 10 CFR Part 20 requirements for unrestricted release. The limit of detection is 1 X 10-12 micro Ci/ml The pH is then adjusted and the liquid discharged into the sanitary system..
~
12.8.5.3 Recortina Resconsibilities Health Physics Technicians collect the samples, perform the measurements, determine acceptability, and perform the
(])
discharge (in the case of the liquids). Any deviations are brought to the attention of the Health Physics Specialist and-the Manager, NIS for investigation and action as required.
Limits and actions have been presented in prior license sections.
Chapter 13 presents methods and results of evaluations to EPA 4
requirements.
l 12.9 Reseiratorv Protection Procram Whenever respiratory protection equipment is used in accordance with Chapter 3.2.8, it shall be used within the program described herein.
Protection factors, if used, shall be as defined in the latest copy of Protection Factors for Respirators as listed in Appendix A of 10 CFR 20.
12.10 occucational Extosure Analysis An analysis of occupational exposure (external and internal) and monthly average airborne concentration of radioactivity covering 1981 and 1982 plant operations at all process / work areas in the exposed fuel areas of the facility is presented below.In addition, derived air concentrations for the
()
sectioning, decon, scrap vault and fuel vault during 1983 and Page 12-12
DocketLicsnes SNM-368 NAVAL k
s UNC No.70-371 PRODUCTS 3
()
1984 are pres Chapter 12 Pag continuing ev luatented. These Rev.e 12-13 areas as a
0 ion areas Date:
. differ substantially frwell as the p. The 1/22/86 are identified as av roductionerage Internal airborne w ll below 10important pathdeposition om the 1981 andand lab areas (not areas under e
of uranium throu h 1982 w y of o a
data.
presented) dor these rem / year. secondary concer CFR 20 limitsccupational exposuinhalation is th g
not
- n. Maximum )x. External radiati re in this plant (th 12 10 1 e ternal e most External doses on are less thatexposure is ough UNC fabricateuranium (enriched iExposure Ev luati Nav l a
of Products a
05 uses on n the Uunirradiated, gov a health physicsand assembled withreactor fuel eleme 235 isotope to ernment-fdrnishedgreate radiation is the l other nts exposureattenuate themitigated by multiplconsidera is compo ow core which are to energy 186 keVthe primary sou a
configuration.aded radiation.e layers upgr acc stays below that lThus the of zirconiumgamma from U ordance rce 235.'Thisof external From with 10 UNC currently o 7
ev l which mustcumulativ CFR radiation tome'tal'which A
e 4
20,202 regulati e
c(;1ain frr'4ation producina film badge progrperates tw be e to c4 am (monthlo independent r monitored in orkers ons.
w g
employees.uel ge handlers;quipment, y exchange)adiation dosim e4 and a TLDhandling calibrat for 12 10 1 andThe TLD results workers eter programs program (yearly esourcoperating ion 12 10.2. Tablesfor the past nonthly film badg
~
fiv xchange)es 1adga data d and 12 10e years for e date for the pa.3 and geviously repor are all a
oes not 4
2rtain producti differ o years.4 summarize thesumma 12 10 ted. The st tw Lemants from in control and produsubstantially fr on categories ements to proc e
.This om of highest exposusummary dataexternal mensional correcti remov ess minor storage to e
film gg ction personnel wh
~
scratches / burrs w
re tramity exp ons.
ork stations, represent who hando hand carry g TLD's and wrist badgesosure has been
, and who remity exposure i make ev luated minorfinish
.toring.
a s below theon different occafor these (g
idition, film bad op g
action lev l sions.erations, using heoratical w2 inches for 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> c'
for fullResults indicat e
ges hav time e been po sbulated in Table 1orst case,exposur160 hours,sitioned at cont e
s and 4
ity doses 2 10 5.-
es from 480 hours0.00556 days <br />0.133 hours <br />7.936508e-4 weeks <br />1.8264e-4 months <br /> act, 9,
(S i ard can be to 6 inches bsthe amount ofestimated based o a fuel elem,ent ev luate,
a
. Re time sults spent handling thi n the e
mass is of material
)
Page 12-13
"~
s material,
TABLE 12.10.2 Man-Rem Dose - UNC Naval Products Averace Individual Average Persons No. of Persons Total Dose Per Person Dose Per Year Badged With Measurable Exposure Man-Rems Group (Rems)
' Individual 1980 1209 616 29.57
.048
.024 1981 1230 366 17.64
.048
.014 1982 1265 216 11.15
'.052
'.009 1983 1382 448 24.45
.054
.018 1984 1587 495 29.37
.059
.018 N
l REV.0 Date: 1/22/86 O
Page 12-15
UNC Naval Products License SNM 368 Chapter 12 Page 12-16 Date: 1/22/86 Rev 0 O
Table 12.10.3 Suggested Draft Format For the Reporting of Recorded Personnel Whole Body Exposure For Calander Year 1983 Licensee Reporttag (hane & Address) setC License ne(s).
UNC Naval Pro' ducts 67 Sandy Cesert Road 51 6 368 Docket 70-371 Uncasv111e, Ct. C6332 06-06884-01
- r stasonntt matroatnc was not stoutato cuataG Tut itAa, catcz Tuts son.
- oTMitut$C coPFLtit fut FoLLoWinG TA4LE:
Annual note Sody oose phaber of Indtsteuals tanges * (Re951 in fact Range no Nasuraete (sonsure 86 Measuraele (noosure tess thaa o.tCo 24 c.100 -- o.250 2
o.tso - e.500 1
o.soo - o.7so 0
o.?so. t.os:
4 1.000 - 2.000 0
i 7.000 -- 3.000 0
3.000 -- 4.000 0
4.000 -- s.000 o
, s.ooo L s.ooo 0
6.000 - 7.000 0
7.000 - e.oco 0
8.000 - 9.000 g
9.000 - 1o.000 0
1 1c.oco -- i.o00 0-11.000 -- 12.000 0
> 12.000 0
Total nuncer of Individuals reported 113 The aeove infomation is sweef tted for the total numeer of Individuals for wnon personnel monitortag was (cnect one):
reoutred under la CFR 20.?o2(a) of to CFR 34.33(a) during the calendar year.
Provided ouring the calendar year.
'Indlvtoual values esaCLIF eCual to the values se94 rating gaDosure ranges shall be reported in :ne htgser range.
i l
Page 12-16
NC Naval Products License SNM 368 Chapter 12 Page 12 Date: 1/22/86 i
Rev 0 Table 12.10.4 Suggested Draft Format For the Reporting of Rec'orded Personnel Whole Body Exposure For Calander Year 1984 tscensee am etia,tas.e s aderessi neC Licease ae(s).
UNC Naval Products 67 Sandy Desert Road SNti-368. Docket 70-371 Uncasv111e. CT 06382 06-06884-01 O outiaG Tut vt.catroetnG was not atoutato tF peasonntL e A. C W CK Tuts son.
ofdeutst. Corept(TC TMC FollowthG fASLC:
I amau 1 Whete. Be.er,sse shamee,r.of Instelev.ts o
ees.-
a....aee
..e...c.eie c....re 62 me.sve.ete (spesure tess th.a o. loo go
- o. loo -- c.7so 5
O o.2so -- o.soo o.soo -- o.rso 0
o.rso -- i.ooo 0
t.000 -- r. coo O
O
- r. coo -- 3.000 0
J.000.. 000 0
. 000 - 5.00o 0
s.oco -- 4.000 0
4.000 -- 7.000 0
7.000 - s.ooo O
s.ooo.. s. coa 0
s.ooo -- 1o.000 0
to. coo -- 11.000 0
ll.0)o -- 12.000 0
>tr. coo 0-fot.l seer of ladtview.ls reported 126 fne.eeve taform.tten is svesittee for the tot.l assueer of laelvleu.ls for.aos perse net asaltertag..s (enect ene):
i 0 reevired under to CFR 2o.2C2(.) of to CF4 34.33(.) evetag the calead.c
~
re..
g,re.ie,e.,ia,tue c.ie..,,;.,.
. tad...e..i..i.es e.x ti, ee..: t tne..i.es m.,.t a, e.ees.,e
..,es in.n ee reported in tae ntgaer rea,e.
1 Page 12-17 n.
-.-,n m.,
..n.
+
e
-or, w-
.~R 1-.
.. I - - - -
F.-l er :,.
i O,.".',.,, 2 f 2 S
1 3 atAus es00 esv
.a l
Uh3TED NUCL E A6a CORP 2924 SPECIAL J62S2 809776'
~--
was nepeeschTArave R. S. Landauer. h. & Co.
us.CAsv Loc cf 032 o - -' ' - * = op- ** ~ ~e e aa e ~~
RADIATION Table 12.10.5 DOSIMETRY
********".n""n' c....
o.
[. j^""-
D 62
_ REPORT.
s a ew oin'n ***
Pse e93 - 2tso
.T---------,,,,,,,,,,,,,,,,,,,,,, '.,,,.---*~~'~,-';~;~.
1.
., t
..<. u..-. '.
1 T,=.,,' ', I,
--.=, I;!....
f P..: 1t.~' : :*
e....a se........u 3.
8 l'39. ;..
.**-s***aa*"~****...e*.**.
- y
'.~../
O
~{j
'fi
,_.. Fa%,%,'
}.f' ~ ~' ~.."
""-" a POR EMPOSUAE s%hD 04/30/TT
?
l l 00000 CONTp0L 1
M 4
NI l N0 TOT AL.
120p contact 320 lu ;
l p.0 TOT AL '
9900s' Ga t
i j i
99002 G't 320_
J20 :M NOTCTAL 480 hrs.
'n' s0y. 6" 30[
l i
FOTOTAL lj:
99003 l
99004 Working I
4 50 i
50 NOTOTAt l
885 calendar Gj8l 20g12a NOTOT Aa. [ j j
[
20 at 2 a-20 NO W AL 99004 quarter NOTOTALll f
9900T 1
9 90 M) 99006 Gl 12 0<
120.M, NCTOTAL 9900s 160 hrs.
48 2*T 6a 20 I
kom AL 99080 G't.
- : e a
990!!
Working I
h0T OT at. '
j l l
month l
ai m;
NO TOT A4.,
990:2 3c )
30 NOTOT AL. '
g3 990:3 30 1 contact I
8* ! '
"" * '*- 1 8 99084 990:s.
40 hrs.
ci
=*
NO T O T A4.
- I a
"8 Egij$','
990:e' Working g
mS aj l' l
I N0' C T **-
j g'
al-12" 990:T Week llg 9908e waycyat 99019 g(e 8 m.
