ML20198S294
| ML20198S294 | |
| Person / Time | |
|---|---|
| Site: | 07003073 |
| Issue date: | 04/30/1997 |
| From: | Larsen S, Lux J, Pounds R KERR-MCGEE CORP. |
| To: | |
| Shared Package | |
| ML20198S292 | List: |
| References | |
| PROC-970430, NUDOCS 9901110246 | |
| Download: ML20198S294 (41) | |
Text
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KERR-McGEE CORPORATION l
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SITE RADIATION SAFETY PLAN l
l CUSHING, OKLAHOMA REFINERY SITE l;.
l REVISION 2 i
9901110246 970430 PDR ADOCK 07003073[:'
C PDR UNCONTROLLED April 30,1997 DOCUMENT mp
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,i APPROVALS e
The individuals below have read at d approved the attached Radiation Safety Plan.
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-S. Jesd.arsen -
Project Leader l
Cushing Project J
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Project Manager -
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I Robert E. Pounds l Site Manager
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Elden C. Cheatham Health &. Safety Officer s
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% d.[{/Mu Teme-VGibson i L
Administrative Supervisor p
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! CtL w Terence M. Moore l
Radiation Safety Officer Radiation Safety Plan i
Rev. 2 t
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1 TABLE OF..CO.NTENTS l
1.
Radiation Safety Program 1-1 1.1 Introduction
. 1-1 1.2 Organizational Responsibility........................
1-1 1.3. General Radiation Safety Policies
....................1-2 1.4 Radiation Safety Program Review 1 -2 2
1 2.
External Exposure Protection..............................
2-1 2.1 Introduction 2-1 2.2 Use of Film Badges and Other Dosimeters.................
2-1 2.3 External Exposure Control Measures.
2 -2 2.4 Personnel Exposure Limits...........................
2-3 2.5 Exposure Records 2-4 3.
Internal Exposure Protection............
3-1 3.1 Introduction 3-1 3.2 Air Sampling...............................
3-1 3.3-Bioassay Sampling.
..............................3-1 3.4 Exposure Records 3-3 4.
-Respiratory Protection.
4-1 4.1 Introduction.
4-1 4.2 Policy.
4-1 4.3 Respirator Usage Requirements....
4-2 4.4 Use of Respirators 4-2
- 4.5 Testing and Maintenance 4-3 5.
Declared Pregnant Woman Exposure Control 5-1 5.1 Introduction 5-1
- 5.2 Policy.......
5-1 5.3
' Declaration of Pregnancy 5-1 5.4 Planning Pregnancy.....................
5 -2 f.5 Revoking Declaration of Pregnancy 5-2 5.6 Exposure Limits and Contrci 5 -2 6.
Visitor Exposure Control 6-1 6.1
. Access Requirements and Restrictions 6-1 Radiation Safety Plan ii Rev.2 L
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TABLE OF CONTENTS (Continued) 7.
. Radiological Area Control...............................
7-1 7.1 Definitions.............................
7-1 7.2 Posting Requirements..............................
7-1 7.3 l Area Surveys and Limits.
7-2 7.4 General Access Requirements....
7-2
.8.
Radiological Surveys..................................
8-1 8.1 Surface Contamination
.............................8-1 8.2 External Radiation.................................
8-1 8.3
- Airborne Radioactive Materials........................
8-2 8.4 Documentation 8-3 9.
- Environmental Monitoring 9-1 9.1 Purpose....
9-1 9.2 Air..........
9-1 9.3 Surface Water 9-1 9.4 Groundwater 9-1 9.5 Soil............
9-1 9.6.
Vegetation.....................................
9-1 i
9.7 Gamma Radiation Monitoring.................
9-1 9.8 Special Samples 9-2 10.
Waste Monitoring and' Disposal.
10-1 10.1 Solid Waste 10-1 10.2 Liquid Waste.
. 10-1 11.
Release of Material or Equipment for Unrestricted Use......
...... Il-1 11.1 Release of Material or Equipment
... Il-1 11.2 Documentation 11-1 12.
Radiation Safety Training........................
12-1 12.1 Introduction 12-1 12.2 Radworker Training.........
12-1 12.3 Non-Radworker Training
. 12-1 l
Glossary Radiation Safety Plan iii Rev. 2 l
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1 SECTION 1.
RADIATION SAFETY PROGRAM 1.1 Introduction Kerr-McGee Corporation has an established Radiation Safety Program at its Cushing.
Oklahoma site. The primary mission of this program is to conduct all work activities, involving licensed radioactive material. in full compliance with the Cushing site's radioactive material license (SNM-1999) and all applicable regulatory requirements (i.e.,10 CFR 19.10 CFR 20. etc.) using approved radiation work procedures, standards. policies, practices, and/or engineering controls.
The purpose of this Radiation Safety Plan is to define the rules, standards, policies, i
engineering controls. and/or general radiological work practices which will be utilized at the Cushing site to ensure the safety of both on-site personnel and members of the general public. Applicability extends to all Kerr-McGee emplo, sees contractors.
subcontractors, and visitors.
The 'As Low As Reasonably Achievable" (ALARA) exposure principle is the design basis of this Radiation Safety program. The ALARA exposure principle incorporates the Total Effective Dose Equivalent concept for exposure control and monitoring.
1.2 Organintional Responsibility The Radiation Safety Officer iRSO) is responsible to ensure that the provisions of this Radiation Safety Plan are in full compliance with the Cushing site's radioactive material i
license and all applicable regulatory requirements. The RSO shall ensure that these provisions are incorporated into individual Health Physics Operating Procedures. as necessary. The RSO is also responsible for conducting site inspections on a regular basis in order to evaluate the effectiveness of this plan and to verify its implementation.
The RSO at the Cushing site is Mr. Terence M. Moore.
The overall responsibility for radiation safety extends from top management to the individual employce. Each manager / supervisor in the management line accepts responsibility for the safety of the employees and work locations under his or her supervision. Each manager / supervisor provides leadership, proper example, and administrative control to assure a successful radiation safety program that minimizes p;rsonnel exposure to radiation and radioa:tive materials. Supervisors receive the full support of management m mamtamme safe radiological operations.
Radiation workers shall be instructed on their specific rights and responsibilities. They shall follow all procedures and instructions dealing with radiation safety.
l Radiation Safety Plan 1-1 Rev.2 i
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- t-t In addition, each radiation worker shall maintain his/her own exposure as low as reasonably achievable using approved radiation work practices, procr/.aes. and
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protective equipment.
1.3 General Radi=*ian Safety Policies Qualified Health Physics (HP) personnel shall be on duty whenever work is performed in radiologically restricted areas and/or radioactive materials areas. Any person scheduling work is responsible to ensure that the RSO or Designated Alternate is aware i
of the work schedule. Each individual is responsible to perform work in a manner that j
minimizes exposure and the spread of contamination.
Work performed in all radiologically restricted areas and/or radioactive material areas shall be covered by a valid operating procedure or a special work permit. Employees j
shall understand and observe established radiation safety procedures pertaining to the task they are performing, as applicable.
If existing procedures do not adequately address the work to be performed, or j
conditions change during the performance of the task, employees shall inform HP personnel and their supervisor.
l No entry is allowed in areas of unknown dose rates or contamination status within radiologically restricted areas and/or radioactive materials areas without the accompaniment of HP personnel.
Eating, chewing gum, or use of tobacco products is not permitted in radiologically restricted areas and/or radioactive materials areas.
Loitering in radiologically restricted areas and/or radioactive materials areas is L
prohibited.
L HP personnel shall be informed immediately if any of the following occurs in a radiologically restricted area and/or radioactive materials area:
L a,
failure of any piece of protective equipment, b.
loss of or damage to a film badge, L
c.
injury that occurred within the area, or l
d.
loss of radiation and/or contamination control in the radiological area.
1 1,4 Radiation Safety Prc,mm Review g-t
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The RSO shall ensure that a radiation protection program review (audit) is performed periodically (at least annually). This program review will be for both content and implementation. Audit results, from this program review, shall be documented and m
reviewed by the Project Manager, Site Manager, and RSO.
