International Isotopes Fluorine Products, Inc. (IIFP) 

A Wholly Owned Subsidiary of 

International Isotopes, Inc. (INIS)

Fluorine Extraction Process & Depleted 

Uranium De-conversion 

 (FEP/DUP) Plant 

License Application 

Chapter 4 

Radiation Protection 

Revision B 

 October 31, 2011 

 

LA-IFP-001 Revision B CHAPTER 4 
 

LA-IFP-001 Revision B CHAPTER 4 October 31 , 2011 

Page 4- ii

TABLE OF CONTENTS 

LIST OF FIGURES .................................................................................................................................. 4-iv 

LIST OF TABLES .................................................................................................................................... 4-iv 

ACRONYMS and ABBREVIATIONS (Provided In License Application Chapter 1 Revision B) 

 

4 RADIATION PROTECTION .......................................................................................................... 4-1

4.1 COMMITMENT TO RADIATION PROTECTION PROGRAM IMPLEMENTATION .... 4-1 

4.1.1 Responsibilities of Key Program Personnel .............................................................. 4-1

4.1.1.1 IIFP Chief Operations Officer .............................................................. 4-2 

4.1.1.2 IIFP Environmental, Safety and Health Manager .................................. 4-2 

4.1.1.3 Radiation Protection Manager ............................................................... 4-2 

4.1.1.4 Radiation Protection Staff ...................................................................... 4-2 

4.1.1.5 Facility Personnel .................................................................................. 4-3 

4.1.2 Independence of the Radiation Protection Program .................................................. 4-3 

4.1.3 Annual Review of the Radiation Protection Program ............................................... 4-3 

4.2 ALARA PROGRAM ............................................................................................................. 4-3 

4.2.1 ALARA Policies and Procedures .............................................................................. 4-4 

4.2.2 ALARA Goals ........................................................................................................... 4-4 

4.2.3 ALARA Committee .................................................................................................. 4-5 

4.3 ORGANIZATION AND PERSONNEL QUALIFICATIONS .............................................. 4-6 

4.4 COMMITMENT TO WRITTEN PROCEDURES ................................................................ 4-7 

4.5 TRAINING COMMITMENTS .............................................................................................. 4-8 

4.5.1 Training of Personnel and Visitors ............................................................................ 4-8 

4.5.2 Level of Training ....................................................................................................... 4-9 

4.5.3 Radiation Protection Training Program .................................................................... 4-9 

4.5.4 Review of Radiation Protection Training Program ................................................. 4-10 

4.6 VENTILATION AND RESPIRATORY PROTECTION PROGRAMS ............................ 4-10 

4.6.1 Ventilation Program ................................................................................................ 4-11

4.6.1.1 Description of Building Ventilation and Process Vents ...................... 4-11 

4.6.1.2 Management Measures for Ventilation Systems ................................. 4-14 

4.6.1.3 Design Criteria for Ventilation Systems .............................................. 4-14 

4.6.1.4 Testing of Ventilation Systems ............................................................ 4-16 

4.6.2 Respiratory Protection Program .............................................................................. 4-17 

4.6.2.1 Respiratory Protection Requirements; 10 CFR 20, Subpart H ............ 4-17 

4.6.2.2 Procedures for Using Respiratory Protection Equipment .................... 4-17

4.7 RADIATION SURVEYS AND MONITORING PROGRAMS ......................................... 4-19 

4.7.1 Radiation Surveys and Monitoring Programs Meeting Requirements ......................... 

 of 10 CFR 20, Subpart F ......................................................................................... 4-19 

4.7.2 Approved Procedures for Radiation Surveys and Monitoring Programs ................ 4-20 

4.7.3 External Occupational Radiation Exposures ........................................................... 4-20 

4.7.4 Internal Occupational Radiation Exposures ............................................................ 4-20 

4.7.4.1 Urinalysis Program .............................................................................. 4-21 
 

LA-IFP-001 Revision B CHAPTER 4 October 31 , 2011 

Page 4- iii

TABLE OF CONTENTS (Continued)

4.7.4.2 In Vivo Lung Counting Program ......................................................... 4-21 

4.7.5 Summation of External and Internal Occupational Radiation Exposures ............... 4-21 

4.7.6 Air Sampling Program............................................................................................. 4-22 

4.7.7 Control of Airborne Radioactive Material .............................................................. 4-22 

4.7.8 Minimization of Contamination .............................................................................. 4-22 

4.7.9 Contamination Survey Program .............................................................................. 4-23 

4.7.10 Corrective Action Program for Personnel Contamination ...................................... 4-23 

4.7.11 Corrective Action Program for Airborne Occupational Exposure .......................... 4-24

4.7.12 Equipment and Instrumentation Sensitivity ............................................................ 4-24 

4.7.13 Policies for Removal of Equipment and Materials from Radiological 

 Controlled Areas ..................................................................................................... 4-24 

4.7.14 Sealed Sources ......................................................................................................... 4-25 

4.7.15 Access Control ........................................................................................................ 4-25 

4.7.16 Radiation Reporting Program .................................................................................. 4-26 

4.8 ADDITIONAL PROGRAM COMMITMENTS ................................................................. 4-27 

4.8.1 Records .................................................................................................................... 4-27 

4.8.2 Event Reporting ....................................................................................................... 4-27 

4.8.3 Annual Dose Monitoring Report ............................................................................. 4-27 

4.8.4 Corrective Action Reporting ................................................................................... 4-27 

REFERENCES .................................................................................................................................. 4-28 

 
 

LA-IFP-001 Revision B CHAPTER 4 October 31 , 2011 

Page 4- iv

LIST OF FIGURES 

Figure 4-1 IIFP Plant Operation Organization ..................................................................................... 4-7

LIST OF TABLES 

Table 4-1 Design Criteria for Vent Off-gas Treatment Equipment ................................................... 4-15
LA-IFP-001 Revision B CHAPTER 4 October 31, 2011 

Page 4-1

4 RADIATION PROTECTION 

International Isotopes Fluorine Products, Inc. (IIFP), a wholly owned subsidiary of International Isotopes, 

Inc. (INIS), will build and operate a depleted uranium processing facility near Hobbs in Lea County, New 

Mexico. The IIFP Facility (also referred to as the FEP/DUP Plant) is being licensed under Title 10 Code 

of Federal Regulations (CFR) Part 40. A description of the planned facility is provided in the IIFP 

License Application (LA), Revision B Chapter 1 “General Information.” 

Chapter 4 addresses the IIFP commitment to radiation protection and the policies and procedures to 

maintain doses to the workers, the public and the environment as low as reasonably achievable (ALARA). 

4.1 COMMITMENT TO RADIATION PROTECTION PROGRAM IMPLEMENTATION 

This section describes the facility Radiation Protection Program (RPP). The RPP provides the foundation 

necessary to protect the radiological health and safety of the workers, the environment and the public and 

complies with the regulatory requirements of 10 CFR 19, “Notices, Instructions and Reports to Workers: 

Inspection and Investigations,” (CFR, 2008a); 10 CFR 20, “Standards for Protection Against Radiation,” 

(CFR, 2008b) and 10 CFR 40, “Domestic Licensing of Source Material”, (CFR, 2008c).

Specifically, the RPP meets the requirements of 10 CFR 20 Subpart B, “Radiation Protection Programs,” 

(CFR, 2008d), and is consistent with the guidance provided in Regulatory Guide 8.2, “Guide for 

Administrative Practices in Radiation Monitoring,” U.S. Nuclear Regulatory Commission (NRC) (NRC, 

1973). In accordance with 10 CFR 20.1101 (CFR, 2008e), the RPP uses approved written procedures and 

engineering controls based on sound radiation protection principles to achieve occupational and public 

doses below the NRC established limits and to maintain exposure to radiation ALARA. Occupational 

exposures are maintained ALARA through the following: 

• Exposure monitoring is consistent with guidance in 10 CFR 20.1501, “General” (CFR, 2008f)

and 10 CFR 20.1502, “Conditions Requiring Individual Monitoring of External and Internal 

Occupational Dose,” (CFR, 2008g) 

• Frequent interactions between the Radiation Safety Committee and Operations personnel 

• Annual RPP assessments with senior management 

Occupationally exposed personnel annual exposure goals will be established to ensure that personnel 

doses received are below the limits specified in 10 CFR 20.1201 (CFR, 2008h). The RPP content and 

implementation are reviewed annually, at a minimum, as required by 10 CFR 20.1101(c) (CFR, 2008e). 

In addition, controls are established such that no member of the public is expected to receive a total 

effective dose equivalent (TEDE) in excess of 0.25 millisieverts per year (mSv/yr) or 25 millirems per 

year (mrem/yr). 

4.1.1 Responsibilities of Key Program Personnel 

The key program personnel play an important role in the protection of workers and the environment as 

well as the implementation of the ALARA Program. Revision B Chapter 2 “Organization and 

Administration” of the IIFP LA describes the facility, organization and administration in further detail. 

Staffing is consistent with guidance provided in Regulatory Guide 8.2 (NRC, 1973) and Regulatory 

Guide 8.10, “Operating Philosophy for Maintaining Occupation Radiation Exposures As Low As Is 

Reasonably Achievable,” (NRC, 1977). 
LA-IFP-001 Revision B CHAPTER 4 October 31, 2011 

Page 4-2

4.1.1.1 IIFP Chief Operations Officer 

The Chief Operations Officer (COO) has the overall responsibility of ensuring that facility operations are 

conducted in a manner that protects the employee, the environment and the public from radiological, 

chemical and industrial hazards and that operations are carried out in accordance with all applicable 

regulations, licenses and permits. The duties of the COO are performed in accordance with written 

policies and procedures. The COO provides for safety and control of operations and protection of the 

environment by delegating and assigning responsibility to qualified plant and line supervisors. These 

qualifications are detailed in Revision B Chapter 2 of the IIFP LA. 

4.1.1.2 IIFP Environmental, Safety and Health Manager 

The Environmental, Safety and Health (ESH) Manager reports to the COO, but also has an interacting 

relationship with all IIFP managers on matters of ESH policies, regulatory requirements, plant safety and 

environmental compliance. The ESH Manager has responsibility for directing the activities to ensure the 

facility complies with appropriate rules, regulations and codes. This includes ESH activities associated 

with radiation protection, chemical safety, environmental protection, industrial safety/industrial hygiene, 

emergency preparedness/security, regulatory affairs and licensing. The ESH Manager works with other 

managers and supervisors of the plant for ensuring consistent interpretations of the requirements, 

performing independent reviews and supporting facility and operations change control reviews. The ESH 

organization provides independent oversight of plant operations relative to ESH compliance, specific 

descriptions of responsibilities and authority. Qualifications for the ESH Manager position are provided 

in the IIFP LA, Revision B Chapter 2. 

4.1.1.3 Radiation Protection Manager 

The Radiation Protection Manager (RPM) reports to the ESH Manager and is responsible for 

implementing the RPP. In matters involving radiation protection unresolved concerns, the RPM has direct 

access to the COO. The Radiation Protection staff, including engineers, technicians, administrative 

support personnel and contractors specifically assigned to the Radiation Protection Program report to the 

Radiation Protection Manager. The RPM ensures that the facility is staffed with suitably trained radiation 

protection personnel and that sufficient resources are provided to implement an effective program. 

Specific descriptions of the RPM responsibilities, authority and qualifications are provided in Revision B 

Chapter 2 of the IIFP LA. 