NOTOT AL l
g 9902G g M
NOTCTAL.
l
- l t
i I
i i
I I
I i i i
.4 i i l
i I
l l
l a
em e oe e er "O o'
e e
ee e e 'ee e'e e
!!5:.=. ~;b---
" - - - - - - - ~ - - - - - -
e e
??!.7. "!c."4'"!.:..-.c
. is :nw,: !:7 ir m..v=v. sci-- :- - -
Page 12-18 Rev. 0 Date: 1/22/86 i
UNC NAVAL PRODUCTS License SNM-368 Chapter 12 Page 12-19 Date: 1/22/86 O
Docket No.70-371 Rev.0 12.10.2 Internal Radiation Evaluation The fabrication of fuel elements for internal radiation protection j
purposes can be grouped into two categories - working with exposed fuel or working with encapsulated fuel. The latter category cannot contribute to internal radiation exposure under ordinary production operations, and therefore from an ALARA evaluation need not be discussed in this section. Exposed fuel (unencapsulated) operations are confined to a controlled portion of one building which is i
referred to as B-South. Within this area, process operations occur such as fuel forming, weighing, measuring, X-ray, and assembling with zirconium components, as well as support operations such as i
metallurgical preparation and examination, chemical analyses, sectioning of components, rad waste disposal, and decontamination.
Table 12.10.6 identifies these areas and operations.
- a. Air Samole Data Analvsis
~
Air sampling data for 1981 and 1982 is presented in Table 12.10.7 and Table 12.10.8. All process areas in which airborne radioactive material exists have concentrations which are less than 25 percent of the amounts specified in 10 CFR Part 20 for the number of hours
\\
in any week during which individuals are in the area. Table 12.10.9 shows 1983 and 1984 data for those areas under continuing ALARA evaluati,on (i.e., Sectioning, Decon, Vaults).
Air concentrations are reported in units of microcuries (micro Ci) of activity per mililiter (ml) of air. However, in order to minimize mathematical errors, we have found it more convenient to work with whole numbers and therefore express radioactive airborne concentrations in units of disintegrations per minute (DPM) per cubic meter of air. Table 12.10.7 and 12.10.8 are Average Airborne Concentrations reported in dpm/m3 units. Any number as dpm/m3 is directly convertible into micro Ci/ml by multiplying by the factor 4.50 x 10-13. We use 220 dpm/m3 as the 10 CRF 20, Appendix B, Table 1,
Column 1 value.
UNC NAVAL CONVERSION APPENDIX B PRODUCTS X
FACTOR TABLE 1 VALUE
=
dpm/m3 (micro Ci/ml) l U235 220 X
4.50 x 10-13 1 x 10-10
=
Page 12-19
O O
O B-SOUTil AREAS AND OPERATIONS Table 12.10.6 PROCESS NUMBER NUMBER OF j
AREA MACilINES/0PERATIONS OF PEOPLE SillFTS Polishing wheels, Met. Lab belt sanders, sur-5-6 1
All wet operations Sample Prep.
face grinding 1
Chem. Lab.
Weighing, chem 8
1 Hood exhausts. Some bench work.
analyses Fuel testing, Spec. Lab.
emission spectro-3 1
Enclosed operations gph, neutron assay-X-ray, fuel measur-Unit I Q.C.
ing, storage 6
1 Process exhausts Unit I Fuel forming, Production fuel weighing 7
1 Glove boxes Pack Fuel assembling, J
1 Clean room conditions i
Assembly weld Cut off wheels, Sectioning Shear, Milling 2
1 Process exhausts Trash compacting, Adjacent to sectioning Decon Decon 3
1
()oor open most of time Unit 2*
Fuel forming and 8-12, 1-3 Process modifications glove boxes weighino fuel Vault Fuel Storage, 2-3 1
Glove box Fuel Weighing Scrap Vault Fuel Storage Piece Counting 4
1
- When operating Rev. 0 Date: 1/22/86 Page 12-20 J
m m
y T
y
Table 12.10.7 OERIVE0 AIR CONCENTRATION (dpm) (Meter-3) 1981 1981 MET LAB CHEM LAB SPEC LAB UNIT 1 Q.C.
JANUARY
- 81
.51
.3d 60 FEBRUARY
.94
.16
.32
.89 MARCH 3.51
.35 2.19 1.49 APRIL 1.6d
.3 1.71 1 17 MAY 1.28 42 1.13 1.33 JUNE
.93
.27
.65
.88 JULY
.79
.28
.84 1.01 AuousT 1.31 43 43
.1c SEPTEMBER 42
.11
.$2
.66 OCTOBER
.97
.35
.61 1.7 NOVEMBER
' 1.04
.48 1.18 1.53 DECEMBER
,78
.14
.6$
1.?
TOTAL UNIT 1 DECON connnrrinN PACK ASSEMBLY SECTIONING -
JANUARY
.57
.11 9.77 1.57 FEBRUARY
.56
.17 5.87 1.PA MARCH
.97
.3 27.16 7.63
()
APRIL
.67
.35 11.00 d d4 MAY 1.8
.51 7.19 3.82 JUNE
.37 43 6.51 3.R6 JULY
.57
.36 6.43 3.93 AuousT
.26
.1 4.22 2.02 SEPTEMBER
,61
.22 d,97 7.1 OCTOBER
.92
.37 5.21 2.73 NOVEMBER 1.08
.26 5.74 9.9A DECEMBER
.8
.19 5.26 2.54 TOTAL PR0bbbIbN UNIT 2 0.C.
FUEL VAULT SC9AP VAULT JANUARY
.16
.14 2.d4 1.57 FEBRUARY
.12
.23 1.41 1.29 MARCH
.22
.2 21.9 11.92 APRIL
.14
.14 d.14 3.01 MAY
.28
.3 a 71 6.07 JUNE
.31
.31
~
3.65 7.56 -
JULY
.07
.08 4.11 6.01 AuouST
.12
.16 1.33 2.66 SEPTEMBER
.48
.07 2.54 2.6
()
OCTOBER
.37
.17 3.38 3.13 NOVEMBER
.2
.16 1.93 d.16 DECEMBER
,1p
,ng
?,0 d.A1 TOTAL l
Accendix 3 T=ble 1 Column 1 #oe U 235= 1 x 10-10 o Ci /mi =?ondem/m3 e.
n.
n n....
4 me,nc
Table 12.10.8 DERIVED AIR CONCENTRATION (dpm) (Meter-3) 1982 MET LAB CHEM LAB SPEC LAB UNIT 1 0.C.
JANUARY 1,n6
.12
---_l. 2 d
.60 FEBRUARY 2.1
.18 2.28
.66 MARCH 1.25
.2 1.da 1.17 APRIL 2.51
.1
.29
.65 MAY
.76
.21
.82 4.01 JUNE
.63
.15 1 57
? da Jucr
.3
.17
.25 1.11 AuoUST 1.89
.24
.52
.79 SEPTEMBER 1.1
.13
.81 1.67 OCTOBER
.7
.??
09 1 na NOVEMBER
.77
.2
,89
.77 DECEMBER 1.58
.33
.73
- 7A TOTAL UNIT 1 connurTinN PACK ASSEMBLY SECTIONING npeny JANUARY
.64
.19 3.72 47 FEBRUARY
.46
.19 6.32 7 AG j
MARCH 1.28
.14 7.75 2.81 APRIL
.94
.09 4.1 1.7?
MAY
.99
.??
1.67 1 a?
JUNE 1.08
.17 6.1R 1 o JULY 48
.09 3.17 1 19 AUoUST
.62
.13 7.29 7 d6 SEPTEMBER
.94
.09 6.55
?.3d OCTOBER 1.29
.17 R.76 6 17 NOVEMBER
,67
.19 7.1R
?_7A DECEMBER 1.01 1.1 7.33 i
1.61 TOTAL l
l UNIT 2 UNIT 2 n_r_
PRODUCTION FUEL VautT
<rono vom 7 JANUARY
,14 l
.og 1_gg 12.4 FEBRUARY
.07 I
.11 a.04 5.61 MARCH
.01
.03 1.76 4.47 APRIL
.01
.02
.57 0.11 MAY
.04
.03 1.0 12.5 JUNE
.02
.02 1.6 1.51 JULY
.01
.02
.64 5.91 AuouST
.01
.03 1.26 3.88 SEPTEMBER 0.076 2.55 1 0
( i OCTOBER 0.20 2.43 2.93 NOVEMBER 0.408 2.41 2.82 DECEM BER 0.449 1.86 3.7 TOTAL l l
O. O C Table 12.10.9 DEP I VE b AIR f DIILEIIT2/)T~thil5 [ bnc )
- i 56cT;eginc,.
Fuel V/lu t.T D C C, e N 5 C /E /l f * / 9 E.b AF OI DAC R c o'M, 04C Roe M D/lc V /1tJ L 7. BAC JANUARY ),{
- 2. 3 N
- jz"I N FEBRUARY
(,, $' (3 / /, l/ 2d ) 2.b 2,b )
- f. Y
_jo g / ]y ~/ MARCn ,,1 3.C / __f. o ' APRIL [,O N Q,} N 2.l N _ 1, O N MAY f ) I. } _ _) l ) J. 2 2_. 3 2.i Q,7 ) ls[ JUNE _ /,3 _/. ] 4.2. j _, 7 ' JULY la s 0.3 x 1, 3 N
- i. O x AUGUST 1, af
) 2,6 J,(, #) /.2, ~{. A > 2. f L6 > 3.9 / SEPTEMBER _M j,, 3 3.f _3. U OCTOBER Y,O 3 NOVE MtsER 37 '/.1 ~ -l. O N dd 'h 'l N f.0 ) /. I 2.3 / 2.2.
- 3. 'I
) 3. r DECEMBER ~). O ' l.2 /
- 2. 2. #
2, Y ' TOTAL S E C T, c // ; iv G_ f'u i; t. V /l u t.'r DECCN E C R A fs Y Y /) 1: i Il, li C R o c Vi f)R C lt O C h DAC VD U L T bAC JANUARY 8/ (, O.9 N 1./ N _Ia0 N N> 8/t1 01 } l.0 2. 'l } 2.3 __5.6 ) 4. I ~~~~ 3,f( FEBRUARY uAnCn et,1 / / 1, I 2.3 / _LY' APRIL h jd N 2.3 1 N __d. T \\ MAY 3.J '/, 3 0,_') ) /.O 2.O )_ 2.2, ___2. 0 ) 9.b 1,y / o,_3
- 2. 3 '
I 9J ' JUNE J[, ( x3
- 2. f JutY 0.4 x
- 2. 2 x
_ _ L._7 N 12 0 3 l.1 2J > 3.3 _E..] > 2. 8/ AucuSY pr SEPTEMBER ,,( / 12
- f. 2. '
__ZJ ' / OCTOBER 'f,3 x 1.0 N 2.2 's _ f. 2. N NOVEMBER 3.6 ) L_(__ O.3 ) Ou L f.f )
- 1. E __
l _7 ) f.4 i DECEMBER 3, ( / O7 l.b $ 3. "l TOTAL L(.h Ell)_) 111E T.EJ )_,lipgeaday 8 TtI,l< I Ln$omu / fr.1-D c I] ' I
- I O ~ '"" l<* Y in l )
( 220 (1)pm l{meren '3) = Pa9e 12-23 Rev. 0 o. Date: 1/?2/86 4
1 l UNC NAVAL PRODUCTS O'. License SNM-368 Chapter 12 Page 12-24 Date: 1/22/86 Docket No. 70-371 Rev.0 Air Samole Data Analysis (cont'd) All areas are monitored for radiological hazards, and personnel exposures are continually reduced to approach ALARA levels through design engineering, use of protective clothing, health physics controls and procedures and training. g The sectioning area has the highest average airborne concentrations and continues to be'an area where incremental reductions in 4 radiation doses may be possible. Engineering efforts to improve confinement and process exhaust have been neutralized to some degree by a specification change in our government-supplied fuel which permitted an increase in the " hotter" uranium 234 isotope in the fuel mixture. This' increase results in a higher mixture specific activity for the same quantity of fuel. We experienced a temporary increase in sectioning area production throughput necessitated by a number of developmental contracts. High airborne concentration.= cccurred whenever the workload throughput doubled.