Radiation Safety Plan 1-2 Rev.2
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SECTION 2 EXTERNAL EXPOSURE PROTECTION 2.1 Introduction External radiation exposure results from exposure to radioactive sources external to the body that have sufficient energy to cause ionization of live tissue. The official external dose of record for workers at the Kerr-McGee Cushing facility is typically derived from interpretation of film badges.
Personnel film badge results above the statistical cutoff of 10 mrem are recorded in the official exposure record for each rauiation worker (NRC Form 5).
Under certain circumstances the RSO and/or Designated Alternate may adjust official personnel doses based on calculations. Lost or suspect dosimetry devices as well as non-routine occurrences are instances when doses may be calculated from radiation surveys, personnel stay times. co-worker exposure comparisons. and other factors as appropriate. All adjustments to official dose records shall be provided with written justification for adjustment.
In addition, area Thermoluminescent Dosimeters (TLDs) are strategically placed 1
j throughout the facility to provide verification that the yearly public exposure from
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external radiation sources at the Kerr-McGee Cushing facility is less than the limit (s) specified in 10 CFR 20.
2.2 Use of Film Badnes and Other Dosimeters Radiation workers trefer to the definition of Radworker in the glossary shall wear their 61m badges at all times while in any Undesignated Area. Radioactive.\\taterials Area (RMA), or any Radiologically Restricted Area (RA). Radiation workers are not required to wear film badges in Building A.9. Trailer A or Trailer B. unless. they are working with radioactive material. or are in a posted RMA/RA (e.g., soil sample storage room in Building A-9).
Non-Radworkers are required to wear film badges if they are working with radioactive material or are entering radiologically restricted areas and/or radioactive material areas.
Film badges are normally stored in a badge rack located in the office area of Building A-9. Film badges should be returned to the badge rack prior to the wearer leaving the l
site.
Radiation Safety Plan 2-1 Rev.2
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F Film badges shall be worn externally at a location between the waist and shoulders. The l
film badge should be positioned on the body such that the name plate is facing outward
. from the individual's chest. Badge holders and film are not to be defaced by coloring or marking with pens or pencils. The badge's film is not to be removed from its holder at any time or for any purpose except by HP personnel.
A lost film badge shall be reported immediately to a HP Technician and/or the RSO. If a film badge becomes damaged or contaminated. it shall be given to a HP Technician immediately, and a new badge issued. Individuals shall report to HP anytime a film badge is taken off the site.
Personnel film badges are exchanged and processed periodically (e.g., quarterly, monthly). Area TLDs are normally exchanged and processed on a quarterly basis.
Visitors and/or contractors entering radiological restricted areas and/or radioactive materials areas shall be issued a film badge. The individuals name and badge number shall be recorded in the Visitor Log. All visitors and/or contractors shall return their film badge to the office prior to leaving. Time of departure shall be entered in the log to indicate the amount of time a person may have been in the radiologically restricted areas and/or radioactive materials areas.
The following information shall be obtained when issuing a film badge to any employee or contractor:
e Full name.
Status thired, transferred. etc.).
Social Security Number.
Birth date.
Permanent Home Address. and Date of Hire tor of stan of work for Kerr McGees.
l 2.3 Frternal Exnosure Control Measures The radiological work practices of Time. Distance. and Shielding shall be used. as much as practicable. to keep personnel external exposures ALARA. In addition. the L
following work practices shall be followed by each supervisor and employee to further assist in controlling / minimizing the radiation exposure to personnel:
Gloves (type to be determined by HP personnel) shall be worn when handling a.
any unsealed uranium or thorium contaminated material, b.
Hand carrying of uncontainerized uranium or thorium contaminated material
. shall be kept to a minimum. and The approval of the RSO and/or Designated Alternate shall be obtained Icefore c.
any radioactive sources are brought onto the facility site.
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l Radiation Safety Plan 2-2 Rev.2
r 2.4 Personnel Exnosure Limits
.. Personnel occupational exposures (refer to the defir.ition of Occupational Dose in the glossary) for Adults (individuals 18 or more years of age) shall be controlled to within the following yearly limits:
a.
Total Effective Dose Equivalent - 5 rem.
b.
Eye Dose Equivalent - 15 resa, c.
Shallow Dose Equivalent to the Skin or any Extremity - 50 rem, and d.
Sum of Deep Dose Equivalent and Committed Dose Equivalent to any individual Organ or Tissue (Referred to as Total Organ Dose Equivalent) -
50 rem.
Personnel occupational exposures for Minors (individuals under the age of 18 years) shall be controlled to within 10% of the annual dose limits for Adult workers.
The dose to an embryo / fetus during the entire pregnancy. due to occupational exposure of a Declared Pregnant Woman (refer to the definition of Declared Pregnant Woman in the glossary) shall not exceed 500 mrem in accordance with the requirements listed in 10 CFR 20 and Section 5 of this plan.
Operations at the Kerr-McGee Cushing Facility shall be conducted such that the Total Effective Dose Equivalent to members of the public does not exceed 100 mrem in a year and the dose in any Unrestricted Area does not exceed 2 mrem in any one hour.
This limit applies to members of the public who are permitted to enter the facility's restricted area (s). Demonstration of compliance with this requirement may be by either of the two methods listed in 10 CFR 20.
At present time. it is not anticipated that planned special exposure limits (see Glossary),
as described in 10 CFR 20. will be implemented at the Kerr McGee Cushing Facility based upon present conditions at the site. If conditions change in the future, a procedure shall be developed to implement the requirements for planned special exposures listed in 10 CFR 20.
In accordance with 10 CFR 20. occupational exposure limits may be exceeded in an emergency during or immediately after an accident. Justification for exceeding occupational limits may be on the basis of the rescue of persons or prevention of the exposure of a large number of people. Whenever possible individuals shall be informed of the risk and the estimated exposure before they undertake work under such exposure conditions.
Radiation Safety Plan 2-3 Rev.2
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t 2.5 1 Ernosure Records External monitoring shall be performed as described in this plan (see Section 2.2).
Documentation of external exposure to an individual shall be conducted as required in 10 CFR 20. at a minimum.
I ifetime exposures shall be documented on a NRC Form 4. as needed. Individual monitoring period exposures shall be documented on a NRC Form 5. as needed.
Individuals shall be informed of their exposures as required by 10 CFR 19. at a muumum.
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Radiation Safety Plan 2-4 Rev.2 i
r SECTION 3 INTERNAL EXPOSURE PROTECTION 3.1 Introduction All work conducted at the Kerr-McGee Cushing site involving radioactive materials shall be controlled and monitored in accordance with this Radiation Safety Plan. This Plan emphasizes the use of appropriate engineering and process controls to minimize the amount of radioactive contaminants that become airborne.
Kerr-McGee has developed and implemented an internal exposure program in order to measure and record intakes of radionuclides. The program uses air sampling and bioassays, as needed, to quantify internal exposures.
Air sampling is performed at Kerr-McGee to evaluate potential internal radiation hazards, determine the effectiveness of engineering controls and procedures, and evaluate the need for internal monitoring. If internal monitoring is needed. air sampling shall be used to determine a worker's radionuclide intake. Lapel and area air samples are both used in the internal exposure program.
In addition to the air sampling, bioassays may be used to measure internal doses. In-vivo lung counting and in-vitro sampling will be performed as needed and/or required.
3.2 Air Samnline Lapel air sampling is performed to provide a measurement of airborne hazards that are representative of the air inhaled by the workerts). They can be used to measure the airborne concentration tin gCi/mli that the worker is breathing. or they may be used as a direct measurement of intake t Cit Table 3-1 identifies the Lapel Filter Activity To DAC-Hr Ratio when using the lapel air samplers as a direct measurement of internal intake. Refer to Table 3-2 for the expected actions to be taken based upon the short term and long term analysis of the DAC-hr value from the lapel air filter media.
3.3 Bloassav S2 moline Bioassay samples are collected to supplement the air sampling program, as necessary.
Bioassay samples shall be analyzed by a certified laboratory.
j Urine bioassay samples are not normally collected. Urine sampling and analysis for uranium isotopes will be performed for all workers in a crew, if either area sample (s) or lapel sample (s) indicates the following:
a.
