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Page Title:
Planning for Maintenance, Operations, and Modifications |
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|  DOE-STD-1098-99
Radiological Control
Conduct of Radiological Work
June 2004
4.
The site-specific radiological control manual should establish trigger levels requiring formal radiological review of
non-routine or complex work activities. The trigger levels should be based on radiological conditions in existence or
expected prior to implementation of the job-specific engineering and administrative controls. These appropriate
trigger levels should include:
a.
Estimated individual or collective d ose greater than preestablished values (e.g., any individual likely to receive
a dose exceeding 50% of the local administrative control level or collective dose likely to exceed 1 man-rem)
b.
Predicted airborne radioactivity concentrations in excess of pre established values (e.g., greater than 10 times
the applicable DAC value(s) provided in 10 CFR 835)
c.
Removable contamination on accessible surfaces greater than pre -established values (e.g., greater than 100
times the values in Table 2-2)
d.
Entry into areas where dose rates exceed 1 rem/hour
e.
Potential releases of radioactive material to the environment.
5.
For non-routine or complex tasks a formal hazards analysis should be conducted using a nationally recognized
process as discussed in DOE G 440.1. This review is in addition to the formal radiological review discussed above.
An integrated set of controls for all hazards (e.g., radiological, chemical, and physical) should be developed from
this hazard analysis.
6.
At a minimum, the formal radiological review should consider the following:
a.
Inclusion of radiological control hold points in the technical work documents
b.
Elimination or reduction of radioactivity through line flushing and decontamination
c.
Use of work processes and special tooling to reduce time in the work area
d.
Use of engineered controls to minimize the spread of contamination and generation of airborne radioactivity
e.
Specification of special radiological training or monitoring requirements
f.
Use of mock-ups for high exposure or complex tasks
g.
Engineering, design, and use of temporary shielding to reduce radiation levels
h.
Walkdown or dry -run of the activity using applicable procedures
i.
Staging and preparation of necessary materials and special tools
j.
Maximization of prefabrication and shop work
k.
Review of abnormal and emergency procedures and plans
l.
Identification of points where signatures and second party or independent verifications are required
m.
Establishment of success or completion criteria, with contingency plans to anticipate difficulties
n.
Development of a pre -job estimate of collective dose to be incurred for the job
o.
Provisions for waste minimization and disposal.
7.
Radiological control requirements identified as part of the above formal radiological review should be documented in
the job plans, procedures, or work packages.
8.
The ALARA Committee should review and approve plans for radiological work anticipated to exceed site-specific
individual or collective dose criteria.
3-4
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