Appendix I to Part 50 - Numerical Guides for Design Objectives and Limiting Conditions for Operation To Meet the Criterion “As Low as is Reasonably Achievable” for Radioactive Material in Light-Water-Cooled Nuclear Power Reactor Effluents
10:1.0.1.1.30.0.117.88.31 : Appendix I
Appendix I to Part 50 - Numerical Guides for Design Objectives and
Limiting Conditions for Operation To Meet the Criterion “As Low as
is Reasonably Achievable” for Radioactive Material in
Light-Water-Cooled Nuclear Power Reactor Effluents
SECTION I. Introduction. Section 50.34a provides that an
application for a construction permit shall include a description
of the preliminary design of equipment to be installed to maintain
control over radioactive materials in gaseous and liquid effluents
produced during normal conditions, including expected occurrences.
In the case of an application filed on or after January 2, 1971,
the application must also identify the design objectives, and the
means to be employed, for keeping levels of radioactive material in
effluents to unrestricted areas as low as practicable. Sections
52.47, 52.79, 52.137, and 52.157 of this chapter provide that
applications for design certification, combined license, design
approval, or manufacturing license, respectively, shall include a
description of the equipment and procedures for the control of
gaseous and liquid effluents and for the maintenance and use of
equipment installed in radioactive waste systems.
Section 50.36a contains provisions designed to assure that
releases of radioactive material from nuclear power reactors to
unrestricted areas during normal conditions, including expected
occurrences, are kept as low as practicable.
SECTION II. Guides on design objectives for
light-water-cooled nuclear power reactors licensed under 10 CFR
part 50 or part 52 of this chapter. The guides on design
objectives set forth in this section may be used by an applicant
for a construction permit as guidance in meeting the requirements
of § 50.34a(a), or by an applicant for a combined license under
part 52 of this chapter as guidance in meeting the requirements of
§ 50.34a(d), or by an applicant for a design approval, a design
certification, or a manufacturing license as guidance in meeting
the requirements of § 50.34a(e). The applicant shall provide
reasonable assurance that the following design objectives will be
met.
A. The calculated annual total quantity of all radioactive
material above background 1 to be released from each
light-water-cooled nuclear power reactor to unrestricted areas will
not result in an estimated annual dose or dose commitment from
liquid effluents for any individual in an unrestricted area from
all pathways of exposure in excess of 3 millirems to the total body
or 10 millirems to any organ.
1 Here and elsewhere in this appendix background means
radioactive materials in the environment and in the effluents from
light-water-cooled power reactors not generated in, or attributable
to, the reactors of which specific account is required in
determining design objectives.
B.1. The calculated annual total quantity of all radioactive
material above background to be released from each
light-water-cooled nuclear power reactor to the atmosphere will not
result in an estimated annual air dose from gaseous effluents at
any location near ground level which could be occupied by
individuals in unrestricted areas in excess of 10 millirads for
gamma radiation or 20 millirads for beta radiation.
2. Notwithstanding the guidance of paragraph B.1:
(a) The Commission may specify, as guidance on design
objectives, a lower quantity of radioactive material above
background to be released to the atmosphere if it appears that the
use of the design objectives in paragraph B.1 is likely to result
in an estimated annual external dose from gaseous effluents to any
individual in an unrestricted area in excess of 5 millirems to the
total body; and
(b) Design objectives based upon a higher quantity of
radioactive material above background to be released to the
atmosphere than the quantity specified in paragraph B.1 will be
deemed to meet the requirements for keeping levels of radioactive
material in gaseous effluents as low as is reasonably achievable if
the applicant provides reasonable assurance that the proposed
higher quantity will not result in an estimated annual external
dose from gaseous effluents to any individual in unrestricted areas
in excess of 5 millirems to the total body or 15 millirems to the
skin.
C. The calculated annual total quantity of all radioactive
iodine and radioactive material in particulate form above
background to be released from each light-water-cooled nuclear
power reactor in effluents to the atmosphere will not result in an
estimated annual dose or dose commitment from such radioactive
iodine and radioactive material in particulate form for any
individual in an unrestricted area from all pathways of exposure in
excess of 15 millirems to any organ.
D. In addition to the provisions of paragraphs A, B, and C
above, the applicant shall include in the radwaste system all items
of reasonably demonstrated technology that, when added to the
system sequentially and in order of diminishing cost-benefit
return, can for a favorable cost-benefit ratio effect reductions in
dose to the population reasonably expected to be within 50 miles of
the reactor. As an interim measure and until establishment and
adoption of better values (or other appropriate criteria), the
values $1000 per total body man-rem and $1000 per man-thyroid-rem
(or such lesser values as may be demonstrated to be suitable in a
particular case) shall be used in this cost-benefit analysis. The
requirements of this paragraph D need not be complied with by
persons who have filed applications for construction permits which
were docketed on or after January 2, 1971, and prior to June 4,
1976, if the radwaste systems and equipment described in the
preliminary or final safety analysis report and amendments thereto
satisfy the Guides on Design Objectives for Light-Water-Cooled
Nuclear Power Reactors proposed in the Concluding Statement of
Position of the Regulatory Staff in Docket-RM-50-2 dated February
20, 1974, pp. 25-30, reproduced in the annex to this appendix
I.