>40 DAC-hrs for a single air sample result, or l
Radiation Safety Plan 3-1 Rev.2 l
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> 100 DAC-hrs accumulated exposure for any one worker.
. In addition, urine samples and analysis for uranium isotopes will be performed when l
a.-
recommended by air sample action levels described in Table 3-2, or b.
requested by RSO and/or Designate.
The frequency and/or quantity of the urine samples collected will be determined by RSO and/or Designate based upon the following considerations:
estimated magnitude of exposure, a.
b.
mode ofintake,
_ type (s) of radioactive element present, c.
- d. ~ ' urine sample results, or e.
other information.
The following actions shall be taken. as applicable for urine samples with results greater than the MDA cf the sample analysis laboratory, and greater than the relative background of uranium in urine:
The laboratory report shall be reviewed in detail for accuracy and validity, a.
b.
An exposure evaluation shall be performed (e.g., review of previous bicassay history, work activities, air sample results),
r Monthly urine samples may be instituted (if appropriate) at the direction of the c.
RSO if the above review and evaluation indicate an actual or potemial internal
- exposure, d.
The applicable individual shall be notified of their internal exposure results if the above review and evaluation indicate an actual or potential internal exposure. and The site manager shall be notified in writing of review and evaluation results, e.
Work activity restrictions may be imposed based on bioassay or air sample results.
Employees placed under restricted work duty may not enter any area where there is unsealed uranium or thorium, where airborne contamination from radioactive materials may exceed 0.25 DAC, or where smearable contamination exceeds 1000 dpm/100 cm2 alpha, or 670 dpm/100 cm beta. The RSO and/or Designated Alternate shall determine in writing when the restricted work duty can be lifted.
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- Fxal bioassay samples are not normt.lly collected. Fecal analysis will be performed in i
cases where thorium exposure is suspected and either area air sample (s) or lapel air -
sample (s) indicate chronic or acute exposures in excess of 100 DAC-hrs.
1 Radiation Safety Plan 3-2 Rev.2
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In addition. fecal samples will be collected and analyzed when:
a.'
recommended by air sample action levels described in Table 3-2. or b.
requested by RSO and/or Designate.
The frequency and/or quantity of the fecal samples collected will be determined by the RSO and/or Designate based upon the following considerations:
a.
estimated magnitude of exposure, b.
mode of intake.
c.
type (s) of radioactive element present.
d.
fecal sample results. or i
e.
other information.
j Urine and fecal samples shall be handled using the Sample Identification and Control procedure (KM-AD-101).
In-vivo lung counting shall be performed at the discretion of the RSO and/or Designate.
3.4 Frnosure Records 1
Internal monitoring shall be performed as described in this plan. Documentation of internal exposure to an individual shall be conducted as required in 10 CFR 20. at a minimum.
Lifetime exposures shall be documented on a NRC Form 4. as needed. Individual monitoring period exposures shall be documented on a NRC Form 5. as needed.
ludividuals shall be informed of their exposures as required by 10 CFR 19. at a minimum.
i Radiation Safety Plan 3-3 Rev.2
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TABLE 3-1 LAPEL FILTER ACTIVITY TO DAC-HR RATIO ISOTOPE / LUNG CLASS Lapel Flow Rate: 31pm Lapel Flow Rate: 5 Ipm Thorium-232/W 3.34 DAC-hr/dpm 2.0 DAC-hr/dpm Thorium-232/Y 1.2 DAC-hr/dpm 0.70 DAC-hr/dpm Uranium-234. 235 and 238/W 0.008 DAC-hr/dpm 0.005 DAC-hr/dpm Uranium-234. 235 and 238/Y 0.15 DAC-hr/dpm 0.09 DAC-hr/dpm Notes:
1.
If a mixture of isotopes is present. use the DAC-hr ratio for Thorium-232/Y.
2.
Written authorization from the RSO shall be given to use DAC-hr ratios other than the ones listed above (e.g., different lapel flow rate being used).
Examples:
1.
A filter from a sampler ran at 51pm indicates 2.0 dpm. The sampler was on an individual working in an area known to contain both Thorium and Uranium isotopes. In this case, the ratio for Thorium 232/Y is used.
The 2.0 dpm is multiplied by 0.7 DAC-hr/dpm and the product equals j
1.4 DAC-hr.
2.
A filter from a sampler ran at 31pm indicates 1.6 dpm. The sampler was on an individual working in an area known to only contain Uranium (Class Y) isotopes. In this case. the ratio for Uranium isotopes is used.
The 1.6 dpm is multiplied by 0.15 DAC hridpm and the product equals 0.24 DAC-hr.
J Radiation Safety Plan 3-4 Rev. 2
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TABLE 3-2 AIR SAMPLE ANALYSIS ACTION LEVELS Category Air Sample Results Ev-eed Actions Shon Term Analysis
> Minimum Contact RSO and calculate the airborne (at least 12 hr decay)
Detectable Activity concentration at work site. Perform l'
(MDA) long term analysis (at least 7 day decay).
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1 Short Term Analysis
>40 DAC-hrs Evaluate work pbce conditions, (at least 12 hr' decay) including results of area and co-worker lapel air samples and evaluate work site for causes of airborne and/or potential j
hazards. Perform long term analysis (at i
i least 7 day decay).
Short Term Analysis
> 100 DAC-hrs Restrict worker (s), collect soil and/or 1
(at least 12 hr decay) contamination samples for solubility i.
analysis, begin urine and/or fecal
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sampling as directed by the RSO, correct and remediate the cause of airborne exposure. Perform long term analysis (at least 7 day decav).
Long Term Analysis
>40 DAC hrs for any Evaluate work-place conditions and (at least 7 - 14 day one worker in a work other air samples. Perform urine Jecay).
crew analysis for potential Uranium exposure on all workers in work crew.
Long Term Analysis
> 100 DAC-hrs Evaluate work-place conditions and (at least 7 - 14 day other air samples. Perform fecal decay) analysis (if thorium exposure is suspected).
l Accumulated
> 100 DAC-hrs Evaluate work practices and potential (Chronic) Exposure source term. Perform urine and fecal (per calendar year)
(if thorium exposure is suspected) analysis.
Note:
The coutnbution for naturally occurnng radon should be subtracted prior to comparison to the above action levels.
i Note:
Ammml= red (chronic) exposures > 200 DAC-hrs (per calendar year) require monitoring and reporting of exposures per 10 CFR 20.
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Radiation Safety Plan -
3-5 Rev.2 l
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j SECTION 4 RESPIRATORY PROTECTION 4.1 Introduction The primary objective of the Kerr-McGee Cushing Site Radiological Respiratory Protection Program is to limit the inhalation of airborne radioactive materials while keeping the Total Effective Dose Equivalent As Low As Reasonably Achievable (TEDE ALARA). When the potential for airborne radioactivity exists, process or engineering controls shall be used, as much as practicable. Examples of process or engineering controls are the wetting of particulate material and ventilation of work areas.
4.2 Policy If process or engineering controls are not practicable. or if the process or engineering controls will not sufficiently control the concentrations of radioactive material in the air. the use of respirators shall be considered.
The use of respiratory protective devices is subject to the following considerations:
a.
The use of respiratory protective devices shall be consistent with maintaining TEDE ALARA.
b.
The use of respirators for routine operations, when process or engineering controls are practicable is inappropriate, and shall not be used. Respirators may be considered for use in this situation while process or engineering controls are being instituted or evaluated.
The use of respirators in non-routine operations may be appropriate in situations c.
where process or engineering controls are not practicable.
d.
In emergency situations. respirators may be used initially until accurate air surveys and evaluations can be made.
It is necessary to provide respirator wearers with relief periods from wearing e.
respirators at reasonable intervals. and to limit total daily use.
f.
Provisions shall be made for respirator users to leave respirator area and remove their respirator for relief in case of equipment malfunction. undue physical or psychological distress, procedural or communication failure. significant deterioration of operational condition (s), or any other condition that may require such relief, g.
Current environmental conditions at work site shall be consideted so as to limit industrial health risks (e.g., heat stress falling).
h.