4.1.1.4 Radiation Protection Staff 

The Radiation Protection Manager and his/her staff are responsible for: 

• Establishing and maintaining the RPP

• Developing and maintaining procedures necessary to implement the RPP

• Establishing and maintaining an ALARA Program

• Reviewing and auditing the efficacy of the RPP in complying with applicable federal and state 

regulations and NRC license conditions

• Adequately staffing the Radiation Protection organization to implement the RPP

• Establishing and maintaining a Respiratory Protection Program

• Developing and maintaining an internal and external dosimetry program

• Calibration and quality assurance of radiological instrumentation, including verification of 

required Lower Limits of Detection or alarm levels
LA-IFP-001 Revision B CHAPTER 4 October 31, 2011 

Page 4-3

• Establishing and maintaining a Radiation Safety Training Program 

• Establishing and maintaining the Radiological Environmental Monitoring Program (REMP)

• Ensuring Restricted and Radiological Controlled Areas (RCAs) are posted in accordance with 

regulations and license conditions and developing occupancy guidelines as needed. 

4.1.1.5 Facility Personnel 

Facility personnel are required to work safely and to follow the rules, regulations and procedures that 

have been established for their protection and the protection of the public and environment. Personnel 

whose duties require working with radioactive material, entering radiation areas, controlling facility 

operations that could affect effluent releases or directing the activities of others are trained such that they 

understand and effectively carry out their responsibilities relative to the RPP. 

4.1.2 Independence of the Radiation Protection Program 

The RPP remains independent of the routine production operations of the facility. The management of the 

RPP is conducted through the ESH Manager and the RPM. 

4.1.3 Annual Review of the Radiation Protection Program 

In accordance with 10 CFR 20.1101(c) (CFR, 2008e), the RPP is reviewed annually by the ALARA 

Committee. The review considers facility changes, new technologies and other process enhancements that 

could improve overall program effectiveness. Further detail regarding the review is provided in Section 

4.2. 

4.2 ALARA PROGRAM 

This section describes the IIFP commitment to an ALARA Program. The ALARA Program functions as 

a subset of the RPP. The objective of the Program is to make every reasonable effort to maintain facility 

exposures to radiation as far below the dose limits of 10 CFR 20.1201 (CFR, 2008h) as is reasonably 

achievable and to maintain radiation exposures to members of the public such that they are not expected 

to receive the dose limits of 10 CFR 20.1101(d) (CFR, 2008e). The design and implementation of the 

ALARA Program is consistent with guidance provided in Regulatory Guide 8.2 (NRC, 1973), Regulatory 

Guide 8.13 “Instruction Concerning Prenatal Radiation Exposure,” (NRC, 1999a), Regulatory Guide 

8.29, “Instruction Concerning Risks from Occupation Radiation Exposure,” (NRC, 1996) and Regulatory 

Guide 8.37 “ALARA Levels for Effluents from Materials Facilities,” (NRC, 1993).

Features of the ALARA Program include: 

• Management commitment demonstrated through a written policy statement, procedures, other 

directives and periodic management reviews 

• Formal program audits conducted on at least an annual basis 

• Well-supervised and defined radiation protection capability including appropriately qualified and 

trained supervisors and technicians. All personnel on site have the authority to stop work as 

needed to ensure appropriate safety precautions are observed. 
LA-IFP-001 Revision B CHAPTER 4 October 31, 2011 

Page 4-4

• Training for the workforce including training consistent with the requirements of 10 CFR 19.12 

(CFR, 2008i) and incorporating appropriate portions of the guidance provided in Regulatory 

Guides 8.13 (NRC, 1999a) and 8.29 (NRC, 1996) 

• Appropriate authority vested in radiation protection personnel including stop work authority 

• Consideration of the need for plant modifications as warranted for reducing exposures and doses 

to personnel 

Documented RPP policies are implemented to ensure that ALARA goals are met. Procedures incorporate 

the ALARA philosophy into routine operations and ensure exposures are maintained below 10 CFR 

20.1101 limits (CFR, 2008e). As discussed in Section 4.7, “Radiation Surveys and Monitoring Program 

Commitments,” RCAs will be established within the facility. These areas are identified by the use of 

signs, ropes, gates, fences or other visible means. Each zone will have specific entry requirements, 

survey requirements and dosimetry requirements. The establishment of these areas supports the ALARA 

commitment to minimize the spread of contamination and reduce unnecessary exposure of personnel to 

radiation. 

4.2.1 ALARA Policies and Procedures 

To ensure occupational doses are maintained, ALARA work activity restrictions are imposed when an 

individual’s exposure exceeds 80% of the applicable 10 CFR 20.1201 limit (CFR, 2008h). 

Doses to declared pregnant workers are maintained below the regulatory limit specified in 10 CFR 

20.1208, “Dose Equivalent to an Embryo/Fetus,” (CFR, 2008j) and are maintained ALARA. Female 

employees are advised of the RPP policy for declared pregnant workers during basic radiation safety 

training. The policy for occupational exposures to declared pregnant workers is consistent with the 

guidance in Regulatory Guide 8.13 (NRC, 1999a). 

Approved written procedures dictate that atmospheric releases are to be monitored and measured. Doses 

to the public are calculated to ensure compliance with the requirements of 10 CFR 20.1101(d) (CFR, 

2008e). Numerous controls exist to ensure public exposure resulting from operations remains below 

limits specified in 10 CFR 20.1301, “Radiation Dose Limits for Individual Members of the Public,” 

(CFR, 2008k). See the IIFP LA, Revision B Chapter 9 “Environmental Protection” for further 

information regarding implemented measures to keep public doses ALARA. 

4.2.2 ALARA Goals 

In accordance with 10 CFR 20.1101 (CFR, 2008e), the RPP is designed to achieve occupational and 

public doses that are ALARA. The Radiation Protection Manager is responsible for the implementation 

of the ALARA Program. The ALARA Committee provides oversight of the RPP as described in Section 

4.2.3 “ALARA Committee.” In order to keep exposures ALARA, the following principles guide the 

RPP: 

• Radiation exposures and the release of radioactive effluents shall be monitored. 

• Individual exposures shall be controlled to less than applicable regulatory limits. 

Specific goals of the ALARA Program include maintaining occupational exposures, as well as 

environmental releases, as far below regulatory limits as is reasonably achievable. With respect to 

environmental effluents, ALARA Goals will be initially set at 20% in accordance with Appendix B, 10 
LA-IFP-001 Revision B CHAPTER 4 October 31, 2011 

Page 4-5

CFR Part 20 values (CFR, 2007). The ALARA concept is also incorporated into the design and operation 

of the facility. The size and number of areas with higher dose rates are minimal. Per approved written 

procedures, the time spent in these areas is controlled and projects are evaluated to ensure workers receive 

the minimum exposure. Areas where personnel spend significant amounts of time are designed to 

maintain the lowest dose rates reasonably achievable. 

The RPM is responsible for implementing the ALARA Program and ensuring that adequate resources are 

committed to make the program effective. The RPM ensures that an annual ALARA Program evaluation 

report is prepared and submitted to the COO and the ALARA Committee. The report reviews the 

following: 

• Radiological exposure and effluent release data for trends 

• Audits and inspections 

• Use, maintenance and surveillance of equipment used for controlling exposures and effluents 

• Other issues, as appropriate, that may influence the effectiveness of the RPP and ALARA 

Program 

4.2.3 ALARA Committee 

The IIFP ALARA Committee supports the Facility Safety Review Committee (FSRC) and is represented 

in the Figure 4-1 Plant Operation Organization “FSRC” box that reports to the COO. The ALARA 

Committee consists of key members of facility management, supervision and the workforce and will meet 

periodically on a frequency established in the IIFP Facility ALARA Program. The ALARA Committee 

uses the guidance provided in Regulatory Guides 4.21, “Minimization of Contamination and Radioactive 

Waste Generation: Life-Cycle Planning,” (NRC, 2008), 8.10 (NRC, 1977) and 8.37 (NRC, 1993) to 

formulate facility operating philosophy in reducing exposures. Membership of the ALARA Committee 

includes: 

• The Chief Operations Officer 

• The Radiation Protection Manager 

• Selected department managers 

• The Environmental, Safety and Health Manager 

• Selected supervisors and hourly personnel 

The ALARA Program facilitates interaction between radiation protection and operations personnel. The 

ALARA Committee is utilized in achieving this goal. 

The ALARA Committee's activities include at a minimum an annual review of the following: 

• Reviewing site radiological operating performance including trends in airborne concentrations, 

personnel exposures and environmental monitoring results 

• Reviewing operations and exposure records to determine where exposures may be reduced 

• Reviewing employee training and methods for utilizing information on-the-job to keep exposure 

ALARA Reviewing potential modifications of procedures and equipment when changes will 

reduce exposure at reasonable cost 

In addition, the ALARA Committee reviews major changes in authorized activities affecting radiation 

protection practices and evaluates contamination minimization and/or removal activities. 
LA-IFP-001 Revision B CHAPTER 4 October 31, 2011 

Page 4-6

The proceedings, findings and recommendations of the ALARA Committee are reported in writing to the 

COO and appropriate line management and area managers responsible for those operations reviewed by 

the Committee. Such reports are retained for a minimum of three (3) years. Based upon expected 

improvement, updated performance data, economics and consideration of other site priorities, 

management decides which of the ALARA Committee recommendations will be pursued. If a specific 

recommendation is pursued, a task owner is assigned and the action is tracked to completion. 

4.3 ORGANIZATION AND PERSONNEL QUALIFICATIONS 

The Radiation Protection staff is assigned responsibility for implementation of the Radiation Protection 

Program functions. Only suitably trained radiation protection personnel are employed at the facility. 

Staffing is consistent with the guidance provided in Regulatory Guides 8.2 (NRC, 1973) and 8.10 (NRC, 

1977). The qualifications of the RPM are described in Revision B Chapter 2 of the IIFP LA. 

Qualifications of the staff Health Physicists and Radiation Control Technicians are described below. 

The RPM reports directly to the ESH Manager and has the responsibility for establishing and 

implementing the RPP. These duties include the training of personnel in use of equipment, control of 

radiation exposure of personnel, continuing evaluation and determination of the radiological status of the 

facility and conducting the REMP. The facility organization chart establishes clear organizational 

relationships among the radiation protection staff and the other facility line managers. The facility 

organization is shown in Figure 4-1. 

In matters involving radiological protection, the Radiation Protection Manager has responsibility and 

authority to elevate any unresolved radiation safety or environmental issue to the COO. The RPM is 

skilled in the interpretation of radiation protection data and regulations and is familiar with the operation 

of the facility and radiation protection concerns relevant to the facility. The Radiation Protection 

Manager is a resource for radiation safety management decisions. 

Radiation Protection technicians, engineers and supervisors perform the functions of assisting and guiding 

workers in radiological aspects of the job. These individuals have the responsibility and authority to stop 

work or mitigate the effect of an activity if it is suspected that the initiation of or continued performance 

of a job, evaluation or test will result in the violation of approved radiation protection requirements. 

Staff Health Physicists shall have as a minimum a bachelor’s degree in engineering or a scientific field 

and experience commensurate with health physics and radiation protection duties. 

Staff Radiation Control Technicians shall have a high school diploma and experience commensurate with 

radiation control duties. 
LA-IFP-001 Revision B CHAPTER 4 October 31, 2011 

Page 4-7

Figure 4-1 IIFP Plant Operation Organization 

4.4 COMMITMENT TO WRITTEN PROCEDURES 

Operations at the IIFP Facility involving licensed materials are conducted through the use of approved 

written procedures. Radiation protection procedures are prepared, reviewed and approved to carry out 

activities related to the RPP. Approved written procedures are used to control radiation protection 

activities in order to ensure that the activities are implemented in a safe, effective and consistent manner. 

Radiation protection procedures are reviewed and revised, as necessary, to incorporate facility or 

operational changes or changes to the IIFP Integrated Safety Analysis (ISA) Summary. 