- b. In vivo Countina 1 Q In vivo (whole body) counting is done by vendor-supplied services.
4 Counting schedules are based primarily on work location and exposure potential. However, a complete evaluation is performed involving consideration of the selection criteria listed in Table 12.10.10. I Criteria for in-vivo selection is such that the most potentially exposed personnel will be counted each time. Sectioning personnel, for example, are always counted. l l 4 l I Page 12-24 4 I _ _, _ ~,,. _. -, ..y-- ...,. ~ - -, ..-.,._7_ w. ..,.-..m
Table 12.10.10 Whole Body Selection Criteria Key i Not counted last time Routine - always count 1 i l Hi Urine t ]- i ) Positive in-vivo number last time 1 1 Evaluation------------------ 1 - t l Potential exposure category; most probable if any I Supervisors Comments /Recomendation i i } i l i l i i f i l l lO ge,e 12-23 gev;.o 4 t f. y,--.--w,vn y n-w rw ,.w--vy-9 -ew wwe - - -, -+w-gw.-py-yyw--hvgM77-P=* '-TPV'*'mWgw-* yr m wVa ww ww'grwf'y rw--mDTw
- NTT "t7
'W' ' * - T'--"'"hW79 *V+--'-**'1'-f'F-' W PW*-'w'#-""W'- 4-~'-Y
- - ~ a UNC NAVAL PRODUCTS () License SNM-36S Chapter 12 Page.12-26 Date: 1/22/86 Docket No. 70-371 Rev.0 In Vivo Counting (continued) Tables 12.10.11 and 12.10 12 detail in-vivo lung counting results per precess area for the previous four years. 4 Maximum permissible body burden was calculated as 179 micrograms U 235 for 1981 through June 1982, and 164 micrograms for July 1982 through December 1984. The difference reflects the increasing U 234 isotope in the fuel mixture. Table 12.10.13 shows an average of the five highest counts and the maximum count in the average for the past five years. The maximum permissible annual dose to any individual showing the highest microgram count number has been less than 50% of the ICRP recommended fose,as determined by additional in-vivo counts.
- c. Uranium in Urine The retention, metabolism,and ultimate toxicity'of~ enriched uranium depend upon the chemical form and specific activity of the elements.
The chemistry of uranium determines its solubility in body. fluids and hence its retention time in body tissues. Although Naval 1 Products fuel material is considered from a conservative standpoint to be non-transportable Class Y material, there is some class W and some class D material present in the dust. (A lung _ clearance rate more rapid than the conservative models has also been observed). The presence of measurable urinary uranium is due to this material. Urinalysis results are primarily used to identify trends and the absence of significant data is indicative of the absence of any unsafe trends, i Uranium urine concentrations for the past four years are shown in Tables 12.10.14 and.12.10.15. All personnel assigned to B-South participate in the sampling program. Samples are requested monthly. Action levels are 50 dpm/ liter for investigation and 100 dpm/ liter for evaluation and restriction until levels drop to 50 dpm/ liter. In the two years of data, no one has exceeded action levels. The relationship of our limits to dose commitment by model is shown in t i Table 12.10.16. i Page 12-26
ll l1 2 8 O 0 6 6 8 1 / 2 0 1 2 2 8 / 1 1 2 1 e 8 1 ta D 02 1 1 1 8 1 0 1 8 O .v 2 2 2 2 2 3 1 0 0 1 1 4 e 8 1 R 08 0 6 1 2 0 0 2 1 0 0 0 0 5 8 2 9 5 2 0 1 3 5 4 4 1 1 7 8 1 1 5 O 9 5 5 7 3 2 2 U f 1 2 1 1 2 3 0 1 0 0 0 0 2 1 S 4 1 8 1 M A e 0 R g 1 G 7 a 2 8 5 2 6 5 3 3 2 2 1 O 4 P 8 1 2 R 1 C I e M l ba T T LU 0 S E R 1 5 1 4 0 7 5 2 5 6 2 76 8 1 1 1 O V I 2 9 8 0 2 8 1 1 V l 3 2 6 1 1 7 8 6 7 1 2 1 a 1-N t / / / / / / / / / / / / / / I o1 9 2 6 4 1 5 3 5 6 0 2 O 3 T 8 1 1 1 1 8 1 tn C n s n o l o i a i t i c t c y r e c u l e j u d b t s d g o m a y o C n r C e M h r O P E_ b i P Q s ? h a n s ra h ? i_ A_ a L o 1 O' I m t t t k l l e t n e t r n t i i i i c c a h i i r t e c j e h e n n a u e t n o U_ M C S U u L l u O j J f i 1 2 3 4 5 6 7 8 9 O 1 2 3 4 b 6 io 9 0 1 2 3 4 5 6 1 8 9 0 1 2 2 2 2 2 2 2 2 2 2 3 3 1 1 1 1 l 1 i t 1 2 1
l i I 48 ) ( 0 6 68 1 / 0 2 2 3 2 1 8 / 1 4 0 0 0 0 0 0 0 0 0 0 0 0 0 e 8 ta D 0 2 1 1 8 3 0 0 0 1 1 1 0 0 0 0 0 3 8 O 4 0 0 1 1 0 0 1 0 0 1 0 0 4 v 8 e R 08 06 3 1 0 0 0 0 0 0 0 0 1 0 1 3 8 2 4 s 2 2 0 0 0 2 2 1 1 1 0 2 8 ) 5 3 ( 2 95 U S 6 3 s 3 1 2 2 1 1 1 ? 3 2 0 8 M 8 3 2 A 2 R 2 2 G 1 1 O 4 1 2 2 8 7 8 3 2 4 8 6 4 5 R 8 2 1 8 e 0 C g 1 I a M P 2 1 S T e LU 0 l b S a E T R 3 8 ? 3 3 7 5 3 5 0 1 6 0 3 B1 1 1 8 O 'J_ l_ V I V s lt4 6 4 5 0 1 N an8 2 1 5 1 7 8 6 4 5 1 7 4 1 tu/ / / / / / L / / / / / / 1 I 4 6 P 5 8 1 / oo3 4 5 4 6 0 7 1 2 TC8 2 1 1 1 l 1 t 1 a C n s no o l i a i t i s t c y r c c u l e i u d b t s d g o m a y o n r C e M h r C P O s P P O b i h a n s r i ? 2 A a a I o 1 1 i e d r n ) I m t t t k l l e t t n i i c c a h i i c ( t o c n n e e h e n n a u lI o U U D e t M C S U U E lf 1 2 3 4 5 6 7 8 9 0 1 8 2 3 4 6 7 e 9 o 2 3 4 5 6 1 s 9 0 t 1 1 1 1 1 1 i 1 2 2 2 2 2 2 2 2 2 2 3 3 1
i ,TA3LE 12.10.13 i (] AVERAGE CF THE FIVE HIGHEST ' DHOLE 30DY COUNTS AND HIGHEST INDIVIDUAL COUNT. SY YEARS Average of the Five The Highest Annual Average Deposition Highest Counts Count Necessary For Maximum (Microcrams U235) (Micrograms U235) Permissible Dose-Commitment 1980 75 101 202/180 1.32 - 1 505 1981 89 120 180 1 50% 1982 70 79 180 1.50$ 1983 98 115 165 1.63% 1984 62 67 165 1.63% i 1 1 Material Spec. 145' 1.8N O i Page 12-29 Rev. O' O
- :e> 1/22/86
- - -.. ~ -,. .n.
l 68 / + 2 6 2 2 / 1 1
- e ta D
5 2 1 00 1 O ve R 9 9 7 7 1 6 7 0 5 R E T I I L 4 / 1 M 0 P 3 0 D 1 9 2 S 4 2 N 5 0 13 1 0 0 0 0 0 1 0 1 0 0 3 0 o 1 10 0 1 2 3 1 1 1 O 6 1 1 e I 2 g E T a L A P 1 i R A T I N E CN O C 5 5 4 4 2 2 4 1 4 3 1 2 7 g 0 3 0 0 o 4 7 9 7 2 9 1 2 M 2 3 1 2 p 1 1 1 2 U 1 I 3 N 1 A RU Y RAN I RU 2 0 8 24 3 7 0 2 3 0 9 4 7 4 0 3 7 3 1 0 8 3 1 2 5 7 1 9 0 09 0 0 0 9 0 1 8 9 g 1 9 7 7 95 01 2 2 0 5 1 1 1 1 1 1 1 1 J 1 1 1 1 1 1 1 2 0 j 1 I R R R Y R R R Y E R E E Y R i L s B B L E R E E Y R T A l i H s B E B B L R B E R A L E Y C I Y M M A A C I Y E Y R R A N L u M B M U u c E O T 2 U R R A N L u M B A A U U M M T 1 M U U c E O U R E E R E E O T T O 8 N A P 8 N B A P T T A E M A J J u V C B A J J u V C T 9 P C T 9 A E M A P C A O E O E E O 1 J F E O 1 J F S N D S N D 1 i l l j ji l ,!lll 1 ijjlli ji { ]' Ii}1!!