Only NIOSH/MSHA approved respiratory protection equipment shall be used.
Radiation Safety Plan 4-1 Rev.2
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b Resnirator Usane Reauirements.
A physician shall determine that an individual user is physically able to use respiratory protection equipment prior to initial fitting of respirators, and at least every 12 months -
thereafter.
A respirator fit-test is required prior to initial use and at least annually.
Successful completion of respiratory protection training is required initially and annually thereafter.
4.4 Use of Resnirators Selection of respirators shall be made by HP personnel based upon: the current and/or expected levels of airborne radioactivity in the work area the feasibility and/or effectiveness of process or engineering controls. maintaining TEDE ALARA. the protection factor of respirator versus the level of peak concentrations of airborne radioactivity in the work area and the current environmental conditions in the work area.
Eaca individual qualified to wear a respirator (meets respirator iss ace requirements) should be issued a full face respirator. The respirator should be labeled with the name of the individual to whom it has oeen issued. Assigned respirators shall not be worn by any other individual except in case of emergency.
Respirators shall be stored in an appropriate respirator storage area located on site.
Respirators shall be kept bagged and properly stored when not in use to prevent contamination.
Respirator training is provided in annual radiation safety courses. Each individual is instructed on the use. sarety considerations. and responsibilities mvolved in wearmg respirators including the method for performing an operational check on the respirator prior to use.
Each employee shall be instructed to leave the area of work activity for relief from respirator malfunction. leakage, physical or psychological discomfort procedural or communication failure, or any other condition that might result in a reduction of respiratory protection.
Full-face respirators with high efficiency particulate filters are to be used at the Kerr-l McGee Cushing site. when the potential for airborne suspension of radioactive particulates is high. In addition. respirators such as an air-line supplied respirator or a Self Contained Breathing Apparatus (SCBA) may be utilized when higher respiratory protection factors are necessary.
Radiation Safety Plan 4-2 Rev.2 i
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SCBA respirators shall be used for entry into tanks or other areas where the oxygen h
level may be deficient or when the atmosphere may be Immediately Dangerous to Life and Health (IDLH). The Cushing Health and Safety Plan delineates the requirements for wearing SCBAs in the above situations.
i Respirators shall be worn when advised by supervisors and/or HP personnel or whenever anything that might indicate the need for respintory protection is observed, such as the detection of uncontained contamination that could easily become airborne, i
or when there is a fire near radioactive material. The requirement for use of respirators t
shall normally be indicated on the special work permit associated with the work being
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performed. A change in respiratory protection status may be made by the HP 1
technician assigned to the job.
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l-Respirator frames containing prescription lenses shall be furnished to all personnel who require prescription glasses and are assigned a respirator. Contact lenses may only be L
worn with express approval of the RSO.
Respirator wearers shall have a clean shaven (smooth). facial area, at areas on the face that come in direct contact with the respirator facial seal.
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When respirators are worn HP personnel shall normally take special air samples so l
that the level of airborne contamination before, during, and after respirator use can be i
determined (the sample for 'before' and 'after' may be waived by the RSO). All I'
personnel shall notify HP personnel of any task or situation requiring the use of l-respirators so that HP personnel can obtain representative air samples.
l At the end of er. S work shift, durir.g which a respirator has been worn for radiological
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protectien. personnel shall take their respirators to a HP technician to be surveyed and i
cleaned.
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Tating and Alaintenance L
Respirators are qualitatively fit-tested using an irritant smoke. A qualitative test is used l
for a fit-test when a personal respirator is issued. In addition, each individual who has been assigtied a full-face respirator shall be quantitatively fit tested on an annual basis.
Respirator filter cartridges provided for radioactive particulates shall be changed when they become contaminated, when it becomes difficult to breath through them or when they become visibly damaged.
t-l A qualitative fit test is required following respirator maintenance which involves components effecting the respirator seal integrity.
SCBAs are inspected monthly to ensure that the air bottles are full and that the respirators are intact and serviceable.
Radiation Safety Plan 4-3 Rev. 2 i.
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r co SECTION 5 DECLARED PREGNANT WOMAN EXPOSURE CONTROL i
5.1 Introduction' Kerr-McGee's Declared Pregnant Woman Exposure Control Program is based upon recent changes made in 10 CFR 20. Kerr-McGee encourages female radiation workers to declare their pregnancy so that prenatal exposure can be kept to a mimmum.
i 5.2 ED5cy All radiation workers shall be trained on the risk of prenatal exposure to the embryoifetus (Reference NRC Reg. Guide 8.13). Radiation workers shall be informed that Kerr-McGee encourages female radiation workers to declare their pregnancy so that prenatal exposure can be kept to a minimum.
All radiation workers should sign the Risk From Prenatal Exposure and Declared Pregnant Woman Policy Form during initial radiation worker training (Refer to Sample Form 5-1).
Declaration of pregnancy is a voluntary decision by a female radiation worker.
Declaration of pregnancy shall not affect employment.
Declaration of pregnancy shall be kept strictly confidential.
5.3 Declaration of Prennancy Declaration of pregnancy shall be made by completion of the Declaration of Pregnancy Form (Refer to Sa-Form 5-2). This form shall be completed by the female radiation worker r apven to the RSO.
The RSO shall estab!ish the current dose to the embryo / fetus upon declaration.
The dose to the embryo / fetus is taken as the sum of the:
a.
deep-dose equivalent to the Declared Pregnant Woman, and b.
dose to the embryo / fetus trom radionuclides in the embryo / fetus and l
radionuclides in the Declared Pregnant Woman.
l Radiation Safety Plan 5-1 Rev.2
u 5.4 Planned Pre 9 nancy A female radiation worker. who is attempting to become pregnant. may utilize the i
Declared Pregnant Woman declaration policy prior to becoming pregnant. This early declaration shall ensure that the exposure to the embrycifetus will be minimized (particularly in the first trimester of the pregnancy). Planned pregnancy declarations shall be conducted as described in Section 5.3.
5.5 Revokine Declaration of Preenancy A Declared Pregnant Woman can revoke her Declaration of Pregnancy at any time for any reason. Examples of reasons for revoking the Declaration of Pregnancy would irclude: end of pregnancy (child birth), early termination of pregnancy, termination of planned pregnancy. or desire to return to previous work assignment (if applicable).
Revoking of Declaration of Pregnancy is accomplished by contacting the RSO and completing the Revoking of Declaration of Pregnancy Form (Refer to sample Form 5-
- 2) Following the Revoking of the Declaration of Pregnancy, the female's exposure limits return to the Cushing site's occupational exposure limits as identified in Section 2.4 of this Radiation Safety Plan.
5.6 Frnosure I imits and Control The dose limit to the embryo / fetus of a Declared Pregnant Woman is 500 mrem for the l
entire pregnancy.
If upon declaration it is determined that the dose to the embryo / fetus is at 450 mrem or more, the dose limit shall be 50 mrem for the rest of the pregnancy.
Efforts shall be made to avoid substantial variations above a uniform monthly exposure rate to a Declared Pregnant Woman.
The Declared Pregnant Woman, her Supervisor, and the RSO shall determine radiological work restrictions needed to minimize exposure to the embryo / fetus and to ensure that the embryo / fetus exposure limit is not exceeded.
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SAAIPLE FORAI 5-1 RISK FRO 51 PRENATAL EXPOSURE AND DECLARED PREGNANT WOSIAN POLICY I,
. have been instructed and understand the following information:
a.
The risks associated with prenatal exposure to the :mbryo/ fetus.
b.
Kerr-McGee recommends declaration of pregnancy as soon as possible.
c.
Declaration of pregnancy is volumarv.
d.
Declaration of pregnancy shall not affect employment.
e.
The dose limit to the embryo / fetus of a Declared Pregnant Woman is 500 mrem for the entire pregnancy.
f.
Declaration of pregnancy shall be kept confidential.
Radiation Worker Signature Date l
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o S/d1PLE FORM 5-2 DECLARATION OF PREGNANCY 1.