The radiation protection staff prepares draft procedures that are reviewed by affected personnel to ensure 

the procedures are appropriate and reasonable to implement. The Radiation Protection Manager, or 

Designee, reviews and approves final radiation protection procedures as well as proposed revisions to 

radiation protection procedures. Revision B Chapter 11 “Management Measures” of the IIFP LA provides 

additional information on IIFP procedures. 
LA-IFP-001 Revision B CHAPTER 4 October 31, 2011 

Page 4-8

Routine work involving licensed materials is administered by the use of approved procedures. IIFP uses a 

structured procedure development, review and control systems approach to ensure safety and health 

requirements are appropriately incorporated into working procedures, i.e., use of cross-discipline reviews 

in the development or change of procedures. The IIFP process for developing and controlling procedures 

is described in the IIFP License Application Revision B Chapter 11 Sections 11.4.2, 11.4.3, 11.4.4 and 

11.4.5. Non-routine activities, particularly those performed by non-IIFP employees generally not covered 

by approved written procedures, are administered by the Radiation Work Permit (RWP) system. The 

RWP provides a description of the work to be performed defining the authorized activities. The RWP 

specifies the necessary radiation safety controls, as appropriate, to include personnel monitoring devices, 

attendance of radiation protection staff, protective clothing, respiratory protective equipment, special air 

sampling and additional precautionary measures to be taken. The RWP also contains a description of the 

radiological conditions in the immediate work area covered by the RWP. The RWP requires approval by 

the Radiation Protection Manager or his/her Designee. The Designee must meet the qualification 

requirements of Radiation Protection Manager. RWPs have a predetermined period of validity with a 

specified expiration or termination time. Standing RWPs may be issued for routinely performed activities 

such as tours of the IIFP Facility. 

Prior to commencing work that requires a Radiation Work Permit, employees performing the job must 

review the RWP and document their review. Work is monitored, as required, by a radiation protection 

technician. RWPs are available to workers for re-review at any time and include expiration dates. A 

radiation protection technician or the RPM, or Designee, reviews the status of issued RWPs on a periodic 

basis. RWPs are closed when the applicable work activity for which it is written is complete and 

terminated. A copy of RWPs and any associated records are kept for the life of the facility. 

4.5 TRAINING COMMITMENTS 

The design and implementation of the Radiation Protection Training Program complies with the 

requirements of 10 CFR 19.12 (CFR, 2008i). Records are maintained in accordance with 10 CFR 

20.2110 (CFR, 2008l). The development and implementation of the Radiation Protection Training 

Program is consistent with the applicable guidance provided in the following regulatory guidance 

documents: 

• Regulatory Guide 8.10, “Operation Philosophy for Maintaining Occupational Radiation 

Exposures As Low As is Reasonably Achievable,” (NRC, 1977) 

• Regulatory Guide 8.13, “Instructions Concerning Prenatal Radiation Exposure,” (NRC, 1999) 

• Regulatory Guide 8.29, “Instructions Concerning Risks from Occupational Radiation Exposure,” 

(NRC, 1996) 

• ASTM C986-89, “Developing Training Programs in the Nuclear Fuel Cycle,” (ASTM, ASTM 

C986-89, 1989) 

• ASTM E1168-95, “Radiological Protection Training for Nuclear Facility Workers,” (ASTM, 

1995) 

4.5.1 Training of Personnel and Visitors 

Training programs are established for various job functions commensurate with radiation protection 

responsibilities. Visitors to restricted areas are either trained in the formal Radiation Protection Training 

Program or are given a general training session regarding radioactive materials in the workplace and are 

escorted by trained personnel. 
LA-IFP-001 Revision B CHAPTER 4 October 31, 2011 

Page 4-9

The periodicity of refresher training required by a worker is dependent on the worker’s responsibilities, 

however, the basic refresher training occurs annually (not to exceed 15 months) and includes an exam. 

Training requirements are documented and tracked for employees. Training records are managed and 

stored in accordance with 10 CFR 20.2110 (CFR, 2008l). 

4.5.2 Level of Training 

The level of radiation protection training is based on the potential radiological health risks associated with 

an employee’s work responsibilities and incorporates the provisions of 10 CFR 19.12 (CFR, 2008i). In 

accordance with 10 CFR 19.12(a) (CFR, 2008i) any individual working at the facility likely to receive, in 

one (1) year, an occupational dose in excess of 1 mSv (100 mrem) is: 

• Informed of the storage, transfer or use of radioactive material 

• Instructed in health protection issues associated with exposure to radiation and radioactive 

material, precautions or procedures to minimize exposure and the purposes and functions of 

protective devices employed 

• Required to observe, to the extent within the worker’s control, the applicable provisions of the 

NRC regulations and licenses for protection of personnel from exposure to radiation and 

radioactive material 

• Instructed of their responsibility to promptly report to management any condition that may lead to 

or cause a violation of NRC regulations and licenses or result in unnecessary exposure to 

radiation and radioactive material 

• Instructed on the appropriate response to warnings made in the event of any unusual occurrence 

or malfunction that may involve exposure to radiation and radioactive material 

• Advised of the various notifications and reports that a worker may request pursuant to 

10 CFR 19.13 (CFR, 2008m), “Notifications and Reports to Individuals” 

In accordance with 10 CFR 19.12(b) (CFR, 2008i), management considers the worker’s assigned 

activities during normal and abnormal situations when determining if a worker is likely to receive a dose 

of 1 mSv (100 mrem). The instructions provided to the worker as described above are commensurate with 

potential radiological conditions present in the workplace. 

The RPM is responsible for establishing and maintaining the radiation protection training for all 

personnel including contractor personnel who may be working at the facility. Records are maintained for 

each employee documenting the training date, scope of training, identity of the trainer, any test results and 

other associated information. 

4.5.3 Radiation Protection Training Program 

The Radiation Protection Training Program complies with 10 CFR 19.12 (CFR, 2008i) and 10 CFR 

20.2110 (CFR, 2008l) requirements and takes into consideration a worker’s normally assigned work 

activities. The following topics are covered during basic radiation protection training: 

• Radiation safety principles, policies and procedures 

• Radiation hazards and health risks 
LA-IFP-001 Revision B CHAPTER 4 October 31, 2011 

Page 4-10

• Correct handling of radioactive materials 

• Location of and adherence to RPP procedures 

• Minimization of exposures to radiation and radioactive materials 

• Contamination control 

• Access and egress controls 

• Monitoring for internal and external exposures 

• ALARA and exposure limits 

• Exposure monitoring methods and instrumentation 

• Personal and area dosimetry 

• Donning and doffing of personal protective equipment (PPE) 

• Emergency response 

The radiation protection staff shall be trained in the following radiation protection areas: 

• Radiological Fundamentals 

• Biological Effects 

• Radiation Limits 

• ALARA Program 

• Personnel Monitoring Programs 

• Radiological Access and Control Postings 

• Radiological Emergencies 

• Practical Factors (e.g., RWPs, dosimeters, contamination control, emergency response, protective 

clothing) 

In addition, radiation protection staff will be trained on all applicable RPP procedures and policies and 

receive appropriate on-the-job training (OJT) based on their job requirements. Training materials as well 

as those qualified to provide the training will be approved by the RPM. 

4.5.4 Review of Radiation Protection Training Program 

The contents of the Radiation Protection Training Program are reviewed bi-annually by the RPM. The 

review addresses changes in policies, procedures and requirements and changes to the ISA Summary. 

As described in the IIFP LA, Revision B Chapter 11 Section 11.3.8, the Radiation Protection Training 

Program is systematically evaluated to measure the program's effectiveness in producing competent 

employees. The RPM will review the evaluation information and implement changes in the training 

program as necessary. 

4.6 VENTILATION AND RESPIRATORY PROTECTION PROGRAMS 

In accordance with the regulations in 10 CFR 20, Subpart H, “Respiratory Protection and Controls to 

Restrict Internal Exposure in Restricted Areas,” (CFR, 2008n), control of the release of radiation or 

radioactive materials is a fundamental requirement for facility and equipment design for areas in which 

uranium and other sources of radiation are handled or used in processes. The following section describes 

the design and management measures taken to ensure that the installed ventilation and containment 

systems operate effectively. The section also describes the worker Respiratory Protection Program. 
LA-IFP-001 Revision B CHAPTER 4 October 31, 2011 

Page 4-11

4.6.1 Ventilation Program 

The confinement of uranium is a design requirement for the facility. The internal radiation exposure of 

workers is controlled primarily by the containment of uranium materials within the respective process 

equipment. 

Areas where uranium is processed that have potential of producing dusts, mists or fumes containing 

uranium and other areas where toxic chemicals are processed or produced are provided with dust 

collection and/or scrubber systems to protect employees and the environment at exposure levels that are 

ALARA. 

4.6.1.1 Description of Building Ventilation and Process Vents 

Building ventilation systems control the temperature and the humidity of the indoor air. General 

ventilation systems are used in areas where uranium is processed or handled and consist of fresh-air 

intakes and roof exhaust fans. Roof-exhaust fans and other gaseous effluent emission sources in buildings 

where uranium is processed or handled will be equipped with exhaust monitoring. The Effluent 

Monitoring Program is described in the IIFP Environmental Report (ER), Revision B Chapter 6 Section 

6.1.1; more specifically in Section 6.1.1.1 and Table 6-1, “Gaseous Effluent Sampling Program.” 

During the detailed design of the IIFP process buildings, the ventilation requirements and design 

specifications will be determined for each specific building and process area where applicable. The 

methodology will include calculation of the free volumes of buildings including partitioned areas and 

floor levels once the equipment locations, layout and equipment volumes are designed, scaled and 

finalized. Ventilation air turn-over rates will be determined based on code and comfort requirements and 

specifications. Intakes and exhausts for ventilated areas will be specifically located to satisfy the defined 

specifications for turn-over, air distribution and mixing. The consequence calculations for the accident 

sequences involving the worker and the public will then be updated based on the actual detailed design air 

dispersion volumes, dilutions and mixing. For the public consequence evaluation, the detailed design will 

provide specific ventilation exhaust locations, velocities, potential release points and flow rates to allow 

verification of assumptions and conservatism made in the current analysis that has been based on 

conceptual design of the IIFP Facility and to revise those if needed. 

Area Process Control Rooms that are routinely occupied by workers have environments maintained for 

comfort and safety. All Control Rooms located in process areas where uranium or hazardous chemicals 

are processed, stored or handled and have separate heating, ventilation and air conditioning (HVAC) 

systems. The Control Rooms are maintained at a slight positive pressure with dual fresh air intakes 

located at safe distances from process vent stacks, exhaust fans and equipment containing hazardous 

chemicals. 

In the production of depleted uranium tetrafluoride (DUF4), a feed supply of depleted uranium 

hexafluoride (DUF6) is reacted with gaseous hydrogen in a reaction vessel to produce DUF4 and gaseous 

anhydrous hydrofluoric acid (AHF). The DUF6 feed cylinder autoclaves provide secondary containment 

in event of leakage of a heated DUF6 cylinder or connection. The autoclave area is separated from the 

other processes by a fire barrier wall and has its own separate building ventilation intakes and roof 

exhaust fans. Fluoride and radiation detection monitors and alarms are strategically located within the 

Autoclave and DUF4 Buildings. 

The solid particulate DUF4 exits the bottom of the reaction vessel and is sent to temporary storage vessels 

for later use in the production of fluoride gas products. The off-gas from the reaction vessel primarily 
LA-IFP-001 Revision B CHAPTER 4 October 31, 2011 

Page 4-12

contains: 1) AHF with some small quantities of un-reacted gaseous hydrogen, 2) small quantities of 

particulate DUF4 entrained in the gas stream and 3) potential traces of un-reacted DUF6. The off-gas 

stream passes through a set of filters to remove entrained particles of DUF4 from the gas stream. The 

filtered gas stream then flows through a series of carbon-filled bed filters designed to remove traces of 

DUF6 and any carryover of DUF4. The off-gas flow exits the carbon-bed filter system and in the next step 

the gaseous AHF by-product is removed by a two-stage condensing process. The collected liquid AHF is 

drained to temporary storage tanks located within a containment-type building where the AHF later can 

be loaded into approved truck trailers and shipped to customers. The residual off-gas stream exits the 

AHF condensing system and is passed through a gas-fired burner system to combust excess hydrogen. 