i 1' il i O + 6 2 1 6 8 /2 2 / 5 1 2 1 e 0 t 0 a D 1 O 9 9 v e 7 R 7 / R E T 6 1 1 O I 7 L / 0 M 5 P D 5 S 1 N 1 O 3 0 I 1 T 2 A 1 2 R 1 T 9 e N 4 g e E - 2 2 1 1 1 7 1 1 1 2 5 a l C 6 P b N 2 a O T C M U I N A RU 5 Y 2 6 3 8 5f9 1 6 7 5 6 00 3 3 1 9 9 2 5 R 5 4 1 1 1 j 1 8 1 1 1 1 8 A 3 N 1 I R U 2 3 1 8 6 2 3 0 6 1 2 7 7 7 9 7 4 4 5 5 3 4 3 8 g 8 t; 1 9 3 5 g1 8 7 2 44 7 3 7 3 2 3 6 6 5 2 0 5 1 6 g 0 1 1 J 1 1 1 1 1 1 4 1 1 1 1 1 1 1 1 1 1 5 0 1 1 R _R R R R R Y Y E R E E E R E E Y i Y R T R B E B B L R H L E Y s B E B B L H R A s A L E Y E E 8 U R R A N L u M B A C I Y M M T u M B A U M M A 4 C I Y A U A M U U c E O R R A N L M U U c E O T 3 U R E E O R P A P T T o T T V C 9 N B A J J u 8 N B A J J u V C T P C P C T A E M A E O 9 A E M A O E O E 1 E O J F S N D 1 J F S N D !l' l l lj: li 1 j l lli )] jli j 4 I I1
O Table 12.10.16 103 1 I I I i l 11 1 1 iiitil I I I I i 11 ~ ,.;;*. : '.,., f CLASS (Y) CLASS (W) -] .w. ..= m. _ c . us -o ' -~ 3 ,0, %+ C 9 V RESULT >1 MPO, 4 4 q% y p d O E .5 ACTIONS (1) THMU (11) .............................j., .i.s.. . i.Mr o, - TABLE IV-4 a w g 101 / n....................,., 7....,..- [ N <r..........7.,.3.,.,.,.,......x-1/2< nEsutTs1 Mro. ACTloNS (1) THRU 18) g 1 ~ E / / M ^V. 2 th< R ESULT11/2 MPD @ Investigation' V / / y,/yp.... ...../..,.. /. +g [f. g...... c AcTious ni THau (4) u. .............?.'.~ f, 0.h m 0 E 100 s g g \\ E o U w 02 L L = ] o RESULT 11/5 MPO, g E. P_ 10*l 8 3 No Action 10-2 I I I 111Il 1 I I IIIII I I I I I Ill 100 101 102 303 URINARY URANIUM CONCENTRATION (pCi/l) O rioe, iv 12 oe eCemmitm etleoiceteoe mee.'vs.u,i a,v u,a >em v Concentration, Class (W) and (Y), Single intake ~ 2 - '"~ Rev. O pace Date: 1/22/86 \\ t ' - ' - - ' ~ - ~ ~ ~ " ~ ~ ~
( t r UNC NAVAL PRODUCTS - r I ' () License SNM-368 Chapter,12 Page 12-33 Date: 1/22/86 Docket No. 70-371 Rev.O 12.10.3 Trends in Excesure or Airborne concentration There are no significant trends in personnel exposures or airborne concentrations that can be identified from the 1981-1984 data tabulated. Airborne levels in Pack Assembly, Met Lab, Unit 1, Chem Lab.,and Spec Lab are at ALARA levels now. A process in Unit 2 is still under evaluation and recommendations.have been made and implemented to address ALARA concerns. Sectioning Decon,and the vaults are under continuing review and improved engineered enclosures and process modifications have been made to further reduce airborne concentrations. 12.10.4 Reduction of Employee Exeosure and Airborne Levels Actions Taken
- 1. Additional exhaust installed on shear machine in sectioning.
l
- 2. Coolant stream flow re-directe'd on cut off wheels to point of machining, from a location 180 degrecs away.
()
- 3. Rotation of cut off wheel reversed to reduce i
sparking and airborne. 4. New exhaust added in trash compactor area (Decon Area). l
- 5. New exhaust added to scrap vault table area
- 6. New exhaust added to fuel crib table area a
l Effectiveness
- 1. Floor contamination reduced. Airborne reduced i
slightly. 2., 3., 4., S.,and
- 6. Reduction in airborne.
i I <l' L 1 r ! () Page 12-33 4 _--,.m ,----.,y.- ,y -w -,.r-- r , + - -. -
UNC NAVAL PRODUCTS /' License SNM-368 Chapter 12 Page 12-34 Date: 1/22/86 Docket No. 70-371 Rev.0 Actions Planned
- 1. Additional modification to shear to provide better enclosure.
- 2. Continued evaluation of raw fuel vault.
3. Continued review of process operations. We believe the best demonstration of NPD management's commitment to ALARA is by results achieved, rather than in various status reports. The NRC summation of Occupational Radiation Exposure 1980 and 1981 .(NUREG-0714 Vols 2 and 3) dated October 1983 and the most recent 1982/1983 (NUREG 0714 Vol. 4 & 5) dated October 1985 continue to show UNC as the fuel fabricator with the lowest average worker exposure. This good performance was also achieved in 1977 (NUREG-0463 dated October 1978) the last report to list specific companies prior to 1980-1983 The exposures at NPD are also significantly better than the other license categories of power reactors, industrial radiography,and manufacturing and distribution. 12.11 Measures Taken To Imolement ALARA () Information has been presented in paragraph 3.1.1. The ALARA Committee ( Manager, Nuclear and Industrial Safety, Health Physics Specialist, Nuclear Criticality Specialist, and Industrial Safety and Hygiene Specialist) meets once per year to review the draft ALARA Annual Report. Audit and inspection of operations is presented in paragraph 2.7. A typical Health Physics inspection form is attached as Figure 12.11. Paragraph 11.6 presents procedures for review of new operations and changes in existing activities. l Page 12-34
,a i NEALTH PHYSICS INSPECTION NO. 1 AREA Performed Sys ~ i "'I'** DATE Contact rollow-up Memo No. INSPECT!oM ITEM A. Area Remarks / Action i. 1. Protective Clothing 2. Personnel Monitoring Equipment i 3. Air Sampless 4 4. Process Equipment t 5. Contaminated Weste Handling / 6. Training /Awarene's s 3 General Inspection ftens 1. New or Modified operations 2. Unusual occurrences 3. ruel mandling Review C. Personnel Radiation Protection j 1. ' Contamination Control 3 2. ' Airborne control 3. tree of Monitors s D. Previous reems i ~ ~ ' is -m-E. Additional-Cdemenes/Pecuested Action ,y-
- Ihe$e itees inspected against Drevious month's hP records for area. InsprCtion Code: $*
Satisfactory 0-Questionable U-Unsatisfactory.1l.Not In5Detted. Figure 12.11 Page 12-35 Rev. 01 Date: 1/22/86 .s. Y
- }.$.
RK: NAVAL PRODUCTS () License SNM-368 Chapter 12 Page 12-36 Date: 1/22/86 ) ,v Docket No. 70-371 Rev.0 12.12 Bioassav Procram Information has been presented in Sections 3.2.7.and 12.10. The UNC NP bioassay program meets or exceeds the recommended bicassay program as put forth in Reg. Guide 8.11 with one exception, in the area of in-vivo counting. The Reg. Guide calls for a' semi-annual in-vivo frequency for Class Y material in every case for all personnel working in an area where bioassay measurements are required. It is not our intent to in-vivo count everyone everf six months. We use selection criteria as presented in Section 3.2.7.3 to insure that potentially exposed personnel are identified and counted. Justification for this approach is found in a review of our ALARA data presented in section 12.10 above. In addition, our urine bicassay program which we currently operate i on a monthly basis functions as a prime indicator for in-vivo selection. In virtually every reported case of-long term retention of uranium in the lung there has been a urinary uranium excretion rate measurable for many months, probably due to the additional O' presence of Class D or W material. The prompt appearance of urinary uranium after suspected exposures indicates the presence of these more transportable forms. Our ALARA data for urine bloassay is tabulated in Section 12.10 above and the results support this exception to the Reg. Guide. 12.12.1 FECAL ANALYSIS \\ Derivation of Airborne Extosure From Early Fecal Clearance Data i
- a. Introduction This procedure details the derivation of airborne exposure from early fecal clearance data. It is largely derived from:
(1) Report of Committee II of the International Commission on Radiological Protection Concerning Permissible Dose for Internal Radiation - 1959 Revision; (2) Title 10, Code of Federal Regulations; (3) Existing practice for derivation of airborne exposures. ( Page 12-36
UNC NAVAL PRODUCTS O License SNM-368 Chapter 12 Page 12-37 Date: 1/22/86 Docket No. 70-371 Rev.0
- b. Personnel Extosure Limits The average maximum permissible exposure in any period of seven (7) consecutive days is forty (40) MPC hours.
" Exposure" as used in this context means that the individual is cresent in a measured airborne concentration. c.Model Assumptions 3 (1) The MPC for soluble U235 is 1100 dpm/g (2) The MPC for soluble U238 is 154 dpm/m 3 (3) The MFC for insoluble U235 is 220 dpm/m 3 (4) TheMPCforinsolubleU238gs132dpm/m (5) A working man breathes 10 m of air during an 8 hour day. (6) The first three fecal excretions (3 to 5 days) following exposure to soluble material contain 50% of the activity inhaled (7) The first three fecal excretions (3 to 5 days) following exposure to insoluble material co'nta'in' 62.5% of the activity inhaled
- d. Model Justifications
, O (1) Existing maximum permissible concentrations in air (coupled with Standard Man data of the referenced 1959 ICRP Committee II Report, can be utilized in a relatively simple scheme to evaluate fecal clearance. (2) Later models presuppose knowledge of particle size, but particle sizing on a relatively large scale is impractical.
- e. Model Reservations very significant errors are possible if the particle size distribution departs significantly from 1 AMAD.
() Page 12-37
i UNC NAVAL PRODUCTS 'O License SNM-368 Chapter 12 Page 12-38 Date: 1/22/86 Docket No. 70-371 Rev.0
- f. Derivation of the Exeosure (1) Soluble U235 1100 dem x 10 ml x 0.5 inhalation = 688 dem J
m MPC 8 hrs inhalation fecal clearance MPC hr. Example: Suppose a man was exposed to soluble U235 and the summation of activity in his first three fecal clearances was 27520 dpm; Therefore: 27520 dem = 40 MPC hrs. 688 dpm/MPC hr (2) Soluble U238: 154 dem x 10 ml x 0.5 inhalation = 96 dem 3 m MPC 8 hrs inhalation fecal clearance MPC hr. Example: Suppose a man was exposed to soluble U238"and the summation of activity in his first three fecal clearance was 3840 dpm; Therefore: 3840 dem = 40 MPC hr. , () 96 dpm/MPC hr l (3) Insoluble U235: 220 dom x 10 ml x 0.625 inhalation = 172 dem m3MPC 8 hrs. inhalation fecal clearance MPC hr. Example: Suppose a man was exposed to insoluble U235 and the summation of activity in his first three fecal clearances was 6880 dpm: Therefore: 6880 dem = 40 MPC hrs. 172 dpm/MPC hr. Page 12-38 e.