SECTION III. Implementation. A.1. Conformity with the
guides on design objectives of Section II shall be demonstrated by
calculational procedures based upon models and data such that the
actual exposure of an individual through appropriate pathways is
unlikely to be substantially underestimated, all uncertainties
being considered together. Account shall be taken of the cumulative
effect of all sources and pathways within the plant contributing to
the particular type of effluent being considered. For determination
of design objectives in accordance with the guides of Section II,
the estimations of exposure shall be made with respect to such
potential land and water usage and food pathways as could actually
exist during the term of plant operation: Provided, That, if
the requirements of paragraph B of Section III are fulfilled, the
applicant shall be deemed to have complied with the requirements of
paragraph C of Section II with respect to radioactive iodine if
estimations of exposure are made on the basis of such food pathways
and individual receptors as actually exist at the time the plant is
licensed.
2. The characteristics attributed to a hypothetical receptor for
the purpose of estimating internal dose commitment shall take into
account reasonable deviations of individual habits from the
average. The applicant may take account of any real phenomenon or
factors actually affecting the estimate of radiation exposure,
including the characteristics of the plant, modes of discharge of
radioactive materials, physical processes tending to attenuate the
quantity of radioactive material to which an individual would be
exposed, and the effects of averaging exposures over times during
which determining factors may fluctuate.
B. If the applicant determines design objectives with respect to
radioactive iodine on the basis of existing conditions and if
potential changes in land and water usage and food pathways could
result in exposures in excess of the guideline values of paragraph
C of Section II, the applicant shall provide reasonable assurance
that a monitoring and surveillance program will be performed to
determine:
1. The quantities of radioactive iodine actually released to the
atmosphere and deposited relative to those estimated in the
determination of design objectives;
2. Whether changes in land and water usage and food pathways
which would result in individual exposures greater than originally
estimated have occurred; and
3. The content of radioactive iodine and foods involved in the
changes, if and when they occur.
SECTION IV. Guides on technical specifications for limiting
conditions for operation for light-water-cooled nuclear power
reactors licensed under 10 CFR part 50 or part 52 of this
chapter. The guides on limiting conditions for operation for
light-water-cooled nuclear power reactors set forth below may be
used by an applicant for an operating license under this part or a
design certification or combined license under part 52 of this
chapter, or a licensee who has submitted a certification of
permanent cessation of operations under § 50.82(a)(1) or § 52.110
of this chapter as guidance in developing technical specifications
under § 50.36a(a) to keep levels of radioactive materials in
effluents to unrestricted areas as low as is reasonably
achievable.
Section 50.36a(b) provides that licensees shall be guided by
certain considerations in establishing and implementing operating
procedures specified in technical specifications that take into
account the need for operating flexibility and at the same time
assure that the licensee will exert his best effort to keep levels
of radioactive material in effluents as low as is reasonably
achievable. The guidance set forth below provides additional and
more specific guidance to licensees in this respect.
Through the use of the guides set forth in this section it is
expected that the annual release of radioactive material in
effluents from light-water-cooled nuclear power reactors can
generally be maintained within the levels set forth as numerical
guides for design objectives in Section II.
At the same time, the licensee is permitted the flexibility of
operations, compatible with considerations of health and safety, to
assure that the public is provided a dependable source of power
even under unusual conditions which may temporarily result in
releases higher than numerical guides for design objectives but
still within levels that assure that the average population
exposure is equivalent to small fractions of doses from natural
background radiation. It is expected that in using this operational
flexibility under unusual conditions, the licensee will exert his
best efforts to keep levels of radioactive material in effluents
within the numerical guides for design objectives.
A. If the quantity of radioactive material actually released in
effluents to unrestricted areas from a light-water-cooled nuclear
power reactor during any calendar quarter is such that the
resulting radiation exposure, calculated on the same basis as the
respective design objective exposure, would exceed one-half the
design objective annual exposure derived pursuant to Sections II
and III, the licensee shall: 2
2 Section 50.36a(a)(2) requires the licensee to submit certain
reports to the Commission with regard to the quantities of the
principal radionuclides released to unrestricted areas. It also
provides that, on the basis of such reports and any additional
information the Commission may obtain from the licensee and others,
the Commission may from time to time require the license to take
such action as the Commission deems appropriate.
1. Make an investigation to identify the causes for such release
rates;
2. Define and initiate a program of corrective action; and
3. Report these actions as specified in § 50.4, within 30 days
from the end of the quarter during which the release occurred.