, am voluntarily declaring my pregnancy. My estimated date of conception is i understand the risks associated with prenatal exposure to the embryo / fetus and shall comply with radiological work restrictions in order to meet the embryo / fetus dose limit of 500 mrem for the entire pregnancy.
Declared Pregnant Woman Signature Date Exposure to embryo / fetus at time of declaration:
Radiation Safety Officer Sign:ture Date REVOKING DECLARATION OF PREGNANCY 1.
, am voluntarily revoking my declaration of pregnancy.
I have been briefed on my new exposure limits and recognize them as my exposure limits for occupational exposure.
Person Revoking Declaration of Pregnancy Effective Date Radiation Safety Officer Signature Date Radiation Safety Plan 5-4' Rev.2
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SECTION 6 1
VISITOR EXPOSURE CONTROL t
i 6.1 Access Reauirements and Restrictions All visitor access shall be approved by the Site Manager. RSO. and/or their Designated Alternates prior to entry into radiologically restricted areas and/or radioactive materials areas.
Visitors shall sign the visitor's log when they enter and leave the Cushing facility.
Authorized visitors shall be escorted and properly supervised while in radiologically restricted areas and/or radioactive materials areas.
Visitors shall not handle radioactive material unless specifically trainea for such activity and pre-authorized to do so by the Site Manager. RSO. and/or Designated Alternate (s).
All visitor training requirements shall be met prior to entry into radiologically restricted areas and/or radioactive materials areas (Refer to Section 12 of this Radiation Safety Plan).
Visitors shall be issued a film badge while in radiologically restricted areas and/or radioactive materials areas.
Visitors shall be under the direct supervision of a visitor escort.
When a visitor enters radiologically restricted areas and/or radioactive materiah areas their escort shall be radiation worker qualified, at a minimum.
All personnel shall survey their hands and feet. as a minimum for contamination using a portable survey instrument when exiting radiologically restricted areas and/or radioactive materials areas. Visitors may perform these surveys under the direct supervision, guidance, and assistance of a qualified radiation worker or HP Technician.
These surveys shall be documented in the appropriate log.
Lapel air samples are not required for sirap'e tours. However, if visitors will be touring an area where work involving radioactive material is being performed. then some air sampling may be required. The RSO and/or Designated Alternate shall make this determination.
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j SECTION 7 l
RADIOLOGICAL AREA CONTROL i
7.1 Definitions Radiation Area - An area, accessible to individuals. in which radiation levels could l
result in an individual receiving a dose equivalent in excess of 5 mrem in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at 30 l
centimeters from the radiation source or from any surface that the radiation penetrates.
Radioactive Materials Area - Any area or room in which licensed material is used or stored in an amount exceeding 10 times the quantity specified in Appendix C.10 CFR 20.
Radiological Restricted Area - An area, access to which is limited by the licensee for the pugose of protecting individuals against undue risks from exposure to radiation and radioactive materials.
Unrestricted Area - An area, access to which is neither limited nor controlled by the licensee.
7.2 Postina Reauirements Radiation Areas at the Kerr-McGee Cushing site shall be posted in accordance with the requirements listed in the definition above. Radiation Areas shall be posted with a conspicuous sign or signs bearing a magenta. purple. or black colored radiation symbol on a yellow background with the words " Caution Radiation Area" Access controls into a specific Radiation Area will be addressed by the RSO or Alternate, as appropriate or needed, relative to the hazard involved.
Radioactive Materials Areas at the Kerr-McGee Cushing site shall be posted in accordance with the requirements listed in the definition above. Radioactive Materials Areas shall be posted with a conspicuous sign or signs bearing a magenta. purple, or black colored radiation symbol on a yellow background with the words " Caution Radioactive Material" Specific access controls into a specific Radioactive Materials Area will be addressed by the RSO or Alternate. as appropriate or needed. relative to the hazard involved.
Radictogical Restricted Areas shall be posted at the Kerr-McG< Cushing site in accordance with the requirements listed for demonstration of compliance with the public exposure limits listed in 10 CFR 20. Radiological Restricted Areas should be posted with a sign that identifies the area as a " Restricted Area". Physical access controls (e.g.. physical barricade, fence) shall be used to limit personnel access.
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L*nrestricted Areas at the Kerr-McGee Cushing she are not posted and access to them is t
neither limited nor controlled for radiological purposes.
7.3 Area Surveys and T imiu Radiological Restricted Areas. Radioactive Materials Areas. and other de'signated areas / buildings within the site should be surveyed in accordance with Section 8 of this plan on a routine basis. Results should be' documented on the appropriate form and/or survey map, as appropriate. Area posting (s) should be reviewed to ensure that current
)
posting (s) are in compliance with current survey results.
Equipment and/or materials located within a Radiological Restricted Area and/or
- Radioactive Materials Area shall be surveyed in accordance with Section 8 of this plan by a HP technician prict to removal from area. Contamination limits for release of equipment or materials from a Radiological Restricted Areas and/or Radioactive Materials Area to an Unrestricted Area are listed in Section 11 of this plan.
7.4 General Access Reauiremems A film badge shall be worn by all personnel entering designated radiologically
' restricted areas and/or radioactive materials areas.
Specific access requirements for entry into radiologically restricted areas and/or radioactive materials areas may be listed on Special Work Permits (SWP). All personnel shall review the appropriate Special Work Permit and comply with its requirements prior to entry.
Prior to leaving radiologically restricted areas and/or radioactive materials areas, all personnel shall survey a minimum of their hands and feet with the appropriate survey instruments. Vehicles and equipment are surveyed and released from radiological restricted areas and/or radioacuve materials areas in accordance Section i1 of this plan.
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SECTION 8 RADIOLOGICAL SURVEYS J
8.1 Surface Contamination l
1 Removable contamination surveys are performed to determine the average removable radiological contamination levels on a particular surface and reference that level to a specific limit or area. It is usually referenced to disintegrations per minute (dpm) per 2
100 cm or dpm per large-area wipe.
Radiological surveys for direct (fixed plus removable) contamination are performed to determine the average direct contamination levels on a panicular surface and reference that level to a specific limit or area. It is usually referenced 'o dpm per 100 cnf or dpm per probe area.
Direct contamination surveys can be performed using two methods: scanmng and integrating, a.
Scanning surveys are used when it is desirable to survey large areas for surface contamination. Scanning may or may not be sensitive enough to see actual contamination release limits.
b.
Integrating surveys are used when it is desirable to quantify contamination levels with more precision than a scanning survey using a count rate meter.
8.2 External Radiation Radiological surveys for external gamma radiation are performed to quantify the levels of radiation that individuals temployees or members of the public) are exposed to as a result of radiation emitted from radioacuve material or radiation producing devices.
l These surveys enable HP Technicians to monitor and estimate a person's external radiation exposure. and to quantify external radiation levels in a given area.
Micro-R meters are used to measure radiation levels in the Micro-Roentgen or Micro-Rem (one Micro-Roentge.n= lx10' Roentgens) per hour range. Exposure rates in the Micro-R per hour range are normally considered to be environmental exposure rates.
Milli-R (mR) meters are used to measure radiation levels in the Milli-Roentgen or Milli-Rem (one Milli-Roentgen = lx10 3 Roentgens) per hour range. These are usually i
referred to as dose rate meters because they work in what is considered the occupational dose rate range as opposed to a Micro-R meter which is used in the environmental dose rate range.
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8.3 Airborne Radioactive Materials
. Radiological surveys for airborne radioactive materials are performed to quantify the levels of airborne radioactive materials to which personnel are exposed. These surveys enable HP Technicians to monitor and estimate a person's laternal exposure to 1
tadioactive material. Two types of air sampling are used: area air sampling and personal air sampling. Area air sampling is used to monitor and measure the airborne radioactive material in a panicular area of concern. such as a job site or a work location where one or more workers are located. Personal air sampling is used to more closely monitor the air breathed by an individual worker.
Downwind Area Air Sampling is required when:
]
a.
specified in a Special Work Permit.
b.
work activities are being performed that would cause the potential of producmg airborne radioactisity, such as eartivnoving. or c.
specified by the RSO or Designated Alternate.