The gas stream then flows through a three-stage Plant KOH (potassium hydroxide) Scrubbing System for 

final treatment. 

In the Plant KOH Scrubbing System, the final off- gas stream is contacted with KOH solution in a series 

of steps where essentially all of the remaining fluoride-bearing components are removed prior to venting 

to the atmosphere through a stack. The Plant KOH Scrubbing System is utilized to treat final off-gas 

streams from both the DUF4 production process (DUF6 to DUF4) and the fluoride gas products (fluorine 

extraction process, FEP). The three-stage Plant KOH Scrubbing System is designed for removing 

fluoride bearing components in the gas streams at efficiencies of greater than 80%, 95% and 99% for the 

first, second and third stages, respectively. The overall system removal efficiency for normal operations 

is designed at greater than 99.9 %. The Plant KOH Scrubbing System stack is continuously sampled and 

routinely analyzed to measure for traces of fluorides and uranium in the vent gas. 

The Plant KOH Scrubbing System solution is recycled within each of the scrubbers until the 

concentration of KOH needs replenishment. The KOH solution concentration is maintained at a safe 

margin to ensure it effectively reacts (scrubs) with fluoride components in the gas stream. The spent 

scrubbing solution containing potassium fluoride (KF), water and some excess KOH is pumped to the 

Environmental Protection Process (EPP) where the solution is treated with lime (CaOH2) to form solid 

particulate calcium fluoride (CaF2) and regenerated KOH. The resulting products are filtered and the 

CaF2 is dried and prepared for shipment to customers or to a licensed Resource Conservation and 

Recovery Act (RCRA) disposal facility if the CaF2 is determined to be a RCRA waste. Representative 

samples of dried CaF2 ready for shipment are analyzed for uranium prior to leaving the plant. The KOH 

liquor is regenerated at a concentration suitable for pumping back to the Plant KOH Scrubbing System for 

reuse. 

In areas where uranium particulate solids are handled or processed, equipment and systems are provided 

for dust capture and collection. The two-stage dust collection systems are filter-type dust collectors that 

are used to remove the uranium-bearing particulates prior to discharging the air flow through a vent stack 

to the atmosphere. Equipment where uranium bearing powders are handled or stored, such as storage 

hoppers and enclosed drum packaging stations, are connected to the dust collection intake header ducts. 

Uranium particulates (powders) captured by the dust collection systems are either recycled back into the 

respective process operations or packaged and sent to a licensed off-site disposal facility. 

Sampling and analysis are routinely conducted for uranium between each of the dust collector units. If an 

unacceptable level of uranium carryover is detected on any given filter unit, the unit is removed from onstream service and investigated and corrective action is taken. Additionally, each dust collector is 

continuously monitored for differential pressure across the filter sections to ensure filter integrity is 

maintained. Descriptions of the dust collector shutdown features are provided in the IIFP ISA Summary, 

Revision B Section 3.1.2.5, subsection “Dust Collectors in the DUF4 Building” and Section 3.1.3.2, 

subsection “Dust Collector and Hood Vent Equipment.” 
LA-IFP-001 Revision B CHAPTER 4 October 31, 2011 

Page 4-13

The fluoride products operations (FEP) are located in a building separate from the DUF4 production 

process. DUF4 powder is conveyed through contained piping to the FEP Building where it is pre-mixed 

and reacted with either silicon dioxide (SiO2) or boron oxide (B2O3) to produce the silicon tetrafluoride 

(SiF4) or boron trifluoride (BF3) gas products, respectively. 

In the SiF4 process, the DUF4 and SiO2 are mixed in the desired ratios and fed directly to a rotary calciner. 

Two flow streams exit the rotary calciner and are described as follows: 

1) One flow stream is the product off-gas that contains some vapors of hydrogen fluoride (HF) and 

fluorosilic acid and potential traces of entrained particulate uranium oxides or fluorides. This offgas stream flows through porous metal filters to remove uranium bearing particles. Subsequently, 

the relatively small quantities of HF and fluorosilic acid vapors are removed from the off-gas 

flow by cooling in a pre-condenser system. The collected HF is sent to the Plant KOH Scrubbing 

System where it is treated as described above. After removal of the HF and fluorosilic acid 

impurities using the pre-condenser system, the residual fluoride product gas stream passes 

through a set of cold trap heat exchanger vessels operating at cryogenic temperatures. The 

gaseous fluoride product solidifies in the cold trap. When loaded, the cold trap is warmed for 

unloading and packaging the product into Department of Transportation (DOT) containers. The 

final off-gas stream exiting the cold trap and containing non-condensable gases and trace 

quantities of fluoride gases then flows to the Plant KOH Scrubbing System where it also is treated 

as described above. 

2) The second flow stream exiting the rotary calciner is the resulting waste uranium oxide 

particulate solids that discharge from rotary calciner. This waste stream is conveyed via the 

enclosed cooling screw equipment to a temporary storage hopper (bin) to be later packaged and 

shipped to an off-site licensed disposal facility. 

For the BF3 process, an additional step is used. The DUF4 and B2O3 mixture is pre-heated before it is fed 

to the rotary calciner where it reacts to produce the BF3 gas. In the pre-heating step, the mixture passes 

through a pre-heater vessel that is maintained at a temperature to cause moisture in the mixed powder to 

react with small amounts of the DUF4 resulting in HF vapors and uranium oxide solid particles being 

produced. The pre-heater vessel off-gas contains some nitrogen purge gas, HF vapors and traces of 

particulate DUF4 or uranium oxides that may have become entrained in the off-gas stream. The stream 

passes through a set of filters to remove the uranium component particulates. It then flows to the Plant 

KOH Scrubbing System for final treatment as described above. The resulting pre-heated solid particle 

materials discharge directly from the pre-heater vessel to the inlet of the BF3 production rotary calciner 

where the remainder of the process materials and components flows through equipment and is processed 

as described similarly in the SiF4 process. Final treatment of the BF3 process off-gases is accomplished in 

the Plant KOH Scrubbing System by the same method as the SiF4 process. 

The equipment that handles or stores solid particulate uranium materials within the FEP Building for both 

the SiF4 and BF3 processes is connected to a two-stage dust collector system that removes uranium prior 

to venting to the atmosphere. 

The AHF, SiF4 and BF3 final products are chemically separated from licensed materials and physically 

located separate from licensed materials. (Refer to LA, Revision B Chapter 1 and the IIFP ISA Summary, 

Revision B Section 3.1 for more detailed description of the AHF storage and the AHF, SiF4 and BF3 

trailer loading systems). Ventilation intakes and exhausts of the AHF Staging Containment Building and 

the Fluoride Products Trailer Loading Building storage have fluoride detectors, a water spray deluge 

system and engineered controls which close the ventilation and activate a gas knock-down spray of water 
LA-IFP-001 Revision B CHAPTER 4 October 31, 2011 

Page 4-14

in event of fluoride-detector activation in the affected area. The two containment-type buildings are not 

totally leak tight, but are designed to inhibit and suppress releases to the environment in event of a leak or 

spill. 

The plant laboratory hoods that are used in handling of uranium-bearing materials are checked at least 

monthly and adjusted as needed to assure the adequate face velocity in accordance with manufacturer’s 

recommendations. 

Non-uranium process buildings where hazardous materials are handled, stored or packaged have separate 

ventilation systems with their own fresh-air intakes and roof-exhaust fans. Enclosed hoods are located in 

the SiF4 and BF3 small cylinder packaging area to capture the gases in event of a leak. Additionally, area 

fluoride detectors and engineered controls are located in the fluoride gas packaging areas. The controls 

provide for closing the area ventilation systems and evacuating leaks or releases of hazardous gases to an 

emergency KOH scrubbing system. The treated gas exiting the emergency scrubber then flows to the SiF4

venturi scrubber and enters the Plant KOH Scrubbing System where the gas stream undergoes further 

treatment. In the event of activation, the spent KOH scrubbing liquors resulting from scrubbing of hood 

ventilation are sent to the EPP for treatment as described above for the Plant KOH Scrubbing System. 

4.6.1.2 Management Measures for Ventilation Systems 

The Ventilation Program, radiation detectors/alarms, process vents and associated containment systems 

are checked routinely as part of the operating process controls and Preventive Maintenance Program. 

Operations and maintenance relative to the Ventilation Program including calibrations, change 

management, measurements and analysis are performed using approved written procedures. The 

procedure system is described in the IIFP LA, Chapter 11. Management measures that pertain to 

preventive and corrective maintenance are described in the IIFP LA, Revision B Chapter 11 Section 11.2 

“Maintenance.”

4.6.1.3 Design Criteria for Ventilation Systems 

Engineered controls and redundancy are integrated into the design of ventilation systems. Normal 

operation of the facility does not result in a discharge of radioactive materials that exceeds regulatory 

limits. Ventilation systems for areas that do not have the potential for contamination are not monitored 

for radioactivity because radioactive materials are not handled or processed in those areas. 

Design requirements for the Plant KOH Scrubbing System provide for a safety margin between normal 

and abnormal operation. The margin is provided so that in event of abnormally higher concentrations or 

mass flows of the off-gas, the scrubbing system can effectively handle the operational deviations until 

such time that engineered controls can either correct or shut down the abnormal operation. 

The dust collection systems for the DUF4 and FEP processes are designed with a primary dust collector 

followed by a secondary dust collector. Sampling and analysis are routinely performed between the 

primary and secondary dust collectors and in the vent stack after the secondary dust collector discharge. 

Pressure differential across each dust collector is measured and monitored with alarm notification in the 

Control Room if the differential pressure deviates outside the set administrative control limits. If 

differential pressures indicate open filters simultaneously on both of the two-stage dust collectors, the 

dust collectors and equipment served by the respective dust collectors are shut down until investigated 

and corrected, if needed. 
LA-IFP-001 Revision B CHAPTER 4 October 31, 2011 

Page 4-15

The design efficiency of dust collectors is greater than 99% for each collector. At least two (2) 

equipment units are used in series to ensure an overall system efficiency of greater than 99.5% in the 

collection and removal of particulate uranium from the vented process gas. 

Design- rated efficiency criteria for uranium particulate dust collection components and process vent offgas scrubbers are provided in Table 4-1. 