UNC NAVAL PRODUCTS (LJ~} License SNM-368 Chapter 12 Page 12-39 Date: 1/22/86 Docket No. 70-371 Rev.0 (4) Insoluble U238: 132 dem x 10ml x 0.625 inhalation = 103 dem m' MPC 8 hrs. inhalation fecal clearance MPC hr. Example: Suppose a man was exposed to insoluble U238 and the summation of activity in his first three fecal clearances was 4120 dpm; Therefore: 4120 dem = 40 MPC hrs. 103 dpm/MPC hr g.If any evaluation, there is reasonable doubt as to the physical form and/or chemical form and/or isotopic identification of the material inhaled, always use the most conservative estimate based on the best available evidence. 4 12.13 Air Samolina and Internal Extosure Procram Information is presented in paragraphs 3.2.3 and subparagraphs ~ thereto, 12.8.2,and 12.10. 12.14 Surface Contamination Information is presented in paragraphs 3.2.1, 3.2.6,and 3.2.4.2. The plant layout identifying the areas currently designated as controlled and limited control is presented in figure 12.14. i i l () Page 12-39 i
O e APPENDIX 12.9 Q RESPIRATORY PROTECTION PROGRAM i j 1 O k t
DEC 2 91977 PROGRAM FOR RESPIRATORY PROTECTION AGAINST ] AIRSORNE RADI0 ACTIVE MATERIALS NAVAL PRODUCTS DIVISION TABLE OF CONTENTS * (i) License Information SECTION 1 INTRODUCTION 1.1 Purpose 1.2 Scope 1.3 General Policy Statement 1.4 Program Administration SECTION 2 RESPIRATORY HAZARDS AND EQUIPMENT SELECTION 2.1 Classification of Respiratory Hazards p 2.2 Differences in Risk Associated With Exposures Over Limits 1 V 2.3 Air Sampling Program 2.4 Equipment Selection SECTION 3 TRAINING AND IllSTRUCTI0li 3.1 Qualifications of Training Personnel 3.2 Extent of Training 3.3 Contents of Training Program 3.4 Fitting of Respirators NAINTEllANCE - If1SPECTION - REPAIR SECTION 4 4.1 Issuance and Return of Respirators 4.2 Cleaning and Disinfection 4.3 Reassembly and Inspection 4.4 Repair of Respirators 4.5 Storage SECTION 5 MEDICAL AND HEALTH PHYSICS SURVEILLANCE PROGRAM 5.1 Pedical Surveillance Program 5.2 Guide to Final Evaluation for the Use of Respirators 5.3 Bioassay Program O 4
DEC 2 : N77 PAGE 2 ,,/ TABLE OF CCNTENTS SPECIFIC PROCEDURES LIST 3 Procedure 6-1 Health Physics Job Evaluation for Radiation Exposure Procedurt 6-2 Respirator Training Program Topics i Procedure 6-3 Negative Pressure Test Comfo Type Respirator i Procedure 6-4 Positive Pressure Test Comfo Type Respirator Procedure 6-5 Challenge. Atmosphere Test l Procedure 6 New Respirator Inspection Procedure 6 Cleaning and Disinfection of Comfo Type Respirator i Procedure 6-8 Reassembly and Inspection of Comfo Type Respirator ~ 3 O Appendix A Press Suits l Appendix B - Operation and l'.aintenance flanual - Scott Air-Pak Appendix C Survive Air -Pak .i 1 O I i ,y,,,_,-,w.n,,, .__.r,_-, ,_-.___~w,y..<.
DEC 2 91977 O* UNCA.vtLLE. COMMECTICUT O.3 8 vai, RESPIRATORY PROTECTION PROGRAM FOR RADI0 ACTIVE PARTICULATES BACKGROUND INFORMATION Since 1968 Naval Products Division has had approval from the Nuclear Regu-latory Conaission to make allowance for the use of respiratory protection equipment subject to conditions specified in its SNM license. We have never found it necessary to implement such a program. Respirators were issued to maintenance personnel for jobs such as filter changes and sectioning equip-ment repair and to production personnel for equipment cleanouts as-an extra - precaution to keep any exposure as low as practical. Personnel were never knowingly permitted to be exposed to airborne concentrations of radioactivity exceeding federal regulatory limits (for no respiratory protection) even when wearing respirators. O In December,1976 amendments to Title 10 Code of Federal Regulations, Part 20 stated that licensees who have previously been authorized to make allowance for respiratory protective equipment prior to December,1976 must now establish a program to meet new requirements, as stated in Part 20, within 'one year. At Naval Products Division, the need for such a program continues to remain as an adjur;ct to the Health Physics Program. Respirators are issued to per-sonnel performing maintenance type jobs such as cutomatic cleanouts and HEPA filter changes to maintain am radiation exposure as low as is reasonably achievable. Respirators are not required for day-to-day production operations. However, we.are required to establish a program in sufficient detail to permit taking credit for reduced actual' exposure due to use of a. respirator. The following program establishes this option. O L
i Q n.yt,1on 0_ - SECit,0N I Approved INTRODUCTICN Issued DEC 2 9 1977 Supersedes NEW l.1 PURPOSE This program has been prepared to provide technical inform on the application of respiratory protection devices for protection against airborne radioactive materials in Naval Products Division. The various elements of a respiratory program are described in sufficient detail to meet the requirements of Title 10 'Part 20.103, " Exposure of individuals to concentrations of radioactive material in air restricted areas" as discussed in Regulatory Guide 8.15, " Acceptable Programs ~ for Respiratory Protection". 1.2 SCOPE This program is designed to provide adequate information for the planned use of respirators to protect incividuals from airborne radioactive materials that might be encountered during certain production or maintenance operations in Naval Products Division. 1.3 GENERAL POLICY STATEMENT The primary objective of the respirator program discussed in this manual is to, first, limit the inhalation of radioactive materials and, second, to maintain occupational radiation exposure as low as is reasonably achievable. For routine operations these objectives are normally accomplished by the application of i engineering and health physics controls such as containment, ventilation, and procedures. For some non-routine operations, and when such controls are not feasible, the use of respirators may be appropriate. For emergencies, advance preparation may also include the possible use of appropriate respiratory equip-ment. The periods of time respirators are worn shall be kept to a nrinimum. Provision shall be made for the respirator user to leave areas where respirator use is required at reasonable intervals for rest periods and for any other condition that might require such relief. I NPD is comitted to seeing that radioactive materials are handled in accordance with the condition of its license and the rules of the Nuclear Regulatory Com-mission. Each employee shall use the provided respiratory protection in accor-l dance with instructions, training, and guidance described in this program. i l-1
O SECTION I Approved / / d israoouCTIon 2.,,,a DEC 2 91977 Supersedes NEW We are a uranium fuels fabrication operation, where except for operations in Building B South, all radioactive material is in encapsulated fonns. No radio-active gases or transuranic elements are involved, therefore only those safe practices and requirements for using respirators for protection of the respiratory system from inhalation of particulate uranium as generated in UNC type operations is included. 1.4 PROGRAM ADMINISTRATION Overall responsibility for maintenance of the respirator program is assigned to the Specialist, Radiological and Environmental Control. The actual pregram shall be administered by the Health Physics Section. The established program meets current needs under current manufacturing operations. The Specialist shall ensure that the program is ~ carried out satisfactorily and that it remains effective, by continuing examination and modification to meet changing conditions. 9 0 J 2 ' g 1-2 y-y ...------.-----m.
'l 0 o- %f M SE QION 2 Approved 4_// RESPIRATORY HAZA5DS AND E'QUIPMENT DEC 2 91977 SELECTION Issued Supersedes NEW 2.1 CLASSIFICATION OF RESPIRATORY HAZARDS In order to choose the proper respirator, from the hundreds that are available, for use against a specific hazard, one must first assess the type and extent of the hazard. Respiratory hazards are either: Oxygen Deficiency or Air Contamination by Particulates Gases and vapors or a Corbination s The selection of respirators requires identification of all respiratory hazards present. A procedure for this assessment is shown in 6-1. O" With each hazard, one must answer the question, is the hazard innediately dangerousf to life or health?* 2.2 DIFFERENCES IN RISK ASSOCIATED WITH EXPOSURES OVER LIMITS ~ The respiratory hazard identified from the hazard evaluation for routine, non-routine and emergency situations ** is air contamination by uranium.particulates. The manner in which concentration limits for radioactive and non-radioactive con-taminants in air are detennined results in levels of risk that differ greatly when individuals are exposed to concentrations in excess of the limits. For non-radioactive hazards, concentration limits are usually not more than a factor of ten below those levels of exposure that cause discomfort irritation or in some cases, death. For radioactive hazards, concentration limits relate to levels of exposure that are far below those at which any observable effect would be expected. So, exposure for an hour, for example, to uranium airborne par-ticulates at levels two or three times the maximum permissible concentration (fPC) would not be expected to result in any serious effects whereas similar exposure in excess of the threshold limit value for non-radioactive contaminants could result in irritation, eye injury or death. The current accepted definition of an atmosphere innediately dangerous to life and health is one fro.n which a person cannot escape unprotected within a half hour without irreversable damage to health, eyes, or without injury. The key word is irreversable.
- Excluding a criticality incident.
'I I l l j f 2-1
i Ravinion 0 SECTION'2 MN RESPIRA90RY HAZARDS AND Approved /,////d j EQUIPMENT SELECTION IssuedDEC 2 91977 Supersedes j NEW ( MPC's represent a uniform degree of risk, and control to this level limits annual radiation doses such that throughout a working lifetime no observable effect on the individual would be expected. Standards for radiation protection take into consideration a "no thmshold" concept and within the recommended limits actual exposure to uranium particulates must be kept as low as is reason-ably achievable. 2.3 AIR SAMPLING PROGRAM NPD's air sampling program can be directly related to resp, ira, tory protection in that it: a. Provides an estimaterof the potential intake of airborne radioactive materials and resulting exposure of the individual worker. O b. Provides data to assist in the selection of respiratory protective equipment that would provide adequate protection under exposure conditions. c. Provides data for control of long-term exposures to workers. d. Provides documentation of personnel exposures for legal or regulatory purposes. e. Identifies and characterizes the contaminants and their sources. f. Provides data for determining the requirements for engineering or adminis-trative controls. l
- g. ' Indicates the continuing effectiveness of existing controls, and warns of i
the deterioration of control equipment or operating procedures. 1 h. Provides a record of long-term trends showing variations in contaminant { levels.
- i. Continuously measures the level of airborne contaminants in and about work areas and warns of releases of airborne contaminants to the outside environment.
i 2.4 EQUIPlfNT SELECTION There are two general classifications of respirators (1) air-purifying and (2) atmosphere - supplying. The air-purifying respirator class consists of three types available for use against specific hazards: particulate removing, vapor and gas removing, and a combination particulate removing and vapor and gas 4 removing. These types remove sone or all of the radioactive material by filtering the air. The atmosphere - supplying devices provide clean,ebreathable air to the wearer and separates him from the contaminated atmosphere by an air-tight system of mask, hose, and tank. Specific types of equipment from both l 2-2 .,,.~_._. _.._-.