Personal Air Sampling (Issuance of Lapel Air Samplers) is required when:
1 a.
specified in a Special Work Permit, b.
there is a reasonable probability that personnel may be exposed to airborne radioactive material. or c.
specified by the RSO or HP staff.
i Lapei air samplers may be issued at a minimum of one t 1) per work crew, or a maximum of one i1) per individttal. depending on the work scope and the potential for worker exposure.
The RSO and the Site Manager shall be notified it:unediately when an area or personal air sample indicates airborne radioactivity levels in excess of 0.5 DAC. An evaluation shall be performed by the RSO and the Site Manager to determine what dust suppression measures were in effect and what additional measures should be implemented, if any.
If an air sample is in excess of 1.0 DAC. work shall stop until the conditions are changed to prevent a recurrence.
Radiation Safety Plan 8-2 Rev. 2
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- Documentation Radiological surveys associated with this section shall be maintained as a permanent record and shall be maintained pursuant to NRC regulations for decommissioning records or as specified in 10 CFR 19 and/or 20. whichever is longer. These records shall include as a minimum:
a.
surveyor's name! signature.
b.
date of survey, c.
instrument serial number, d.
instrument calibration due date, instrument response check infor. nation as appropriate, e.
f.
location of survey, and g.
approval signature of the appropriate reviewer.
The RSO (or his designeet shall review survey records. These reviews will ensure the survey records contain the information essential to the decommissioning of this facility.
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SECTION 9 ENVIRONMENTAL MONITORING 9.1 Purnose Air, surface water groundwater. soil and vegetation samples are collected to determine their concentration of licensed materials in these media.
l 9.2 Air Three high volume air samplers are used to monitor the release of airborne contaminants to unrestricted areas.
9.3 Surface Water Surface water samples are collected and analyzed annually. Upstream and downstream surface water samples are collected at the property line to monitor the concentration of licensed material in the surface waters. Surface water samples are analyzed for gross alpha and beta activity. Analyses for uranium and thorium concenention will be performed for samples that have gross activity exceeding 15 pCi/;ur.
9.4 Groundwater Groundwater samples are ce"ected and analyzed annually from 5 groundwater monitoring wells, at a minimum. Groundwater samples are analyzed for gross alpha and beta activity. Analyses for uranium and thotium concentration will be performed for samples that have gross activity exceeding 15 pCilliter.
9.5 Sail Soil samples are collected annually at 8 locations on the site. Each sample is analyzed for Uranium and Thorium content.
9.6 Veeetation Vegetation samples are cohected annually at 8 locations on the site. Each sample is analyzed for Uranium and Thorium content.
9.7 Gamma Radiation Monitoring Gamma radiation is monitored with TLD packets. The TLD packets are changed and processed quarterly.
Radiation Safety Plan 9-1 Rev.2
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9.8 Snecial Samnies l
Special samples shall be collected if there is a release. or suspected release of radioactive contamination to any environmental media.
Should an unintentional release occur, appropriate measures shall be taken to monitor the release of radioactive materials to the environment. These measures may include.
but are not limited to:
l a.
placement of area air sampler (s) downwind from the release, b.
installation of lapel air samplers on all personnel working in the area, c
. collecting soil samples, and/or d.
collecting surface water samples.
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Radiation Safety Flan 9-2 Rev.2
O SECTION 10 WASTE MONITORING AND DISPOSAL 10.1 Solid Waste Solid waste generated in unaffected areas. such as the office areas in Building A-9. or in uncontaminated areas of the site shall be considered radioactively uncontaminated solid waste and disposed of accordingly.
Solid waste generated in radioactive material areas or areas under investigation for radioactive materials (Undesignated Areas - UDAs), shall be surveyed in accordance with Section 8 of this Radiation Safety Plan, unless the waste cannot be economically surveyed. Solid waste found to be above release limits or that cannot be economically surveyed to verify that it is uncontaminated. shall be treated as radioactively contaminated waste and disposed of accordingly.
Compactible solid radioactive waste (e.g., disposable clothing. plastic, tape) may be segregated and packaged for compaction prior to disposal as radioactive waste.
Decontamination of solid waste that is identified as radioactively contaminated may be attempted if it is determined that the decontamination efforts would be economically feasible and meet ALARA standards.
Solid waste which meets the relcase of material for unrestricted use criteria listed in Section 11 of this Radiation Safety Plan shall be considered radioactively uncontaminated solid waste and disposed of accordingly.
10.2 llouid Waste Laundry system water (when radiologically contaminated materials are cleaned),
rainwater that collects in radioactive materials areas, and decontamination cleaning solutions represent potential sources of liquid radioactive waste generated at the site.
All liquid wastes, which have the potential of containing licensed radioactive materials.
are sampled and analyzed for gross alpha activity. If the material is determined to meet the release limits of 10 CFR 20, it is disposed of as radioactively uncontaminated liquid waste.
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SECTION 11 RELEASE OF MATERIAL OR EQUIPMENT FOR UNRESTRICTED USE 11.1 Release of Material or Eauinment All material and equipment shall be surveyed by a HP technician in accordance with the methods specified in Section 8 of this Radiation Safety Plan prior to removal from any radioactive materials area. HP approval is required to remove tools, equipment or material from radioactive materials areas for use elsewhere. Survey results and release documentation are Quality Assurance documents.
The individual requesting removal of material or equipment shall contact a HP j
technician to perform a radiological survey of the material or equipment.
The history of the equipment or material to be surveyed for release shall be provided by the requester to the HP technician, if known.
The HP technician shall perform the appropriate surveys required to meet the release limits specified in Table 11-1. Normally, surveys for both alpha and beta-gamma radiation. and surveys for both removable and direct shall be performed. The RSO may be contacted for guidance, as necessary. Any item that has internal surfaces that cannot be surveyed and could be contaminated internally shall not be released from a radioactive materials area for unrestricted use without RSO aoproval.
11.2 Documentation Surveys generated by this section shall be maintained as a permanent record. These records shall be documented as specitied in Secuoti 8 of this Radiation Safety Plan.
The RSO (or designeet shall review the survey records generated by this section.
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TABLE 11-1 ACCEPTABLE SURFACE CONTAMINATION LEVELS i
i Nuclides' l
Average Maximum"3
'Removablehdd ul Nat'l U. U235. U238. assoc.
. 5000 dpm a/100 cnf 15000 dpm all00 cnf 1000 dpm a/100 cnf decay products Nat'l Th, and Th232 1000 dpm al100 cnf 3000 dpm a/100 cnf 200 dpm a/100 cnf 670 dom B/100 cui 2010 dpm B/100 caf 134 dpm B/100 cnf Beta gamma emitters 5000 dpm By/100 cm 15000 dpm By/100 cnf 1000 dpm By/100 cnf (nuclides with decay modes other than alpha emission or spontaneous fission) except:
for Sr90 and others noted above
.a Where surface contamination by both alpha and beta-gamma emitting nuclides exists the limits established for alpha and beta-gamma emitting nuclides should apply independently.
b As used in this table. dpm (disintegrations per minute) means the rate of emission by radioactive l
material as determined by correcting the counts per minute observed by an appropriate detector for background, efficiency, and geometric factors associated with the instrumentation.
c Measurements of average contaminant should not be averaged over more than i square meter. For objects of less surface area. the average shot.ld be derived for each object.
d'
~ The maximum contammation level applies to an area of not more than 100 cm The amount of removable radioactive material per l00 cni of surface area should be determined by l
e wiping that area with a dry tilter or sort absorbent paper, applying moderate pressure, and assessing the amount of radioactive material on tne wipe with an appropriate instrument of known efficiency.
When removable contamination on objects of less surface area is determined, the pertinent levels should be reducea proportionally and the entire surface should be wiped.
f Average and maximum radiation levels associated with surface contamination resulting from beta-
. gamma emitters should not exceed 0.2 mrad /hr at I cm and 1.0 mrad /hr at I cm. respectively, measured through not more than 7 milligrams per sauare centimeter of total absorber.
Radiation Safety Plan 11 - 2 Rev. 2
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SECTION 12 i
RADIATION SAFETY TRAINING j
12.1 Introduction All individuals working in or frequenting any portion of a restricted area are given radiation safety training commensurate with the potential radiological health hazards in the restricted area.