Table 4-1 Design Criteria for Vent Off-gas Treatment Equipment 

Component Design Efficiency Comments 

DUF4 dust collectors >99.5% particulates Applies to all primary, secondary and redundant 

units 

FEP uranium oxide dust collectors >99.5% particulates Applies to all primary, secondary and redundant 

units 

DUF4 vacuum cleaner cyclone >80% particulates Cyclone discharges to DUF4 vacuum cleaner 

dust collector 

FEP uranium oxide vacuum cleaner 

cyclone 

>80% particulates Cyclone discharges to oxide vacuum cleaner 

dust collector 

DUF4 vacuum cleaner dust collector >99.5% particulates Discharges to inlet of DUF4 secondary dust 

collector 

FEP uranium oxide vacuum cleaner 

dust collector 

>99.5% particulates Discharges to inlet of FEP uranium oxide 

secondary dust collector 

DUF4 primary metal filter >95% particulates Removes entrained particulates from the DUF4

to DUF6 reaction vessel off-gas 

DUF4 secondary metal filter >95% particulates Removes entrained particulates that may pass 

through the DUF4 primary filter 

SiF4 primary metal filter >95% particulates Removes entrained particulates from the SiF4

rotary calciner off-gas 

SiF4 secondary metal filter >95% particulates Removes entrained particulates that may pass 

through the SiF4 primary filter 

BF3 pre-heater primary metal filter >95% particulates Removes entrained particles from the BF3 preheater vessel off-gas 

BF3 pre-heater secondary metal filter >95% particulates Removes entrained particles that may pass 

through the BF3 pre-heater primary filter 

BF3 primary metal filter >95% particulates Removes entrained particles from the BF3 rotary 

calciner off-gas 

BF3 secondary metal filter >95% particulates Removes entrained particles that may pass 

through the BF3 primary filter 

KOH venturi scrubber >80% gaseous and 

particulates 

Receives vent gas from DUF4 and FEP process 

off-gas system. Exit gas of venturi discharges to 

packed tower scrubber 

KOH packed tower scrubber >95% gaseous Second stage system. Exit gas discharges to 

coke box system 

KOH coke box scrubber >99% gaseous Discharges to atmosphere through Plant KOH 

Scrubbing System vent stack 

DUF4 off-gas primary carbon bed trap >95% gaseous and 

particulate uranium 

Absorbs DUF6 gas and traces of DUF4. 

Discharges to secondary carbon-bed trap 

DUF4 off-gas secondary carbon bed 

trap 

>95% gaseous 

uranium 

Absorbs DUF6 trace gas that may pass through 

primary carbon-bed trap. Discharges to tertiary 

carbon-bed trap 

DUF4 off-gas tertiary carbon-bed trap >95% gaseous 

uranium 

Absorbs final traces of DUF6 that may pass 

through the secondary carbon-bed trap and 

provides added margin of safety in removing 
LA-IFP-001 Revision B CHAPTER 4 October 31, 2011 

Page 4-16

Table 4-1 Design Criteria for Vent Off-gas Treatment Equipment 

Component Design Efficiency Comments 

 gaseous uranium 

DUF4 Hydrogen burner >99% hydrogen 

burned 

Gas-fired burner to destroy excess hydrogen 

from DUF6 to DUF4 reaction vessel off-gas 

FEP hood vent system emergency KOH 

scrubber 

>95% gaseous 

fluoride 

Treated gas from emergency scrubber exits to 

SiF4 venturi scrubber in the Plant KOH 

Scrubbing System for further and final treatment 

Calcium Fluoride Dust Collector >99.5% particulates Removes air particulates in the CaF2 storage area 

and process 

DUF4 Transfer Dust Collector >99.5% particulates Allows for the transfer of particulate DUF4 from 

the DUF6-to-DUF4 process to FEP consumers 

B2O3 Unloading Dust Collector >99.5% particulates Removes particulates in the B2O3 unloading 

process 

Hydrated Lime Unloading Dust 

Collector 

>99.5% particulates Removes particulates in the Hydrated Lime 

unloading process 

Design of building ventilation systems in process areas and Control Rooms are sized with adequate flows 

and pressure differentials for comfort and to ensure potential airborne concentrations of radioactivity do 

not exceed the derived air concentration (DAC) values specified by the International Commission on 

Radiological Protection (ICRP)-68 (ICRP, 1995). The ventilation system is designed so that air flow will 

be from areas of low contamination potential towards areas of higher contamination potential to minimize 

the spread of contamination. 

4.6.1.4 Testing of Ventilation Systems 

Several measures are in place to ensure effective operation of the ventilation control systems. Differential 

pressure is monitored and alarmed for High Efficiency Particulate Air (HEPA) filters used for Control 

Rooms where uranium is processed. Operating procedures specify limits and set points on differential 

pressure consistent with manufacturer’s recommendations. Filters are changed if they fail to function 

properly or if the differential pressure exceeds the manufacturer’s ratings. 

Dust collector units in the DUF4 and FEP processes are monitored and alarmed for differential pressure. 

Operating procedures specify limits and set points for acceptable differential pressures and uranium 

sample results. Operating procedures also specify that at least two (2) dust collector units shall be 

operated in series. If this is not possible, the process system being serviced by the dust collectors must be 

placed in a shutdown or standby mode. 

Filter and dust collector inspection, testing, maintenance and change-out criteria are specified in written 

procedures approved by the Plant Engineering and Maintenance Manager and the RPM or designated 

alternates. Change-out frequency is based on considerations of filter loading, operating experience, 

differential pressure data and any monitoring data that exceeds set administrative control limits. 

Pressures are continuously monitored and controlled for the Plant KOH Scrubbing System and across the 

process system that is being vented to the scrubbing system. Limits are set to ensure an adequate safety 

margin of pressure controls for the scrubbing system. Operating procedures and operator aids also provide 

for corrective response when alarms are received relative to the system pressure controls. Testing to 

ensure established set point pressure drops across scrubber equipment is specified in written procedures 

that are approved by the Plant Engineering and Maintenance organization. 
LA-IFP-001 Revision B CHAPTER 4 October 31, 2011 

Page 4-17

Air flow rates at exhausted enclosures and close-capture points related to uranium processing and 

handling areas are adequate to preclude escape of airborne uranium and minimize potential for intake by 

workers. Air flow rates are checked routinely when in use and after modification of any hood, exhausted 

enclosure, close-capture point equipment or ventilation system serving these barriers. 

4.6.2 Respiratory Protection Program 

The Respiratory Protection Program is a subset of the RPP and is conducted in accordance with 10 CFR 

20, Subpart H (CFR, 2008n). In accordance with 10 CFR 20.1703(c)(1-2), “Use of Individual Respiratory 

Protection Equipment,” (CFR, 2008o), the Respiratory Protection Program includes air sampling to 

identify potential hazards, permit proper equipment selection and estimate occupational doses. Surveys 

and bioassays are also performed, as necessary, to evaluate potential or actual intakes. The Respiratory 

Protection Program is consistent with the guidance in Regulatory Guide 8.15,”Acceptable Programs for 

Respiratory Protection,” (NRC, 1999b). 

4.6.2.1 Respiratory Protection Requirements; 10 CFR 20, Subpart H 

In accordance with 10 CFR 20.1701 (CFR, 2008p), the IIFP Facility is designed and operated to use, to 

the maximum extent practical, process and engineering controls to minimize the concentration of 

radioactive material in air. In accordance with 10 CFR 20.1702(a), “Use of Other Controls,” (CFR, 

2008q), when it is not practical to apply process or other engineering controls, ALARA principles to 

include access control to the affected area, limitations on exposure times and use of respiratory protection 

equipment are applied. In accordance with 10 CFR 20.1703(a) (CFR, 2008o), respiratory protection 

equipment specifically tested and certified by the National Institute for Occupational Safety and Health 

(NIOSH) is used. 

4.6.2.2 Procedures for Using Respiratory Protection Equipment 

In accordance with 10 CFR 20.1703(c) (4) (CFR, 2008o), approved written procedures dictate the 

following: 

• Monitoring including air sampling and bioassays 

• Supervision and training of respirator users 

• Fit testing of respirators 

• Respirator selection 

• Breathing air quality 

• Inventory and control of respirators 

• Cleaning of respirators 

• Storage, issuance, maintenance, repair, testing and quality assurance of respiratory protection 

equipment 

• Recordkeeping 

• Limitations on respirator use and relief from respirator use 

Selection of Respiratory Protection Equipment

In accordance with 10 CFR 20.1702(b) (CFR, 2008q) when performing ALARA analysis to determine if 

respiratory equipment should be used, other safety factors are considered including the impact of 

respiratory protection equipment use on industrial safety and health. 
LA-IFP-001 Revision B CHAPTER 4 October 31, 2011 

Page 4-18

In accordance with 10 CFR 20.1703(e) (CFR, 2008o), consideration is given to the limitations appropriate 

to the type and mode of respiratory device use. Provisions are made for vision correction, adequate 

communication, low/high temperature work environments and the concurrent use of other safety or 

radiation protection equipment. Per approved written procedure(s), radiation protection personnel select 

the appropriate type of respiratory device to be used for activities involving potential exposure to airborne 

radioactivity. 

Fitting of Respiratory Protection Equipment

Approved written procedures describe the proper techniques for performing fit tests. An adequate fit is 

determined for face sealing respirators using either a quantitative fit test method or a qualitative method. 

In accordance with 10 CFR 20.1703(c) (6) (CFR, 2008o), qualitative fit testing is acceptable if it is 

capable of verifying a fit factor of 10 times the assigned protection factor (APF) for face pieces operated 

in a negative pressure mode or it is capable of verifying a fit factor of 500 for face pieces operated in a 

positive pressure mode. Mask fits are reevaluated least annually. Also, in accordance with 

10 CFR 20.1703(h) (CFR, 2008o) no objects, materials or substances such as facial hair or any conditions 

that interfere with the face piece seal or valve function and that are under the control of the respirator 

wearer are permitted between the skin of the wearer’s face and the sealing surface of a tight fitting 

respirator face piece. 

Issuance of Respiratory Protection Equipment

Approved written procedures prescribe the actions to be taken when issuing respiratory protection 

equipment. In accordance with 10 CFR 20.1703(c) (5) (CFR, 2008o), individuals designated to use 

respiratory protection equipment are evaluated by a physician to determine if the individual is medically 

fit to use respiratory protection devices. Individuals are medically evaluated periodically thereafter in 

accordance with 29 CFR 1910.134(e) (CFR, 2008r). 

Maintenance of Respiratory Protection Equipment

Respiratory protection equipment is cleaned, serviced, tested and inspected in accordance with the 

instructions specified by the manufacturer per NIOSH for each respiratory protection device. The IIFP 

Facility is equipped with a suitable location for cleaning and storage of respirators and other reusable 

PPE. Contaminated items must remain inside the RCAs where the items are cleaned until they are 

successfully decontaminated. Respiratory protection equipment is then taken to the respirator cleaning 

and refurbishing area for hygienic cleaning and servicing as described above prior to its return to service. 

Cleaned PPE such as face shields and respirators that come into contact with the wearer’s face must be 

inspected after cleaning before reuse. Approved written procedures prescribe the actions to be taken for 

maintenance of respiratory protection equipment. The liquid waste resulting from cleaning respirators and 

other reusable PPE is sent to the plant Decontamination Building liquid treatment process for removal of 

uranium that may be in the cleaning waste liquid. 

Testing of Respiratory Protection Equipment

In accordance with 10 CFR 20.1703(c) (3) (CFR, 2008o), respirators are tested for operability (user seal 

check for face sealing devices and functional check for others) immediately prior to each use per the 

instructions in approved written procedures. 
LA-IFP-001 Revision B CHAPTER 4 October 31, 2011 

Page 4-19

Training on the Use of Respiratory Protection Equipment

If there are no medical restrictions precluding respirator use, the individual is provided respiratory 

training and fitting by a qualified instructor. Additional training on the use and limitations of selfcontained breathing devices is provided to designated individuals per approved written procedures. 

In accordance with 10 CFR 20.1703(d) (CFR, 2008o), each respirator user is advised that he/she may 

leave the area at any time for relief from respirator use in the event of equipment malfunction, physical or 

psychological distress, procedural or communication failure, significant deterioration of operating 

conditions or any other condition that may require such relief. 

Monitoring Areas Requiring Respiratory Protection

In accordance with approved written procedures, an area requiring respiratory protection is monitored by 

the radiation protection staff for airborne radioactivity in order to estimate the dose to the individual 

wearing respiratory protection. This monitoring could include air sampling, bioassay and/or other 

method(s) deemed appropriate by radiation protection personnel. 

Recordkeeping for the Use of Respiratory Protection Equipment

Records regarding the use of respiratory protection equipment are maintained in accordance with 

approved written procedures and comply with 10 CFR 20, Subpart L “Records.” (CFR, 2008s). The 

Records Management Program is described in the IIFP LA, Revision B Chapter 11. 