l O 1 V n.,,4,, n, n o m SECTION 2' )/f RESPIRATORY HAZARDS.AND AD9 towed /2/M EQUIPRENT SEfECTION E29M Supersedes NEW I iclassifications are provided by NPO for routine, non-routine and emergency purposes. The specific hazard in all cases has been currently identified as uranium particulate. 2.4.l'. Routine and Non-Routine Health Physics Monitored Operations, (Includes Spills and Cleanups) The Health Physics Section provides the Mine Safety Appliance Comfo II Respirator #460968. This is a half-mask face piece with two filters or cartridges and two sets of headbands. (a) Cartridge #459439 Type H is an ultra-filter cartridge which protects against radionuclides, dusts, mists and fumes. Alternate brands of half-face masks and full face masks may also be provided. In all cases, such masks shall carry NIOSH certification. 2.4.2 Routine Production Operations Production personnel use a custom made atmosphere-supplying type suit in the filler fabrication operations. These are used because of need to work in an inert atmosphere, not because of the need for radiation protection. Because of the unique circumstances involved in this operation, the suits are further discussed in Appendix A to this manual. 2.4.3 Emergency Operations The Medical and Industrial S~afety Sections provide Scott-Air Paks and Survive Air-Paks for emergency type operations in hazardous atmospheres. This apparatus provides complete respiratory protection against toxic j gases, oxygen deficiencies as well as radioactive particulates. The manufacturers recomendations are followed in the use, operation and maintenance of this equipment. The Scott Air Pak Operation and Maintenance Manual is attached as Appendix B and Survive Air Pak in-formation is attached as Appendix C to this manual. 2-3 ' e 9 .,._,,.a
i O n. y t, 4 m, 0, -SECTION 3 APP' v'd / TRAINING AND INSTRUCTION I'*"*d Supersedes NEW 3.1 QUALIFICATIONS OF TRAINING PERSONNEL Training in the use of respiratory protective devices shall be given by a qualified and experienced instructor. For emergency equipment the training pro-gram is implemented through the Industrial Safety Section. For routine and non-routine operations inv61ving radioactive material, the training program is im-piemented through the Health Physics Section. l 3.2 EXTENT OF TRAINING An adequate training program based on the hazards to be encountered and the type of respirator to be worn will be developed by the appropriate section identified in 3.1. Training of both supervisors and workers shall include a discussion of the engineering and administrative controls in use and why respirators also are needed; explanation of the nature of. the respiratory hazard and what happens if the respirator is not used properly; explanation of why the particular type of respirator has been selected; and a discussion of how to recognize and handle emergencies. 3.3 CONTENTS OF TRAINING PROGRAM Procedure No. 6-2 " Respirator Training Program Topics" lists an outline of topics which should be discussed in'the classroom training program. In addition, when Comfo or similar type respirators are designated by Health Physics for specific jobs involving production, inspection or maintenance per-sonnel, Health Physics shall provide on-the-job refresher training covering, at a minimum, items 3 and 5 of procedure 6-2 and instruction on leaving the work area for rest periods, undue physical or psychological distress or any other condition that might require such relief. 3.4 FITTING OF RESPIRATORS Every respirator wearer shall receive fitting instructions, including how it 4 should be worn, how to adjust it and how to determine if it fits properly. Respirators shall not be worn when conditions prevent a good face seal. Such conditions as beards and stubble may prevent a good face seal and require further testing noteo below. 3-1 ~
!O o y cTroN'3 Approved / /
- TRAINING'AND INSTRUCTION gg 3
Supersedes NEW NPD will use three types of qualitative fitting tests to check air puri type respirators, (1) negative pressure test (2) positive pressure test (3 challenge atmosphere. The first two shall always be done prior to beginning any routine and non-routine work.'wher~e respirator use has been specified. gThe third shall be done for the first time fitting of the operator to the respirator. For those operators who' have demonstrated previous good fitting with the same j model, who are well experienced in the use of a respirator, and who am performing jobs that have been previously evaluated by Health Physics the challenge atmos-i phere test may be eliminated; provided they have no facial characteristics that could interfere with an acceptable fit. 3.4.1 Negative Pressure Test i The wearer performs this test by closing off the inlet of the cartridge filter (s) by covering with the palm (s) so that it does not pass air; inhaling gently so that the facepiece collapses slightly; and holding the iO breath for io secoads. 1f the facePiece remaias siishtir coiiaPsed and no inward leakage is detected the respirator is considered satisfactory. Procedure No. 6-3 covers this test in more detail. i 3.4.2 Positive Pressure Test The wearer performs this test by closing off the exhalation valve and exhaling gently into the facepiece. If slight positive pressure can be j built up inside the facepiece without any evidence of outward leakage, the l fit is considered satisfactory. Procedure 6-4 covers this test in more l detail. f i 3.4.3 Challenge Atmosphere Test i I An irritant smoke tube filled with stannic chloride impregnated pumice i produces a very irritating smoke when air is blown through it. The smoke is directed at the facepiece seal and leakage is indicated by irritation l of the throat and lungs. Caution is *taken so that the smoke is not directed into the eyes. i The glass tube is scored at each end for breaking. A squeeze bulb with a short rubber tube aspirates air through the tube, imediately generating visible smoke. 1 3-2 l l
i O 0 navinian t SECTIO'N 3 I' TRAlMING AND INSTRUCTION A#'d A/ 2... 4 DEC 2 91977 Super.. des NEW A similar method is used to generate isoamyl acetate vapor,also referred to as banana oil. This chemical has a pleasant odor, however, since it is a vapor, it must be used with the proper type of cartridge. Since we are concerned about particulates, we would assure the respirator fit using j a vapor cartridge then replace it with the particulate cartridge. NPD has the capacity to perform both challenge atzspheres but will use primarily l the stannic chloride since no cartridge change is required and since leakage is much easier to discern using the irritating chloride rather than the sweet smelling banana oil. Procedure 6-5 covers this test in detail. 4 j i
- o i
4 l i ?. !i I 1 i I I 1 b !..e 4 t 3-3 ]
O ~ o 11-p #p = w SECTION 4 ^ "' " ' d ~ DEC 2 91977 NAINTENANCE - INSPECfION - I'*"*d REPAIR supersedes NEW Naval Products Division has established a maintenance program to ensure that respiratory protective equipment is kept in a state of readiness for use. 4.1 ISSUANCE AND RETURN OF RESPIRATORS The NPD Stores Departme'nt stocks the Comfo half-mask respirator and the Type H cartridges. Health Physics personnel shall withdraw and maintain a supply of these devices adequate for all planned routine and non-routine operations in the Health Physics Laboratory. These new respirators are given a preliminary inspection in the lab (Procedure 6-6) and returned to the box. The need for a respirator shall be determined by Health Physics and indicated on the Health Physics Special Work Permit for non-routine operations or established in the route card for routine opeations such as cutomatic cleanouts. Respirators shall be collected by llealth Physics upon completion of the job. 4.2 CLEANING AND DISINFECTI'ON-After collection, all respirators shall be cleaned, disinfected, and checked for residual contamination by Health Physics personnel. Procedure 6-7 details steps to be followed in this process. 4.3 REASSEM3LY AND INSPECTION All respirators shall be inspected before and after use, including a check of connections, condition of rubber, headbands and valves. Procedure 6-8 details the steps to be followed. 4.4. REPAIR OF RESPIRATORS Repair of Comfo type respirators, other than strap replacement shall not be made. Repair of other types of respirators shall be done only by experienced persons with parts designed for the respirator. No atten:pt shall be made to replace com-ponents or to make adjustments or repairs beyond the manufacturers recommendations. Such repairs, when necessary, shall be perfonned by the manufacturer or his designated representative. p 4.5 STORAGE V Respirators designated for reuse shall be placed in plastic bags and stored in a 1 designated drawer in the Laboratory. The bags should be packed loose so that there is no chance for damage or crushing. 4-1
( t l 10 o SECTICN 5
- ' * *d ITDICAL AND HEALTH PHYSICS SURVEILLANCE I'***d I
i PROGRAM supersedes NEW 1 5.1 NPD Medical Department will use both a questionnaire and physical examination for those employees who may routinely be assigned to operations requiring the use of i respirators. The medical history and physical examination will stress the folo l lowing items: Local. factors related to the proper fitting of i respirators. History or evidence of chronic cardiac or l respiratory disease j Hist.ory or evidence of other conditions relevant to wearing respirators Spirometry Specialized examinations depending on findings of above. items when indicated. O l 5.1.1 Local Factors Related To Proper Fitting of Respirator Any factor related to the physical fitting of the respirator to the i facial contour. Any physical factor related to wearing self-contained { breathing apparatus. 5.1.2 History or Evidence of Chronic Respiratory or Cardiac Disease y a. Chronic bronchitis or emphysema i i b. Asthma l c. Coronary artery disease d. Valvular heart disease e. Congestive heart failure f. Hypertension g. Peripheral vascular disease i h. Symptoms of the following: Cough and sputum Dfspnea on exertion Wheezing 1 Orthopnea
- O Angina l
Edema i 5-1 i I , _ -. ~. _ _ _,_ _.- ~ ---_._ _ _.- _ - - _. _.. _
vl ~ ..,,1 1 0- ,,c,,,,, - MEDJCAL AND HEALTH PHYSICS ADPf*d hl ' 'S'URVEfLLANCE ' PROGRAM 1...e40EC 2 91977 Supersedes NEW 5.1.3 History of Other Conditions Any physical, neurological, or emotional findings relevant to the wearing of respirators should be considered in the evaluation. 5.1.4 Spirometry Spiremetry must be done by NIOSH or ATS Standards'. Interpretation of Spirometry will be as follows: Impainnent None Mild Moderate Severe FVC (% Predicted) 80 66-80 51-65 50 FEYj (% Predicted) 70 61-69 45-60 45 0 515 5aeci " = d exe=$""t'o"= In special cases, additional tests may be indicated such as stress, EKG's, Diffusing Capacity tests, etc. 5.2 GUIDE TO FINAL EVALUATION FOR THE USE OF RESPIRATORS The evaluation of applicants for the use of respirators will usually be directed chiefly toward chronic respiratory or cardiac conditions. The guide for evalu-ation in these cases is as follows: Respirator Type Possible Candidate for Use High Resistance and/or No significant Medical Conditions Oxygen Enriched Normal Spirometry Lower Resistance No significant cardiovascular disorder (Prolonged Use) Mild Impainnent on Spirometry Lower Resistance Any chronic Medical Conditions Under (Brief Use) good control Minimal Resistance Moderate Impairment on Spiremetry The final evaluation in each of the above categories will take into consideration the exercise level and the source and extent of the exposure, both of which may alter the above recommendations. 5-2 p-
i l O'~. a .... w SECTIod 5- % d'- -MEDlCAL AND. HEALTH PHYSICS Approved /// IssuedDEC 2 91977 SURVEILLANCE PROGRAM Supersedes NEW 5.3 BI0 ASSAY PROGRAM N?O operates a bioassay program which will at a minimum, comply with Section 3.2.8 of the SNM license. Respirator users are evaluated for participation in routine whole body counting based on the frequency, type and duration of operations performed during the six month period prior to the scheduled date for wh, ole body counting. ~ 9 i 1 2 o O 5-3 l L
._.m. m .m._. I I I e I i 0 .... + - SPECIFIC PROCEDURES LIST Supersedes NEW l 6 6-1 HEALTH PHYSICS JOB EVALUATION FOR RADIATION EXPOSURE 6-2 RESPIRATOR TRAINING PRdGRAM TOPICS 6-3 NEGATIVE P,RESSURE TEST CONFO TYPE RESPIRATOR I 6-4 POSITIVE PRESSURE TEST COMF0 TYPE RESPIRATOR s 6-S CHALLENGE ATMOSPHERE TEST 6-6 NEW RESPIPATOR INSPECTION I 6-7 CLEANING AND DISINFECTION OF COMF0 TYPE RESPIRATOR 6-8 REASSElELY AND INSPECTION OF COMF0 TYPE RESPIRATOR i. l O S 6 O 1 e