The RSO or Designated Alternate shall determine the potential radiological health hazard for all individuals working in or frequenting any portion of a restricted area and determine the commensurate level of training required.
12.2 Rndworker Training Workers classified as radiation workers" (refer to definition of radiation worker in i
glossary section of this Radiation Safety Plan) shall receive initial radworker training.
In addition they shall receive annual radworker requalification training. when applicable.
Initial radworker training and annual radworker requalification training shall include all
)
of the topics described in 10 CFR 19.12. at a minimum.
All personnel shall obtain a minimum mastery score of 70 percent on radworker training course final exams. This includes the initial and annual requalification courses.
12.3 Non-Radworker Traininn Non-radworker training is given to those individuals who are not classified as radiation workers" The P.SO or Designated Alternate shall determine the radiation safety topics and level of detail necessary based on the potential radiological health hazard for the individual (s). Topics from the radworker training courses may be selected, as deemed appropriate /necessary.
Radiation Safety Plan 12 - 1 Rev.2
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l GLOSSARY ABSORBED DOSE: The energy imparted by ionizing radiation per unit mass of irradiated material. The units of absorbed dose are the rad and the gray (Gy). One (1) rad is equal to l
100 ergsigram or 0.01 gray (1 gray = 100 rads).
ACTIVITY: The rate of disintegration or decay of radioactive material. The units of activity are the curie (Ci) and the becquerel (Bq). 1 Curie equals 3.7 E10 dps. I Becquerel equals I dps. The units of Milli (Symbol m. equal to IE-3), Micro (Symbol g, equal to IE-6), and Pico (Symbol p. equal to 1E-12) are commonly used in conjunction with the curie to describe lower-quantity values.
ADULT: An individual 18 or more years of age.
1 AIRBORNE RADIOACTIVITY AREA: A room, enclosure, or area in which airborne radioactive materials. composed wholly or partly of licensed material. exists in concentrations in excess of the derived air concentrations (DAC) specified in appendix B of 10CFR20 or to such a degree that an individual present in the area without respiratory protection equipment could exceed. during the hours an individual is present in a week, an intake of 0.6% of the Annual Limit on Intake (ALI) or 12 DAC-hrs.
ALARA: Acronym for "As Low As Reasonably Achievable", a basic concept of radiation protection that specifies that exposures to radiation should be kept as far below established dose limits as is practical. taking into account economic and feasible conditions.
ALPHA PARTICLE: A positively charged particle spontaneously ejected from the nuclei of certain radioactive elements. It is identical to a helium nucleus that has a mass number of 4 and an electrostatic charge of +2.
It has low-penetrating power and short range. The most energetic alpha particle will generally fail to penetrate the skin. Alpha particles can present a health hazard when an alpha-emitting isotope is introduced into the body.
ANNUAL LIMIT ON INTAKE (ALI): The derived limit for the amount of radioactive material taken into the body of an adult worker by inhalation or ingestion in a year. ALI is the smaller value of intake of a given radionuclide in a year by the reference man that would result in a committed effective dose equivalent of 5 rems or a committed dose equivalent of 50 rems to any individual organ or tissue.
ATOMIC NUMBER (Symbol Z): The number of protons in the nucleus of an atom.
BACKGROUND RADIATION: Radiation from cosmic sources; naturally occurring radioactive materials. including radon and global fallout as it exists in the environment from the testing of nuclear explosive devices. " Background Radiation" does not include radiation from source, byproduct or special nuclear materials regulated by the NRC.
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H BETA PARTICLE: A negatively charged particle emitted from a nucleus during radioactive decay. A beta particle has a mass equal to 1/1837 that of a proton. The beta particle is
, iderttical to an electron. A positron is a positively charged " beta" particle. Significant beta j
radiation may cause skin burns, and beta emitters are harmful if they are introduced into the body. Beta particles are easily stopped by a thin sheet of metal or plastic.
BIOASSAY: The determination of kinds. quantities or concentrations, and in some cases. the locations of radioactive materials in the human b'ody, whether by direct measurement (in vivo counting) or by analysis and evaluation of materials excreted or removed from the human body.
BIOLOGICAL HALF-LIFE: The time required for a biological system. such as a person, to eliminate by natural processes (other than radioactive decay) one-half of any amount of a substance (primary concern are radionuclides) that has entered it.
BY-PRODUCT MATERIAL: A) The tailings or wastes produced by the extraction of uranium or thorium from any ore processed primarily for its source material content. including discrete surface wastes resulting from uranium solution extraction processes. B) Any radioactive material (except special nuclear material) yielded in or made radioactive by exposure to the radiation incident to the process of producing or utilizing special nuclear material.
CALIBRATION: The determination of or correction of the accuracy of an instrument to assure it operates within appropriate limits of accuracy.
CLASS (OR LUNG CLASS): A classification scheme for inhaled material according to its rate of clearance from the pulmonary region of the lung. Staterials are classified as D. W. or Y which applies to a range of clearance half-times: for Class D (Days > of less than 10 days, for Class W (Weeks) from 10 to 100 days and for Class Y (Yearsi of greater than 100 days.
COh1MITTED DOSE EQUIVALENT: The dose equivalent to organs or tissues that will be received from an intake of radioactive material by an individual during the 50 year period following the intake.
COh1MITTED EFFECTIVE DOSE EQUIVALENT: The sum of the products of the weighting factors applicable to each of the body organs or tissues that are irradiated and the committed dose equivalent to these organs or tissues.
CONTA'.11 NATION: Deposition of radioactive material in an unwanted location.
COUNT: A) The numeric reading produced by a device designed to detect ionizing events. In
' this usage a " count" refers to the number )f detected events registered in a given period of time. B) A signal from a device designed to detect ionizing events. In this usage a " count" is the instmmem's recording of in iomzation event.
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i COUNTER: A radiation detection instrument or survey meter that detects and/or measures 1
radi,ation. A) PROPORTIONAL COUNTER: A gas filled radiation detection tube in which the voltage pulse produced by the tube is proportional to the number of ions formed in the gas by the primary ionizing particle. Voltage pulses are counted by associated circuitry. B)
SCINTILLATION COUNTER: A combination of scintillator photo multiplier tuce. and associated circuits for counting light emissions produced within the scintillator by an ionizing panicle. Phosphor, zinc sulfide and sodium iodide crystals are the most commonly used scintillators.
CPM (Counts Per Minute): The rate of ionizing event occurrence recorded by a radiation detection instrument designed to count ionizing events caused by radiation.
DAUGHTER PRODUCT: An isotope formed by the radioactive decay of another isotope.
E.G.- radium-226 generates several successive daughter products, ending with the stable isotope leaa-206.
DECLARED PREGNANT WOMAN: A woman who has voluntarily informed her employer. in writing, of her pregnancy and the estimated date of conception.
DEEP-DOSE EQUIVALENT: Applies to external whole body exposure, is the dose equivalent at a tissue depth of I centimeter.
DECONTAMINATION: The reduction or removal of radioactive contamination from a structure. area. object, or person.
DERIVED AIR CONCENTRATION IDACh The concentration of a given radionuclide in air which. if breathed by reference man for a working year of 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> under conditions of light work. results in the intake or ALI.
DETECTOR: A material or device tnat is sensitive to radiation and can produce a response signal suitable (with proper calibratioru for measurement or analysis. A radiation detection instrument.
DOSE EQUIVALENT: The product of the absorbed dose in tissue. quality factor, and all other necessary modifying factors at the location of interest.
DOSE RATE: The radiation dose delivered per unit of time.
DPM: Abbreviation for disintegrations per minute. The rate of nuclear transformation or disintegration by radioactive emission. Disintegrations per second (dps) may also be used to describe the rate of nuclear transformation or disintegration by radioactive emission.
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EFFECTIVE DOSE EQUIVALENT: The sum of the products of the dose equivalent to the organ or tissue and the weighting factors applicable to each of the body organs or tissues that are irradiated.
EMBRYO / FETUS: The developing human organism from conception until the time of birth.