Revision of Respiratory Protection Procedures

In accordance with the LA, Revision B Chapter 11, respiratory protection procedures are revised as 

needed. 

Respiratory Protection Program Records

Records of the RPP (including training for respiratory use and maintenance) are maintained in accordance 

with the Records Management Program as described in LA, Revision B Chapter 11. 

4.7 RADIATION SURVEYS AND MONITORING PROGRAMS 

Routine radiological surveys and monitoring are conducted at a regular frequency to ensure occupational 

exposures are ALARA. This includes airborne and surface contamination surveys and personnel 

dosimetry. The survey and monitoring programs are consistent with the guidance in Regulatory Guide 8.2 

(NRC, 1973), Regulatory Guide 8.7, “Instructions for Recording and Reporting Occupational Radiation 

Exposure Data,” (NRC, 2005) and Regulatory Guide 8.9, “Acceptable Concepts, Models, Equations and 

Assumptions for a Bioassay Program,” (NRC, 1993c). 

4.7.1 Radiation Surveys and Monitoring Programs Meeting Requirements of 10 CFR 20, 

Subpart F 

In accordance with 10 CFR 20.1501(a) and (b) (CFR, 2008f), IIFP conducts radiation surveys and 

radiation area monitoring with instrumentation or area dosimetry that: 1) satisfy applicable regulations, 2) 

are adequate to evaluate the magnitude and extent of radiation levels, concentrations or quantities of 
LA-IFP-001 Revision B CHAPTER 4 October 31, 2011 

Page 4-20

radioactive material and 3) can identify potential radiological hazards or the accumulation of 

radioactivity. Section 4.7.6, “Air Sampling Program,” discusses air sampling and Section 4.7.8, 

“Minimization of Contamination,” discusses the Contamination Survey Program. 

In accordance with 10 CFR 20.1501(b) (CFR, 2008f), instruments and equipment are calibrated 

periodically. Section 4.7.12, “Equipment and Instrumentation Sensitivity,” discusses equipment 

calibrations. 

In accordance with 10 CFR 20.1501(c) (CFR, 2008f), personnel dosimeters are processed by a National 

Voluntary Laboratory Accreditation Program (NVLAP) accredited vendor. Section 4.7.3, “External 

Occupational Radiation Exposures,” discusses external dose and personnel dosimetry. 

In accordance with 10 CFR 20.1502 (CFR, 2008g), IIFP monitors exposure to radiation and radioactive 

material to demonstrate compliance with occupational dose limits. Sections 4.7.3 and 4.7.4 discuss 

monitoring for external and internal dose, respectively. 

4.7.2 Approved Procedures for Radiation Surveys and Monitoring Programs 

The approved written procedures include survey and monitoring objectives, sampling procedures and data 

analysis methods, types of equipment and instrumentation to be used, frequency of measurements, 

recordkeeping and reporting requirements and actions to be taken in case measurements exceed 

administrative or regulatory limits. 

4.7.3 External Occupational Radiation Exposures 

External occupational dose is measured in accordance with 10 CFR 20.1501(a) (CFR, 2008f). Deep-dose 

equivalent and shallow-dose equivalent from external sources of radiation are determined by individually 

assigned dosimeters. Per approved written procedures, personnel dosimeters are distributed to individuals 

based on their job functions commensurate with the amount of time an individual spends working with or 

near radioactive materials. Personnel dosimeters are processed by a National Voluntary Laboratory 

Accreditation Program (NVLAP) accredited vendor. The capability exists to process dosimeters 

expeditiously if there is an indication of an exposure in excess of established action guides. Action guides 

for external exposures are established in approved written procedures. Work activity restrictions are 

imposed when an individual’s exposure exceeds 80 percent of the applicable 10 CFR 20.1201 (CFR, 

2008h) limit. 

Any time an administrative limit is exceeded, the RPM is notified. He/she then determines the need for 

investigation and/or corrective action. When the results of individual monitoring are unavailable or are 

invalidated by unusual exposure conditions, external exposures may be calculated by the radiation 

protection staff on the basis of data obtained by investigation. 

4.7.4 Internal Occupational Radiation Exposures 

The Personnel Monitoring Program is designed and implemented for internal occupational radiation 

exposures based on the requirements of 10 CFR 20.1201 (CFR, 2008h), 10 CFR 20.1204, “Determination 

of Internal Exposure,” (CFR, 2008t) 10 CFR 20.1502(b), (CFR, 2008g) and 10 CFR 20.1704(i), “Further 

Restrictions on the Use of Respiratory Protection Equipment,” (CFR, 2008u). Intakes are assigned to 

individuals based upon one or more types of measurements as follows: air sampling, in vitro bioassay (i.e. 

urinalysis or fecal) and/or in vivo bioassay (i.e. lung counting). The type and frequency of measurements 

for an individual are determined by their job function and properties of the licensed material associated 
LA-IFP-001 Revision B CHAPTER 4 October 31, 2011 

Page 4-21

with a known or suspected intake. The measurements are commensurate with the amount of time an 

individual spends working with or near radioactive material. Intakes are converted to committed dose 

equivalent (CDE) and committed effective dose equivalent (CEDE) for the purposes of limiting and 

recording occupational doses. Action levels are established in approved written procedures to prevent an 

individual from exceeding the occupational exposure limits specified in 10 CFR 20.1201 (CFR, 2008h). 

Work activity restrictions are imposed when an individual’s exposure exceeds 80 percent of the 

10 CFR 20.1201 (CFR, 2008h) limit. Control actions include temporarily restricting the individual from 

working in an area containing airborne radioactivity and actions are taken as necessary to prevent 

recurrence. 

4.7.4.1 Urinalysis Program 

The In Vitro (urinalysis and/or fecal) Bioassay Program is conducted primarily to evaluate the intake of 

soluble uranium to assure the 10 CFR 20.1201(e) (CFR, 2008h) intake limit of 10 milligram (mg) per 

week is not exceeded. Personnel assigned to work in areas where soluble airborne uranium compounds 

are present in concentrations likely to result in intakes in excess of 10 percent of the applicable limits in 

10 CFR 20.1201 (CFR, 2008h) are monitored by urinalysis and/or fecal bioassay methods. The minimum 

sampling frequency for these individuals is specified in approved written procedures. In vitro monitoring 

may also be used to monitor individuals involved in non-routine operations, perturbations or incidents. 

In vitro sampling frequencies and action levels are established in approved written procedures based on 

the appropriate bio-kinetic models for the uranium compounds present. Results above the applicable 

action level are investigated. Work activity restrictions are imposed when an individual’s exposure (Total 

Effective Dose Equivalent) exceeds 80 percent of the occupational dose limit in 10 CFR 20.1201(a) 

(CFR, 2008h). Exceeding an action level will result in a temporary work restriction for the individual to 

prevent additional exposure and allow a more accurate assessment of the intake. 

An off-site laboratory that meets the performance standards specified in ANSI/HPS N13.22 and 

ANSI/HPS N13.30 will be utilized to process and analyze in vitro bioassay samples. 

4.7.4.2 In Vivo Lung Counting Program 

In vivo lung counting will be conducted as necessary to supplement or verify in vitro bioassay results. 

Actions are taken based on in vivo lung counting results to ensure the Annual Limit on Intake (ALI) is not 

exceeded. If the individual’s lung count indicates an intake and burden greater than the established action 

level, the individual is restricted from working in areas containing potential airborne uranium until such 

time that investigation and re-counting finds the intake to be below the established limits. Work activity 

restrictions are imposed if an individual exposure were to exceed 80 percent of the occupational dose 

limit in 10 CFR 20.1201(d) (CFR, 2008h). 

In vivo lung counting will be performed by qualified contractors in accordance with ANSI/HPS N13.35 

performance standards. 

4.7.5 Summation of External and Internal Occupational Radiation Exposures 

Per approved written procedures, the summation of external and internal occupational radiation exposure 

is reported as a TEDE and is calculated in accordance with 10 CFR 20.1202(a)-(d), “Compliance with 

Requirements for Summation of External and Internal Doses,” (CFR, 2008v). The calculation is 
LA-IFP-001 Revision B CHAPTER 4 October 31, 2011 

Page 4-22

consistent with the guidance in Regulatory Guide 8.34, “Monitoring Criteria and Methods to Calculate 

Occupational Radiation Doses,” (NRC, 1992a). 

4.7.6 Air Sampling Program 

An Air Sampling Program is designed and implemented in areas of the IIFP Facility that are identified as 

Airborne Radioactivity Areas. This Program includes procedures to conduct air surveys and to calibrate 

and maintain radiation protection airborne sampling equipment in accordance with the manufacturers’ 

recommendations. 

4.7.7 Control of Airborne Radioactive Material 

Air samples are continuously taken from each main process area where airborne concentrations 

potentially could exceed 0.3 derived air concentrations (DAC) when averaged over 40 hours to assess the 

concentrations of uranium in the air. Per approved written procedure(s), the air samples are collected in 

such a way that the concentrations of uranium measured are representative of the air which workers 

breathe. Air sampling results and individual personnel exposure assignments are monitored by the 

radiation protection function to evaluate the effectiveness of personnel exposure controls. 

Evaluations of air sampling effectiveness are performed in accordance with the methods and acceptance 

criteria in Regulatory Guide 8.25, “Air Sampling in the Workplace,” (NRC, 1992b). Filters from air 

samplers are changed each shift during normal operating periods or at more frequent intervals following 

the detection of an event that may have released airborne uranium based upon knowledge of the particular 

circumstances. Filters are not changed as frequently during periods when no work is in progress. The 

filters are processed to determine the uranium concentration in the air for each area. 

Grab samples are obtained during maintenance activities that are known to or have the potential to 

generate airborne radioactivity levels in excess of 1.0 DAC. 

Each air sampler is equipped with a flow meter to indicate flow rate of air sampled. These flow meters are 

calibrated or replaced every 18 months, at a minimum. Air sampling, resulting in excess of 2.5 DAC 

(eight hour sample) and not resulting from specific known causes, are investigated to determine the 

probable cause. Operations or equipment will be shut down and immediate corrective action will be taken 

at locations where an air sample exceeds 10 DAC without a specific known cause. 

In addition to the activities described above, exposure to airborne radioactive material is controlled 

through limiting access to areas, limiting exposure time and use of respiratory equipment. 

4.7.8 Minimization of Contamination 

The IIFP Facility is designed and operated in accordance with 10 CFR 20.1406 “Minimization of 

Contamination,” (CFR, 2008w) to minimize contamination, facilitate eventual decommissioning and 

minimize, to the extent practicable, the generation of radioactive waste. In addition, minimization of 

contamination is accomplished through compliance with labeling and packaging requirements in 

10 CFR 20.1904, “Labeling Containers,” (CFR, 2008x), 10 CFR 20.1905, “Exemptions to Labeling 

Requirements,” (CFR, 2008y), 10 CFR 20.1906, “Procedures for Receiving and Opening Packages,” 

(CFR, 2008z), 10 CFR 20, Subpart K “Waste Disposal,” (CFR, 2008aa). The following are examples of 

methods for minimizing contamination: 

• Containment of radioactive material throughout the facility 
LA-IFP-001 Revision B CHAPTER 4 October 31, 2011 

Page 4-23

• Monitoring for equipment leaks 

• Training on proper techniques for handling radioactive material 

• Airflow from areas of low radioactivity to higher radioactivity 

4.7.9 Contamination Survey Program 

Routine surveys are performed in areas that are most likely to be contaminated or where contamination 

from licensed processes, licensed material decay products or other radionuclide contaminates may 

concentrate. The radiation protection staff determines survey frequencies, compares the survey results to 

action guide values as specified in approved written procedures and ensures the appropriate responses are 

taken. If the results exceed the action guide values, the Radiation Protection Manager, or Designee, is 

informed and he/she determines if an investigation and/or corrective actions are necessary. 