0 n.vt. ton ff . P.BOCEDURE 6-1 Approved HEALTH PHYSICS JOB EVALUATION FOR Issued DEC 2 91977 RADIATION EXPOSURE supersedes NEW i SCOPE: This procedure should be followed in order to properly assess the radiation hazard associated with a SWP (Special Work Permit) request or other routine / non-rcutine operation. This assessment will then be used as the basis for requiring the wearing of a respirator. ,(1) Detennine the nianufacturing, inspection or maintenance opeations to be perfonned. What has to be done? r Estimated time; number of people involved; Who? j Type of equipment, construction Physical conditions during past operation (2) Evaluate work area O Size Equipment layout Ventilation Temperature (3) Evaluate area activity ) Other jobs being performed (4) Examine Past Perfonnances Contamination Levels Experienced Airborne Levels Experienced Time to Completion (5) Review Material Handling l (6) Check Bioassay Results Persons assigned to job Any potential exposures since last in-vivo count? 1 Q (7) Consideration shall be given to the presence of particulates other than V uranium and other gases or vapors in determining whether additional pro-4 taction is needed from the industrial safety / hygiene viewpoint. Contact i the Industrial Safety / Hygiene Specialist or Medical Director for advice. 1 6-1 l a
n.vtstan o ,,PROGEDURE 6-2, A n m ed // RESPIRATOR TRAINING PROGRAM TOPICS Issued DEC 2 91977 Supersedes NEW SCOPd: This procedure covers the topics to be discussed with those personnel who may be assigned to jobs where a respirator is required. (1) Discussion of airborne uranium to include physical properties, FiPC's, physiological action, toxicity, and means of detection; ' (2) Discussion of the construction, operating principles, and limitations of the respirator provided and the reasons the respirator is the proper l type for the particular purpose; (3) Discussion of the reasons for using the respirator and explanation of why more positive equipment or facilities controLis.not imediately feasible. (4) Instruction in procedures for ensuring that the respirator is in proper working condition; (5) Instruction in. fitting the respirator properly and checking for adequacy of fit; I (6) Instruction in the proper use and maintenance of the respirator;. 1 (7) Discussion of the cartridges provided for air-purifying respirators; )j (8) Instruction in emergency action to be taken in the event of malfunction of the respiratory protective devices; (9) Review of radiation and contamination hazards, including the use of other protective equipment that may be used with respirators; (10) Classroom and field training to recognize and cope with emergency situations. (11) Other instructions as necessary for the specific job to be done, j 6 Y l 6-2
0 n winton PROCEDURE 6-3 Approved tv/ DEC 2 91977 NEGATIVE PRESSURE TEST - Issued COMF0 TYPE RESPIRATOR supersedes NEW SCOPE: This procedure shall be used by the respirator wearer to check for a 4 satisfactory fit every time the Comfo type respirator is donned. (1) Close off the inlet opening of the cannister by covering it with 1 the palm of thi hand. (2) Inhale so that the facepiece collapses slightly and hold your breath for 10 seconds. (3) If the facepiece remains in its slightly collapsid condition and no inward leakage of air is detected, the tightness 'of the respirator is satisfactory. 0 l e l i I l I
- O i
6-3 + l
1 0 n winton ,u - PROCEDURE 6-4 A proved //f/ F 4 IssuepEd 2 s1977 POSITIVE PRESSURE TEST - COMF0 TYPE RESPIRATOR supersedes NEW SCOPE: This procedure shall be used by the respirator wearer to check for a satisfactory fit. (1) Cover the exhalation valve and exhale gently into the facepiece. (2) If a slight positive pressure can be built up inside the facepiece without any evidence of outward leakage the tightness of the respirator is satisfactory. %e e (:) t O e i 9 (~) .v 6-4 I
i i e n.v't. tan 0 PROCEDURE 6-5 Approved g/ CHALLENGE ATMOSPHERE TEST Issued DEC 2 01977 Supersedes NEW SCOPE: This procedure shall be followed whenever a qualitative fitting test is specified on the Health Physics Special Work Permit. (1) Take one stannic chloride glass tube, break off the glass tip on both ends and insert into the rubber squeeze bulb. Caution : This smoke is an eye irritant.
- Instruct respirator wearer to keep eyes closed during test. The individual conducting the test should avoid any direct contact.
(2) Direct a small puff of smoke to each side of the facepiece seal of the respirator. (3) Instruct the wearer to make movements that approximate the anticipated work situation, ex. talking, head movements. (4) Any inward leakage will be immediately noticed by thi wearer as throat and lung irritation. NOTE: A further portion of the smoke tube contents may be used to check ventilation / air flow in the vicinity of the job area. A second chemical cartridge is available for respirator checking. Iscarnyl Acetate tubes can.be used in the same manner and yield a i sweet smdlling organic vapor. However the appropriate respirator I c.icartetdge. for organic vapors must be used for the fitting test. Once proper fit is obtained, then the Type H cartridge can be installed in place of the organic vapor cartridge. D e f Ol \\ j 6-5
l i ? O \\ 0 - n.vt.ta, i Approved ' P10CEDURE 6-6 DEC 2 91977 INSPECTION OF NEW RESPIRATORS I'***d Supersedes NEW l SCOPE: This procedure shall be used to examine new respirators received from the stores inventory. I 3 (1) Examine and check tightness of connections. j (2) Check head bands, facepiece, valves for cracks, worn areas, buckles. l (3) Check mask for any distortion from improper storage. (4) Check for any other visual defect. i O O 4 8 b i e k e I 6-6 i I i
' O 0 n.vt in, .PRGCEDURE 6,7 AD'r*v'd CLEANING AND DISINFECTICN OF Issued DEC 2 91977 RESPIRATORS supersedes NEW SCOPE: This procedure outlines the steps to be followed in order to clean, de-contaminate and disinfect Comfo Type respirators prior to re-use. (1) Used respirators are collected and begged by the Health Physics technician and. brought to the Laboratory. .(2) Remove and dispose of as radioactive waste the used filter cartridges. It is permissible to wipe clean and smear cartridges for re-use providing the length of time at the job and type of job is known to have resulted in minimal particulate loading (non-radioactive as well as radioactive). ~ Oisas_seeb_l,y, (3) Remove straps and then metal face piece by pushing rubber bottom through O, the noie-oo not ettempt to 9uil the race piece orr. (4) Remove intake valves by stretching them around the post holding them to the cartridge receptacle. ~' (5) Remove cartridge receptacles,by stretching then outward and twisting them f ree. (6) ' Remcve exhalation valve covec thus exposing the-plastic exhalation valve. ') (7) Remove the exhalation valve by stretching the respirator horizontally and pushing the valve out. .C_le_aning and Disinfecting (8) Use a MSA cleaner-sanitizer packet or equivalent ~ to make up a cleaning solution. First clean the intake and exhalation valves, ther the other parts. (9) Soak, then brush clean the mask outside, then turn it'inside out to clean the inside with a brush. Clean the cartridge receptacles, straps and facepiece. (10) Rinse all' parts and lay them out to dry. (11) Smear parts to confirm decontamination, g See Procedarc16-8 for Reassembly L 1 i 6-7
k
- O n.,4,,e, o
. PROCEDURE 6-8 Approved PIASSEMBLY AND INSPECTION OF COMF0 TYPE Issued DEC 5 91977 RESPIRATOR supersedes SC0FE: This procedure outlines the steps to be followed for reassembly and inspection of cleaned and disinfected respirators. R.eass.eg! l.y b (1) Insert exhalation valve into mask.;uch that the bar in the center of the valve seat is horizontal. Lift the lip of the exhalation valve over } the mask on the side facing the top of the respirator and stretch the i mask outward and around the exhalation valve. ) (2) Insert the cartridge receptable into the respirator in the same manner as step 1. l ~ NOTE: Be sure that the receptacles are off center facing away from the center of the mask. O (3) Slip the intake valves around the posts on the inside of the cartridge receptacle. I (4) Push the facepiece around the rubber bottom. (5) Add straps. Inspe,clion (6) The entire respirator shall now be inspected. In particular (a) Examine facepiece for:- cracks, scratches (b) Examine valves for: detergent residue, improper. installation. cracks \\ (c) Examine straps for: loss of elasticity, worn areas, broken buckles. (d).ky other visual defects. O' 6-8
l I n.vt ion 0 _ &PalDIX B Approved OPERATION AND MAINTENNICE MANUAL Issued DEC 2 01977 SCOTT AIR PAX supersedes NEW Donnino Sequence 1. Grasp backplate and remove Air-Pak from case. 2. Swing unit up and over Head. 3. Slide unit down back. 4. Connect and' adjust waist belt. 5. Pull down side straps to snug unit on back. 6. Complete operation procedure to put unit into service. Operation and Maintenance Operation Air-Pak II may be safely used in any atmosphere excepting that which irritates or poisons through the skin. To use Air-Pak II perfom the following steps. 1. Check cylinder pressure gauge (14, Figure 7) for " FULL" indication. l-Don the unit as illustrated in figures 1 through 5. i Check' regulator hose coupling (12, Figure 7) for tightness; open cylinder valve 2. (13) approximately two full turns. Rotate cylinder valve safety lock (located on opposite side of cylinder valve from gauge (14)) to center position. Check lock by attempting to close valve. Check regulator pressure gauge (11) for " FULL" indication. 3. Adjust straps on mask " full out". Put mask on " chin first;" adjust chin straps, then temple and forehead straps. 4. To check mask tightness, close off breathing tube (3) at quick connect coupling (4) with thumb or palm of hand and inhale slowly. Mask should collapse to face if leak-tight. If leakage occurs, readjust or repair mask as necessary until mask collapses when inhaling slowly. Test mask exhalation valve (1) by exhaling with breathing tube still closed off. Exhalation should be free of excessive back pressure. B-1 e
so .O O DONNi.JG SEQUENCE... .m ^ .. ; ?, 'gl'.);j [:y, ?[y ct Connect and adjust Grasp backplate and 4,' waist belt. 5 remove Air-Pak f rom - 2 [U $ '~ I f. I case. a -. ~ t . et V-(fd y w ( SwinD unit up and to snug unit on back. .f over head. i G I c } Complete operation i procedure to put unit j Slide unit down back. Int 6 service. I k 2 3
t i i Q u.vt<1nn 0 Approved --.rAPPENDIX B 2...e4 DEC 2 91977 Supersedes NEW ~ 5. Connect breathing tube ('3) to regulator (10) when ready to enter contaminated a rea. I 6. Regulator by-pass valve (red knob) (9) should be closed (full clockwise) and regulator shut-off valve (yellow knob) (8) should be open (full counterclockwise) for nonnal operation. Unit should be stored with valves in these " normal" positions. 7. If during use, autcmatic demand regulator (10) should become damaged or inoperative, ocen emergency by-pass valve (red knob) (9) first. Then depress locking tab (7) { and close regulator shut-off valve (yellow knob),(8). Adjust by-pass valve (red knob) (9) to suit breathing requirements, then leave contaminated area. WARNING This procedure is for emergency exit use only. I The duration of the air supply is greatly reduced. when the unit is operating through by-pass valve. Use this operating mode to escape from area only, l not to continue work. 8. When Pak-Alann bell in regulator (10) starts to ring, it is a warning that only 400 psi of air remain in the cylinder. Leave the contaminated area at once. Changing Air Cylinder Ai r-Pak I cylinder may be changed with the unit donned or laid out. The procedure 1s as follows: 1. Uncouple mask hose quick connect coupling (4) from regulator (10). 2. Release cylinder valve safety lock by raising and rotating the safety lock lever (located on opposite side of cylinder valve from gauge (14)) in either direction. Thenclosecylindervalve(13)). 3. Uncouple regulator hose coupling (12) from cylinder valve (13). 4. Pull cylinder clamping lever (15) to release cylinder. S. Remove cylinder and replace with charged cylinder containing pure breathing Q. air. Cylinder pressure gauge (14) must indicate " FULL" (1800 to 2216 psi). t B-3 l
f i svi enn 0 l APPENDIX A e , PRESS
- GUI5S, Aoorevedh f C,'.I l
i + Issued 1/2/79 c Supersedes 1 i NEW I NPD currently uses a one-of-a-ki.d environmental suit which enables the wearer to perform production operations in an inert
- atmosphere.