EXPOSURE: Being exposed to ionizing radiation or radioactive material.
EXTERNAL RADIATION: Exposure to ionizing radiation located outside the body.
EXTREMITY: The hand, elbow, arm below the elbow. foot. knee. or leg below the kree.
EYE DOSE EQUIVALENT: The external exposure to the lens of the eye taken as the dose equivalent at a tissue depth of 0.3 centimeters.
FILM BADGE: A pack of photographic film used for approximate measurement of radiation exposure for personnel monitoring purposes. The badge may contain two or three films of differing sensitivity, and it may contain a filter that shields part of the film from certain types of radiation.
FIXED CONTAMINATION: Radioactive material which cannot be easily be removed without removing or partially removing a layer of surface material by either chemical or mechanical means (e.g., acids sand blasting, grinding).
GAMMA RAY: High energy, short wavelength electromagnetic radiation (no mass. just energy) emitted from the nucleus, Gamma radiation frequently accompanies alpha and beta emissions and always accompanies tission. Gamma rays are generally very penetrating and are best stopped or shielded by dense materials, such as lead or uranium. Gamma rays are similar to X-rays (which are emitted from the electron shell). but are usually more enercetic.
GRAY: tGy) is the SI unit of absorbed dose. One gray is equal to an absorbed dose of 1 joule / kilogram (100 rads).
HALF-LIFE: The time required for a radioactive substance to lose 50% of its activity by decay Each radionuclide has a unique half-life.
HEALTH PHYSICS: The science concerned with recognition. evaluation. and control of health hazards from ionizing radiation.
HIGH RADIATION AREA: An area accessible to individuals. in which radiation levels l
could result in an individual receiving a dose equivalent in excess of 0.1 rem in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at 30 centimeters from the radiation source or from any surface that the radiation penetrates.
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INTERNAL RADIATION: Ionizing radiation resulting from radioactive substances inside the body. Some examples are Carbon-14. Potassium-40, and Radium-226. which are naturally
. - present in the environment.
IN-VITRO SIEASURE31ENT: In-vitro measurements are measurements made of samples taken from an organism te.g.. urine and fecal bioassay samples).
IN-VIVO MEASURE 31ENT: In-vivo measurements are measurements made of an actual organism (e.g., lung counts or whole body counts).
ISOTOPES: Nuclides having the same atomic number but different mass numbers. Isotopes of uranium include: U-234, U-23S U-236, U-237, and U-238. Isotopes have identical chemical properties but different radiological characteristics.
MASS NUMBER (Symbol A): The mass of an atom relative to other atoms. The present basis for the scale of atomic weights is carbon: the most common isotope of this element has arbitrarily been assigned an atomic weight of 12. The unit atomic mass is 1/12 the weight of the carbon-12 atom. or roughly the mass of one proton or one neutron. The atomic weight of any element is approximately equal to the total number of protons and neutrons in its nucleus.
NEUTRON RADIATION: An uncharged particle emitted from the nucleus of an atom.
Neutrons have a relatively high penetration capability. Hydrogenous materials (e.g.- wax, water) are effective shields for neutron radiation.
NRC: Nuclear Regulatory Commission. A federal agency responsible for licensing the transportation. handling processing, and disposal of radioactive materials. The NRC also enforces compliance with regulations governing the transportation. handling processing, and disposal of radioactive materials.
NONSTOCHASTIC EFFECT: Health effects, the severny of which varies with the dose and for which a threshold is believed to exist. Examples: Radiation induced cataracts, sterility.
tissue damage.
NUCLIDE: A species of atom characterized by the constitution of its nucleus. The nuclear constitution is specified by the number of protons (Z). number of neutrons (N), and energy content.
OCCUPATIONAL DOSE: The dose received by an individual in the course of employment in which the individual's assigned duties involve exposure to radiation and/or radioactive material from licensed and unlicensed sources of radiation, whether in the possession of the licensee or other person. Occupational Dose does not include dose received from background radiation. as a paticnt from medical practices, from voluntary participation in medical research programs or as a member of the general public.
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PLANNED SPECIAL EXPOSURE: An infrequent exposure to radiation, separate from and in addition to the annual dose limits.
PROTECTIVE CLOTHING: Clothing provided to reduce > 3esure and prevent the spread of contamination to personal clothing or the body while performmg work with radioactive materials.
i PUBLIC DOSE: Dose received by a member of the public from exposure to radiation and/or I
radioactive material released by a licensee. or to any other source of radiation under the control of a licensee.
QUALITY FACTOR: The modifying factor that is used to derive dose equivalent from absorbed dose. A) X, gamma, or beta radiation QF= 1. B) Neutrons of unknown energy QF=10. C) High-energy protons QF=10. D) Alpha particles, multiple-charged particles, fission fragments and heavy particles of unienown charge QF=20.
l RADIATION AREA: An area, accessible to individuals, in which radiation levels could result in an individual receiving a dose equivalent in excess of 0.005 rem in I hour at 30 centimeters from the radiation source or from any surface that the radiation penetrates.
RADIATION WORKER (RADWORKER): A person who, in the course of employment in j
which the individual's assigned duties involve exposure to radiation and/or radioactive material l
from licensed and unlicensed sources of radiation, has the potential to exceed 100 mrem / year TEDE. (Cushing Site Definition)
RESTRICTED AREA: An area. access to which is limited by the licensee for the purpose of protecting individuals against undue risks from exposure to radiation and radioactive materials.
RADIOACTIVE MATERIALS AREA: Any area or room which licensed material is used or stored in an amount exceeding 10 times the quantity specified in Appendix C.10CFR20.
REFERENCE MAN: A person with the anatomical and physiological characteristics defined in the report of the International Commission on Ndiation Protection ilCRP) Task Group on Reference Man (ICRP Publication No. 23).
REM: The special unit of any of the quantities expressed as dose equivalent. The dose equivalent in rems is equal to the absorbed dose in rads multiplied by the quality factor. One (1) rem is equal to 0.01 sievert (or 100 rem = 1 sievert).
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l RESPIRATOR: Respiratory protective equipment prcvided for protection against inhalation of airborne particles. Half-face respirators, full-face respirators, and supplied air respirators are used when appropriate to provide needed protection.
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s SIEVERT: The SI unit of dose equivalent. The dose equivalent in sieverts is equal to the absorbed dose in grays multiplied by the quality factor (1 rem = 0.01 sieverts.)
SH LLOW DOSE EQUIVALENT: Applies to the external exposure of the skin or an extremity. Shallow Dose Equivalent is taken as the dose equivalent at a tissue depth of 0.007 cm. averaged over area of I crrf.
SITE BOUNDARY: That line beyond which the land or property is not owned, leased, or othenvise controlled by the licensee.
SOURCE MATERIAL: Uranium or thorium. or any combination thereof. in any physical or chemical form.
SMEARABLE CONTAMINATION: Radioactive material which can easily be removed from a surface (e.g., soap and water, light brushing, wiping).
SPECIAL NUCLEAR MATERIAL: Plutonium, uranium 233 uranium enriched in U-233 or U-235. and any other material which the Commission deems Special Nuclear Material but not including Source Material.
SPECIAL WORK PERMIT: A work permit that is reviewed by Health Physics personnel.
~ all parties assigned to perform a task, and all parties affected by the task prior to beginning l:
work.
STOCHASTIC EFFECT: Health effects that occur randomly and for which the probability of the effect occurring. rather than its severity. is assumed to be a linear function of dose without threshold. Examples: Hereditary effects and cancer incidence.
SURVEY METER: Any portable radiation detection instrument adapted for surveying an area to establish the absence of or the amount of radioactive material present.
TOTAL EFFECTIVE DOSE EQUIVALENT (TEDE): The sum of the deep dose equivalent (external exposure) and the committed effective dose equivalent (internal exposure).
TOTAL ORGAN DOSE EQUIVALENT (TODE): The sum of the deep dose equivalent (external exposure) and the committed dose equivalent (internal exposure) to any individual organ or tissue other than the lens of the eye.
UNRESTRICTED AREA: An area access to which is neither limited nor controlled by the licensee.
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