Protective clothing is provided to persons who are required to enter the RCAs where the potential for 

personnel contamination exists as determined by the radiation protection staff. The amount and type of 

protective clothing required for a specific area or operation is determined by operational experience and 

the potential for contamination. Available clothing includes caps, hoods, laboratory coats, coveralls, 

safety glasses, boots, overshoes, shoe covers, rubber and cloth gloves and safety shoes. The protective 

clothing is removed in the change rooms upon exit. In the Laboratory area, where uranium is handled, the 

minimum protective clothing requirement for entry is a laboratory coat and safety glasses. PPE and anticontamination clothing is segregated and disposed of in accordance with the following: 

Labeled radioactive material bags are provided for placement of disposable PPE. Used disposable PPE, 

respirator cartridges and other disposable items are containerized and taken to the Radiological Waste 

Area. 

Radiation protection technicians perform routine contamination surveys in the change rooms, plant exit 

walkways and the Laboratory area. 

4.7.10 Corrective Action Program for Personnel Contamination 

Personnel contamination surveys are required for external contamination on clothing and the body by 

personnel exiting the change rooms. If contamination is found in excess of background levels, the 

individual attempts self-decontamination (except for facial contamination) at the facilities provided in the 

change rooms. If decontamination attempts are not successful, or if facial contamination is detected, 

decontamination assistance is provided by the radiation protection function (typically a radiation 

protection technician). If skin or personal clothing is still contaminated above background levels, the 

individual is not permitted to leave the area without the prior approval (per approved written procedure) 

of the RPM. 

Personnel contamination events that exceed a facility Administrative Control Level will be recorded, 

tracked and managed through the Corrective Action Program described in the IIFP License Application, 

Revision B Chapter 11 Section 6 “Incident Investigations and Corrective Action Program.” The corrective 

action process will require investigation of the contamination event and implementation of corrective 

actions to rectify any deficiencies. Contamination events that are managed through the Corrective Action 

Program will be reported to the ALARA Committee and reviewed as described in Section 4.2.3, 

“ALARA Committee.” Tracking and trending will be performed in accordance with the ALARA Program 

as stated in Section 4.2.2 “ALARA Goals.” 
LA-IFP-001 Revision B CHAPTER 4 October 31, 2011 

Page 4-24

4.7.11 Corrective Action Program for Airborne Occupational Exposure 

Corrective actions are implemented and documented based on the frequency and magnitude of events 

causing releases of airborne uranium that exceed administrative limits. Routine air sampling is 

supplemented by portable air sample surveys as required to evaluate non routine activities or breaches in 

containment. Radiation protection and operations staff will investigate the cause of the release and 

implements recommended actions to prevent future releases. 

4.7.12 Equipment and Instrumentation Sensitivity 

Appropriate radiation detection instruments are available in sufficient number to ensure adequate 

radiation surveillance can be accomplished. Selection criteria for portable and laboratory counting 

equipment are based on the types of radiation detected, maintenance requirements, ruggedness, 

interchangeability and upper and lower limits of detection capabilities. 

Portable instrumentation is calibrated in accordance with manufacturing recommendations before initial 

use, after major maintenance and on a routine basis following the last calibration. Calibration consists of a 

performance check on each range scale of the instrument with a radioactive source of known activity 

traceable to a recognized standard such as the National Institute of Standards and Technology (NIST). 

Prior to each use, operability checks are performed on monitoring and laboratory counting instruments. 

The background and efficiency of laboratory counting instruments are determined on a daily basis when 

in use. 

4.7.13 Policies for Removal of Equipment and Materials from Radiological Controlled Areas 

When removing equipment and materials from RCAs, with the exception of hazardous chemicals 

produced from licensed operations, the guidance contained in NRC Branch Technical Position, 

“Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or 

Termination of Licenses for By-product, Source or Special Nuclear Material,” April 1993 (NRC, 1993b), 

will be followed. Volumetrically contaminated materials will be released if the uranium concentration of 

the material does not exceed 30 pCi/g, or the dose to a member of the public, taking into consideration the 

subsequent use of the material, does not exceed 1 mrem per year. The radiation protection staff must 

approve the release of equipment and/or materials from RCAs. The equipment and material screening and 

evaluation process will be governed by approved written procedures. 

Hazardous chemicals produced from licensed materials, as defined in 10 CFR 70.4, will be considered 

“separated from licensed materials” by meeting the exemptions described in 10 CFR 40.13(a) for 

“unimportant quantities of source material.” The term “Unimportant quantities of source material” is 

defined as “... source material in any chemical mixture, compound, solution, or alloy in which the source 

material is by weight less than one-twentieth of 1 percent (0.05 percent) of the mixture, compound, 

solution or alloy.” 

Environmental, safety and health controls and regulations associated with the storage, handling, 

transportation and disposal of these hazardous chemicals result in more restrictive controls than those 

necessary to protect the worker, public and environment from the radiological hazard associated with 

source material at a concentration of one-twentieth of 1 percent (0.05 percent or 500 ppm) in the 

hazardous chemical. For example, uranium at a concentration of 500 ppm in anhydrous hydrogen fluoride 

(AHF) would result in a dose of 0.09 mrem to an individual exposed to AHF at the ACGIH TLV-STEL 

of 2 ppm for 15 minutes. In the more extreme case, the lowest lethal concentration of HF, considered to 

range between 50 and 250 ppm for 5 minutes, would result in a dose between 0.75 and 3.8 mrem, 
LA-IFP-001 Revision B CHAPTER 4 October 31, 2011 

Page 4-25

respectively. Generally at IIFP, the hazardous chemicals produced from licensed materials and then 

separated from licensed materials are products that are sold. The customers of these products will 

typically require rigorous routine sampling and analysis of the products to meet any required 

specifications. IIFP will establish a statistically confident sampling and analysis written procedure 

including approved analytical methods to demonstrate that customer product purity and impurity limit 

requirements are met. 

IIFP will also include a statistically confident sampling and analysis written procedure for source material 

(uranium) determination in the materials being considered as “separated from licensed materials” as an 

assurance that exemptions described in 10 CFR 40.13(a) remain applicable for the subject materials. The 

measurement methods applied to determine the concentration of source material in hazardous chemicals 

will be governed by approved written procedures. The written procedure for uranium determination in the 

“separated from licensed materials” will include the sampling plan, acceptable quality levels, the 

approved analytical methods and steps, calibration standard requirements and procedures for calibration 

where applicable. The sampling plan will be based on valid technical and statistical principles including 

estimates of variance and established confidence limits associated with the sampling method. The 

qualified measurement methods, including the analytical accuracy, variance and confidence limits will be 

demonstrated to an acceptable performance before being approved as an implementing procedure. 

4.7.14 Sealed Sources 

When not in use, sources shall be stored in a closed container adequately designed and constructed to 

contain radioactive material that may otherwise be released during storage. The sources shall be tested for 

leakage using the Dry Wipe test method described in ISO 9978:1992, “Radiation Protection-Sealed 

Radioactive Sources-Leakage Test Methods,” (ISO, 1992). 

Sealed sources will be leak checked at six (6) month intervals not to exceed that specified on the sealed 

source and device registration certificate using a quantitative analysis requiring that instrumentation used 

to analyze the sample be capable of detecting 185 Becquerel (Bq) (0.005 microcuries) of radioactivity. 

Leak tests will not be required if: 

• Sources contain only H-3. 

• Sources contain only licensed material with a half-life of less than 30 days. 

• Sources contain only a radioactive gas. 

• Sources contain 3.7 MBq (100 microcuries) or less of beta-emitting or gamma-emitting material 

or 370 kBq (10 microcuries) or less of alpha-emitting material. 

• Sources are stored and are not being used (must be leak tested before use or transfer). 

Sources that exhibit removable contamination in excess of 185 Bq (0.005 microcuries) will be removed 

from service and disposed of in accordance with regulations. 

4.7.15 Access Control 

Access control is accomplished through compliance with the requirements in 10 CFR 20.1601(a)-(c), 

“Control of Access to High Radiation Areas,” (CFR, 2008bb) and 10 CFR 20.1602, “Control of Access to 

Very High Radiation Areas,” (CFR, 2008cc). For most RCAs, routine access points are established 

through change rooms. Each change room includes a step off area provided between the contamination 

Controlled and Non-Controlled Areas. Instructions controlling entry and exit from RCAs are posted at the 

entry points. Survey meters are provided in the step off area of each change room for use by personnel 
LA-IFP-001 Revision B CHAPTER 4 October 31, 2011 

Page 4-26

leaving the RCA. Posted instructions address the use of the survey meters, donning and doffing protective 

clothing and appropriate decontamination methods. Alternate access points to RCAs are established for 

specific activities not accommodated by the change rooms. Such access is governed by approved written 

procedures or RWPs which establish controls to prevent the spread of contamination to Non-Controlled 

Areas. 

RCA that may pose a risk to employees are identified and posted in compliance with the requirements in 

10 CFR 20.1901, “Caution Signs,” (CFR, 2008dd), 10 CFR 20.1902, “Posting Requirements,” (CFR, 

2008ee), and 10 CFR 20.1903, “Exceptions to Posting Requirements,” (CFR, 2008ff). Access to these 

areas is controlled so that only appropriately trained individuals are allowed entry. Signs are regularly 

inspected for conformance. The following areas are identified and posted if applicable in accordance with 

definitions provided in 10 CFR 20.1003 (CFR, 2008gg). Definitions of Access Control Areas are given 

in the IIFP LA, Revision B Chapter 1 Section 1.1.2 “Facility Description.” 

• Radiation Area 

• High Radiation Area (unlikely to have but a sealed calibration source may require) 

• Airborne Radioactivity Area 

• Radioactive Material Area 

In addition, contamination areas are posted in accordance with approved written procedures. Signs are 

posted at the entry points of areas requiring protective clothing. Radiation safety training and approved 

written procedures instruct employees on requirements for entering and working in posted areas. 

4.7.16 Radiation Reporting Program 

A Radiation Reporting Program will be established to maintain records of the RPP, radiation survey 

results, corrective action program referrals, RWPs and planned special exposures. The Radiation 

Reporting Program is consistent with the guidance in Regulatory Guide 8.7 (NRC, 2005). 

The Radiation Reporting Program commits to report to the NRC any event resulting in an occupational 

exposure to radiation exceeding the dose limits in 10 CFR 20.1201 (CFR, 2008h), within the time 

specified in 10 CFR 20.2202, “Notification of Incidents,” (CFR, 2008hh), 10 CFR 30.50, “Reporting 

Requirements,” (CFR, 2008ii), 10 CFR 40.60, “Reporting Requirements,” (CFR, 2008jj), and 

10 CFR 70.74, “Additional Reporting Requirements,” (CFR, 2008kk). The Radiation Reporting Program 

also commits to prepare and submit to the NRC an annual report of individual monitoring results, as 

required by 10 CFR 20.2206(b), “Reports of Individual Monitoring,” (CFR, 2008ll). 

Radiation exposure data for an individual and the results of any measurements, analyses and calculations 

of radioactive material deposited or retained in the body of an individual shall be reported to the 

individual as specified in 10 CFR 19.13 (CFR, 2008m). Individuals are advised of their right to request 

radiation exposure data in Basic Radiation Safety Training. In accordance with 10 CFR 19.11, “Posting of 

Notices to Workers,” (CFR, 2008mm), IIFP management posts current copies or locations where they 

may be reviewed of the following documents: 

• The regulations in 10 CFR 19 (CFR, 2008a) and 10 CFR 20 (CFR, 2008b) 

• The license, license conditions or documents incorporated into the license by reference and 

amendments thereto 

• The operating procedures applicable to licensing activities 
LA-IFP-001 Revision B CHAPTER 4 October 31, 2011 

Page 4-27

4.8 ADDITIONAL PROGRAM COMMITMENTS 

The following sections provide commitments to achieve compliance with the regulations in 10 CFR 20, 

Subpart L (CFR, 2008s), 10 CFR 20, Subpart M “Reports,” (CFR, 2008nn) and 10 CFR 70.74 (CFR, 

2008kk). 