Com-bining certain features o f both a supplied air suit and a supplied air hood, the de.vice, called a captive suit by UNC, is a unique approach to working within a controlled a tmo s pi.e r e of inert gas without having to fully enter that atmos'phere. The captive suit is a' half-suit affixed to the underside of a box, not unlike a glove [in a glove box. The' operator raises himself into the half suit via an elevator'such that -only his upper torso is in the suit. 'This arrangement 'e n a b l e s a degree.of freedom unmatched with conventional glove boxes while sti.ll essentially working from the outside. The captive suits have been designed to meet rigid Ype*cifica tio.n s' for' both construction and material (Reference'UNC Specification EE-1042 and AD-107 Certification of material, shrinkage and moisture permeation,- fabric and seam strength, design features, interface provisions, mobility. O, we.ight, leakage and proof pressure tests, helmet and ventilation flows were all verified by UNC and an independent testing.1aboratory. In pcrticular,the. life support air flow to the helmet and the suit cooling air flow to the arms and torso meet specification re'quirements of 5 to 25 CFM at 1" wa,ter and 300 CFM at 4" water respectively. Each press ses an 800 CFM fan to' supply air to each.of three suits involved in the pro-duction operation. It is important to note that there is no distinct separation from general room air. The captive suit is loose enough such that one can look down and see ones feet. The captive s u i,t is not classified as a true respirator as defined by OSHA, N OSH or NUREO-0041. i However, sil aspo::s of our :sspirst:ry'prets: tion program :s descr:2:d in this manual, apply to the operators. E x t e n s.+ i e training is cor. ducted in the use of the captive suits. A bicassay progra= and medical exami-nation progra= are in effect. A rigid inspection and maintenance prairts is conducted on the suits. Cleaning and disinfection is done under health physics and medical cogni:ance. Specification Number EE-1042 Rev. 2, " Environmental Suit - Captive" and BW-346, " Qualification Test Report for a Captive Suit System" submitted by Welson and Co. to UNC, (PO v20936) are incorporated by reference as a cart of this Accendix. (v~h i
,ry ~ ~ Qj u,, w e e 0 Aporoved APPENDIX B Issued DEC 2 9 1977 Supersedes 6. Raise and push cylinder clamping lever (15) to lock cylinder in place and att'ach and tighten regulator hose coupling (12). Unit is then ready to be put into operation. (See Conning and Operation Proc 6 dure). Insoection The following steps outline the inspections required monthly and after each use to insure proper dependable operation of Air-Pak II. 1. Observe cylinder pressure gauge (14) for " FULL" (1800 to 2216 psi) indication. 2. Open cylinder valve (13), connect coupling (4) to regulator and breathe from mask to insure proper operation. Secure unit by closing cylinde'r valve (13), bleeding pressure from regulator (10), and removing coupling (4). g 3. Inspect overall condition of Air-Pak II for deterioration, wear, and other damage. 4. Store unit in carrying case as described under Packing and Storing. Cleaninc After each use remove cylinder from backplate, then clean Air-Pak II components as follows : 1. Wash entire Air-Pak II, except regulator (10), with a solution of detergent and water or soap and water. 2. Rinse mask by flushing water through breathing tube (3) and letting it flow out through openings onto lens. 3. Disinfect mask by sponging with a 70 per cent solution of ethyl alcohol, or a 2 per cent solution of cresol. Rinse and allow to air dry. Polish mask lens, insice and outside, using Scott ICNICLEAN plastic cleaner or equivalent. WARNING Ethyl alcohol is highly volatile and flaamable and is i toxic through inhalation and when taken internally. Use only in well-ventilated ~ area and away frcm flarre or ignition source. l I i t B-4 l i
r O ~ . w o u,, 0 Approved ' APPENDIX B Issued DEC 2 91977 Supersedes NEW P'rotect breathing tube opening of regulator (10) and clean regulator and regulator 4. hose by damp sponging. 5. Clean tarrying case by brushing out (dirt left in case may contaminate Air-Pak II). 6. When thoroughly dry, install a charged cylinder containing pure breathing air. Cylinder pressure gauge (14) must indicate " FULL" (1800 to 2216 psi). Packing and Sto' ring After performing the necessary inspection and clear.ing of Air Pak'II', store it in the carrying case as follows: 1. O Place unit in carrying case, cylinder down as shown in Figure 1. i 2., Connect chest strap (2, Figure 7) and store connected regulator '(10) in corner of case. 3. Make certain waist belt (5) is open and all straps are fully extended, then neatly store all straps. 4. Place mask assembly in front of. case after fully extending all head straps. Take care to protect mask lens from damage. j 5. Before closing case make sure all parts are clear of edges. NOTE Storing Air-Pak II in this manner prepares unit for overhead donning as shown in figures 1 through
- 6.
If alternate donning method is used, storage of straps, etc., should be altered accordingly. 6. If possible, store Air-Pak II in a cool, dry place. O' e 4 . B-5 I
OPEROlON and M AINTENANCE. O O \\ a yr FIGURE 7 ) "'Y gr y LEGEND 15 1. Mask 10xhalation vai.. I 9 2. Chest Strap 1. Itreattiing Tube II. 4. Quick Connert Couplin.: S. Waist Itelt 2,' _j 6. Side Strap hdh I 7 1.ocking Tal, 7 '~q J'Q /dij fl. Shot-Off Valve 0 9. Ily -l'.is s Valv e j / 1 10 Dennand itegislator 'j 4-T j4 11. It egulator I*ressu re (i..uge j i j 0 W J I2. Itegulator flose Couplinn 10 ] y I t 13. Cylinder Valve i l M l -l. Cylinde r Pres su re n... ee lI 5-I 15 Cylinde r Clamping I.. ve r l gy,f L l j i2 .,3 l l l l l i
6 O u., w, 0, APPENDIX C Approved d SURVIVE AIR PAK DEE2 91977 Issued Supersedes NEW (EMERGENCY BREATHING EQUIPMENT) General Descriotion The SURVIVAIR E.B.A. is a small, lightweight, self-contained breathing apparatus de-signed for short duration use of approximately 5 to 10 minutes, depending on the user's exertion. The apparatus is ideal for inspection, trouble shooting, emergency escape, and other short duration operations. It affords complete breathing protection in any contaminated or oxygen deficient atmosphere. NOTE: The E.B.A. may be used safely in any atmosphere except that which contains a contaminant which poisons through the skin, such as hydrogen cyanide. Princioles of Oceration (' The compressed air cylinder.should be charged to 2552 PSI- (2320 + 10%) to obtain the full capacity of 10.8 cubic feet. When recharging the cylinder, it is necessary to utilize a yoke type connection similar to the U.S. Divers #7007 filler and gauge assembly, or the #9352-20 filler adapter, SurvivAir to yoke type connection. After recharging, connect the 1st stage reduction regulator to the cylinder valve by placing the reduction regulator inlet against the "0" Ring seal on the valve. Adjust the regulator so that the hose is directed toward the base of the cylinder valve. Hand tighten the yoke wing nut into the guide hole on the valve., [' On opening the cylinder valve, high pressure air flows into the miniaturized reduction regulator where the pressure is reduced to approximately 110 PSI. The air then flows through the small diameter hose to the 2nd stage demand valve located.at the facepiece. On inhalation, the demand valve opens providing air at atmospheric pressure to the user. On exhalation, the demand valve closes, and the exhaled air is released through the facepiece exhalation valve. The cycle is repeated until the air supply is depleted. NOTE: INCREASING SUCTION EFFORT AND LOW AIR FLOWS GIVE A WARNING OF LOW CYLINDER PRESSURE. WHEN THIS IS EXPERIENCE 0, THE USER SHOULD IttEDIATELY GET OUT OF THE DANGER AREA. Instruction For Use 1. Before donning the apparatus, check the PRESSURE INDICATOR on the cylinder valve. 2. Open the cylinder valve fully by turning counter-clockwise. 3. Remove the mask cover bag and place the neck strap over the ' neck so that the facepiece rests on the chest. C-1
O 0 n.vtsien Approved APPENDIX C ' 05C 2 91977 Issued Supersedes NEW 4. Support the cylinder assembly by holding the SHORT harness with the right hand, lead the long harness strap EVENLY around the waist with the left hand, and snap the clip to the "0" Ring on the short harness. The waist strap now can be adjusted by pulling the strap through the adjustment buckle. The cylinder assembly should rest on the hip and extend down the right leg. Adjust the regulator so that the hose is directly toward the base' of cylinder. If the hose. length is slightly short and restricts normal head movement, the cylinder assembly can be positiened higher on the hip or the reduction regulator can be rotated to provide a longer hose length. 5. The Wearer Is Now In The Stand-By Position. To use the apparatus, it is only necessary to don the facepiece. NOTE: When donning facepiece, adjust all head straps fully out. Pull head harness assembly over the head.and extend the FULL. length down the back of the neck. Place chin against chin guide. Tighten chin straps, then temple and forehead. It is only necessary to tighten comfortably tight. i 6. To remove apparatus, first remove the facepiece by pl' cing the thurrbs and index a fingers on the roller buckles and pull evenly forward, releasing the head straps. NOTE: If the facepiece is removed during a deep inhalation, a steady flow of air i may occur. To stop, simply press the mask against the face. Close the cylinder valve. Remove the air pressure.between. the reduction regulator and demand valve by either depressing the " purge button" on the demand valve or by inhaling in the mask. Dis-g connect waist harness. i 7. Before storing apparatus, recharge or replace cylinder; connect reduction regulator; adjust waist harness to full length, and place mask bag over facepiece. O e-C-2 e
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License SNM-368 Chapter 16 Page 16-1 Docket No. 70-371 Chapter Rev.0 Date:1/22/86 O Chapter 16 - ACCIDENT ANALYSES Potential accidents were discussed and evaluated in Section 4.3.2 of NUREG-1112 and Section 3 of The Radiological Contingency Plan. O l i l Page 16-1 O I 1 -}}