4.8.1 Records 

In accordance with 10 CFR 20, Subpart L (CFR, 2008s), IIFP maintains records of the RPP (including 

program provisions, audits and reviews of the Program context and implementation), radiation survey 

results (air sampling, bioassays, external exposure data from monitoring individuals, internal intakes of 

radioactive material) and results of Corrective Action Program referrals, RWPs and planned special 

exposures. Recordkeeping is further described in LA, Revision B Chapter 11. 

4.8.2 Event Reporting 

Approved written procedures dictate that IIFP will report to the NRC, within the time specified by 

10 CFR 20, Subpart M (CFR, 2008nn) and 10 CFR 70.74 (CFR, 2008kk), any event resulting in an 

occupational exposure to radiation exceeding the dose limits in 10 CFR 20 (CFR, 2008b). Approved 

written procedures contain instructions for when and how to report events to the NRC and other 

regulatory agencies. 

4.8.3 Annual Dose Monitoring Report 

IIFP prepares and submits an annual report of the results of individual monitoring as required by 

10 CFR 20.2206(b) (CFR, 2008ll) to the NRC. 

4.8.4 Corrective Action Reporting 

Any radiation incident resulting in an occupational exposure that exceeds the dose limits in 

10 CFR 20.1201 (CFR, 2008h), or is required to be reported per 10 CFR 20, Subpart M (CFR, 2008nn), 

10 CFR 30.50 (CFR, 2008ii), 10 CFR 40.60 (CFR, 2008jj) and 10 CFR 70.74 (CFR, 2008kk) will be 

evaluated within the IIFP Corrective Action Program. The corrective actions taken (or planned) to protect 

against a recurrence and the proposed schedule to achieve compliance are reported to the NRC. 

 
LA-IFP-001 Revision B CHAPTER 4 October 31, 2011 

Page 4-28

REFERENCES 

ASTM, 1989 ASTM C986-89. "Developing Training Programs in the Nuclear Fuel Cycle," 

 American Society for Testing and Materials, 1989. 

ASTM, 1995 ASTM E1168-95. "Radiological Protection Training for Nuclear Facility Workers," 

American Society for Testing and Materials, 1995. 

CFR, 2007 10 CFR 20 Appendix B. "Annual Limits on Intake (ALIs) and Derived Air 

Concentrations (DACs) of Radionuclides for Occupational Exposure; Effluent 

Concentrations; Concentrations for Release to Sewerage," U.S. Nuclear Regulatory 

Commission, 2007. 

CFR, 2008a 10 CFR 19. "Notices, Instructions and Reports to Workers:Inspection and 

Investigations," U.S. Nuclear Regulatory Commission, 2008. 

CFR, 2008b 10 CFR 20. "Standards for Protection Against Radiaton," U.S. Nuclear Regulatory 

Commission, 2008. 

CFR, 2008c 10 CFR 40. "Domestic Licensing of Source Material," U.S. Nuclear Regulatory 

Commission, 2008. 

CFR, 2008d 10 CFR 20 Subpart B. "Radiation Protection Programs," U.S. Nuclear Regulatory 

Commission, 2008. 

CFR, 2008e 10 CFR 20.1101. "Radiation Protection Programs, " U.S. Nuclear Regulatory 

Commission, 2008. 

CFR, 2008f 10 CFR 20.1501." General, " U.S. Nuclear Regulatory Commission, 2008. 

CFR, 2008g 10 CFR 20.1502. "Conditions Requiring Individual Monitoring of External and 

Internal Occupational Dose, " U.S. Nuclear Regulatory Commission, 2008. 

CFR, 2008h 10 CFR 20.1201. "Occupational Dose Limits for Adults," U.S. Nuclear Regulatory 

Commission, 2008. 

CFR, 2008i 10 CFR 19.12. "Instructions to Workers," U.S. Nuclear Regulatory Commission, 

2008. 

CFR, 2008j 10 CFR 20.1208. "Dose Equivalent to an Embryo/Fetus," U.S. Nuclear Regulatory 

Commission, 2008. 

CFR, 2008k 10 CFR 20.1301. "Radiation Dose Limits for Individual Members of the Public," 

U.S. Nuclear Regulatory Commission, 2008. 

CFR, 2008l 10 CFR 20.2110. "Form of Records," U.S. Nuclear Regulatory Commission, 2008. 

CFR, 2008m 10 CFR 19.13. "Notifications and Reports to Individuals," U.S. Nuclear Regulatory 

Commission, 2008. 
LA-IFP-001 Revision B CHAPTER 4 October 31, 2011 

Page 4-29

CFR, 2008n 10 CFR 20 Subpart H. "Respiratory Protection and Controls to Restrict Internal 

Exposure in Restricted Areas," U.S. Nuclear Regulatory Commission, 2008. 

CFR, 2008o 10 CFR 20.1703." Use of Individual Respiratory Protection Equipment," U.S. 

Nuclear Regulatory Commission, 2008. 

CFR, 2008p 10 CFR 20.1701. "Use of Process or Other Engineering Controls," U.S. Nuclear 

Regulatory Commission, 2008. 

CFR, 2008q 10 CFR 20.1702. "Use of Other Controls," U.S. Nuclear Regulatory Commission, 

2008. 

CFR, 2008r 29 CFR 1910. "Occupational Safety and Health Standards," Occupational Safety and 

Health Administration, 2008. 

CFR, 2008s 10 CFR 20 Subpart L. "Records," U.S. Nuclear Regulatory Commission, 2008. 

CFR, 2008t 10 CFR 20.1204. "Determination of Internal Exposure," U.S. Nuclear Regulatory 

Commission, 2008. 

CFR, 2008u 10 CFR 20.1704. "Further Restrictions on the Use of Respiratory Protection 

Equipment," U.S. Nuclear Regulatory Commission, 2008. 

CFR, 2008v 10 CFR 20.1202. "Compliance with Requirements for Summation of External and 

Internal Doses," U.S. Nuclear Regulatory Commission, 2008. 

CFR, 2008w 10 CFR 20.1406. "Minimization of Contamination." U.S. Nuclear Regulatory 

Commission, 2008. 

CFR, 2008x 10 CFR 20.1904. "Labeling Containers," U.S. Nuclear Regulatory Commission, 

2008. 

CFR, 2008y 10 CFR 20.1905. "Exemptions to Labeling Requirements," U.S. Nuclear Regulatory 

Commission, 2008. 

CFR, 2008z 10 CFR 20.1906. "Procedures for Receiving and Opening Packages," U.S. Nuclear 

Regulatory Commission, 2008. 

CFR, 2008aa 10 CFR 20 Subpart K. "Waste Disposal," U.S. Nuclear Regulatory Commission 

2008. 

CFR, 2008bb 10 CFR 20.1601. "Control of Access to High Radiation Areas," U.S. Nuclear 

Regulatory Commission, 2008. 

CFR, 2008cc 10 CFR 20.1602. "Control of Access to Very High Radiation Areas," U.S. Nuclear 

Regulatory Commission, 2008. 

CFR, 2008dd 10 CFR 20.1901. "Caution Signs," U.S. Nuclear Regulatory Commission, 2008. 
LA-IFP-001 Revision B CHAPTER 4 October 31, 2011 

Page 4-30

CFR, 2008ee 10 CFR 20.1902. "Posting Requirements," U.S. Nuclear Regulatory Commission, 

2008. 

CFR, 2008ff 10 CFR 20.1903. "Exceptions to Posting Requirements," U.S. Nuclear Regulatory 

Commission, 2008. 

CFR, 2008gg 10 CFR 20.1003. "Definitions," U.S. Nuclear Regulatory Commission, 2008. 

CFR, 2008hh 10 CFR 20.2202. "Notification of Incidents," U.S. Nuclear Regulatory Commission, 

2008. 

CFR, 2008ii 10 CFR 30.50. "Reporting Requirements," U.S. Nuclear Regulatory Commission, 

2008. 

CFR, 2008jj 10 CFR 40.60. "Reporting Requirements," U.S. Nuclear Regulatory Commission, 

2008. 

CFR, 2008kk 10 CFR 70.74. "Additional Reporting Requirements," U.S. Nuclear Regulatory 

Commission, 2008. 

CFR, 2008ll 10 CFR 20.2206." Reports of Individual Monitoring," U.S. Nuclear Regulatory 

Commission, 2008. 

CFR, 2008mm 10 CFR 19.11. "Posting of Notices to Workers," U.S. Nuclear Regulatory 

Commission, 2008. 

CFR, 2008nn 10 CFR 20 Subpart M. "Reports," U.S. Nuclear Regulatory Commission, 2008. 

ICRP,1995 ICRP-68. "Dose Coefficients for Intakes of Radionuclides by Workers," International 

Commission on Radiological Protection, 1995. 

ISO, 1992 ISO 2919:1999. "Radiation Protection-Sealed Radioactive Sources-Leakage Test 

Methods," International Organization for Standardization, 1992. 

NRC, 1973 Regulatory Guide 8.2."Guide for Administrative Practices in Radiation Monitoring," 

U.S. Nuclear Regulatory Commission, 1973. 

NRC, 1977 Regulatory Guide 8.10."Operating Philosophy for Maintaining Occupational 

Radiation Exposures As Low As Is Reasonably Achievable," U.S. Nuclear 

Regulatory Commission, 1977. 

NRC, 1992a Regulatory Guide 8.34. "Monitoring Criteria and Methods to Calculate Occupational 

Radiation Doses," U.S. Nuclear Regulatory Commission, 1992. 

NRC, 1992b Regulatory Guide 8.25." Air Sampling in the Workplace," U.S. Nuclear Regulatory 

Commission, 1992. 

NRC, 1993a Regulatory Guide 8.37. "ALARA Levels for Effluents from Materials Facilities," 

U.S. Nuclear Regulatory Commission, 1993. 
LA-IFP-001 Revision B CHAPTER 4 October 31, 2011 

Page 4-31

NRC, 1993b Branch Technical Position."Guidelines for Decontamination of Facilities and 

Equipment Prior to Release for Unrestricted Use or Termination of Licenses for 

Byproduct Source or Special Nuclear Material," U.S. Nuclear Regulatory 

Commission, 1993. 

NRC, 1993c Regulatory Guide 8.9. "Acceptable Concepts, Models, Equations, and Assumptions 

for a Bioassay Program," U.S. Nuclear Regulatory Commission, 1993. 

NRC, 1996 Regulatory Guide 8.29. "Instruction Concerning Risks from Occupational Radiation 

Exposure," U.S. Nuclear Regulatory Commission, 1996. 

NRC, 1999a Regulatory Guide 8.13. "Instruction Concerning Prenatal Radiation Exposure," U.S. 

Nuclear Regulatory Commission, 1999. 

NRC, 1999b Regulatory Guide 8.15. "Acceptable Programs for Respiratory Protection," U.S. 

Nuclear Regulatory Commission, 1999. 

NRC, 2005 Regulatory Guide 8.7. "Instructions for Recording and Reporting Occupational 

Radiation Exposure Data," U.S. Nuclear Regulatory Commission, 2005. 

NRC, 2008 Regulatory Guide 4.21. “Minimization of Contamination and Radioactive Waste 

Generation: Life-Cycle Planning,” U.S. Nuclear Regulatory Commission, 2008.