B. The licensee shall establish an appropriate surveillance and
monitoring program to:
1. Provide data on quantities of radioactive material released
in liquid and gaseous effluents to assure that the provisions of
paragraph A of this section are met;
2. Provide data on measurable levels of radiation and
radioactive materials in the environment to evaluate the
relationship between quantities of radioactive material released in
effluents and resultant radiation doses to individuals from
principal pathways of exposure; and
3. Identify changes in the use of unrestricted areas (e.g., for
agricultural purposes) to permit modifications in monitoring
programs for evaluating doses to individuals from principal
pathways of exposure.
C. If the data developed in the surveillance and monitoring
program described in paragraph B of Section III or from other
monitoring programs show that the relationship between the
quantities of radioactive material released in liquid and gaseous
effluents and the dose to individuals in unrestricted areas is
significantly different from that assumed in the calculations used
to determine design objectives pursuant to Sections II and III, the
Commission may modify the quantities in the technical
specifications defining the limiting conditions in a license to
operate a light-water-cooled nuclear power reactor or a license
whose holder has submitted a certification of permanent cessation
of operations under § 50.82(a)(1).
SECTION V. Effective dates. A. The guides for limiting
conditions for operation set forth in this appendix shall be
applicable in any case in which an application was filed on or
after January 2, 1971, for a construction permit for a
light-water-cooled nuclear power reactor under this part, or a
design certification, a combined license, or a manufacturing
license for a light-water-cooled nuclear power reactor under part
52 of this chapter.
B. For each light-water-cooled nuclear power reactor constructed
pursuant to a permit for which application was filed prior to
January 2, 1971, the holder of the permit or a license, authorizing
operation of the reactor shall, within a period of twelve months
from June 4, 1975, file with the Commission:
1. Such information as is necessary to evaluate the means
employed for keeping levels of radioactivity in effluents to
unrestricted areas as low as is reasonably achievable, including
all such information as is required by § 50.34a (b) and (c) not
already contained in his application; and
2. Plans and proposed technical specifications developed for the
purpose of keeping releases of radioactive materials to
unrestricted areas during normal reactor operations, including
expected operational occurrences, as low as is reasonably
achievable.
Concluding Statement of Position of the Regulatory Staff
(Docket-RM-50-2) guides on design objectives for light-water-cooled
nuclear power reactors
A. For radioactive material above background 1 in liquid
effluents to be released to unrestricted areas:
1 “Background,” means the quantity of radioactive material in
the effluent from light-water-cooled nuclear power reactors at a
site that did not originate in the reactors.
1. The calculated annual total quantity of all radioactive
material from all light-water-cooled nuclear power reactors at a
site should not result in an annual dose or dose commitment to the
total body or to any organ of an individual in an unrestricted area
from all pathways of exposure in excess of 5 millirems; and
2. The calculated annual total quantity of radioactive material,
except tritium and dissolved gases, should not exceed 5 curies for
each light-water-cooled reactor at a site.
3. Notwithstanding the guidance in paragraph A.2, for a
particular site, if an applicant for a permit to construct a
light-water-cooled nuclear power reactor has proposed baseline
in-plant control measures 2 to reduce the possible sources of
radioactive material in liquid effluent releases and the calculated
quantity exceeds the quantity set forth in paragraph A.2, the
requirements for design objectives for radioactive material in
liquid effluents may be deemed to have been met provided:
2 Such measures may include treatment of clear liquid waste
streams (normally tritiated, nonaerated, low conductivity equipment
drains and pump seal leakoff), dirty liquid waste streams (normally
nontritiated, aerated, high conductivity building sumps, floor and
sample station drains), steam generator blowdown streams, chemical
waste streams, low purity and high purity liquid streams (resin
regenerate and laboratory wastes), as appropriate for the type of
reactor.
a. The applicant submits, as specified in § 50.4, an evaluation
of the potential for effects from long-term buildup on the
environment in the vicinity of the site of radioactive material,
with a radioactive half-life greater than one year, to be released;
and
b. The provisions of paragraph A.1 are met.
B. For radioactive material above background in gaseous
effluents the annual total quantity of radioactive material to be
released to the atmosphere by all light-water-cooled nuclear power
reactors at a site:
1. The calculated annual air dose due to gamma radiation at any
location near ground level which could be occupied by individuals
at or beyond the boundary of the site should not exceed 10
millirads; and
2. The calculated annual air dose due to beta radiation at any
location near ground level which could be occupied by individuals
at or beyond the boundary of the site should not exceed 20
millirads.
3. Notwithstanding the guidance in paragraphs B.1 and B.2, for a
particular site:
a. The Commission may specify, as guidance on design objectives,
a lower quantity of radioactive material above background in
gaseous effluents to be released to the atmosphere if it appears
that the use of the design objectives described in paragraphs B.1
and B.2 is likely to result in an annual dose to an individual in
an unrestricted area in excess of 5 millirems to the total body or
15 millirems to the skin; or
b. Design objectives based on a higher quantity of radioactive
material above background in gaseous effluents to be released to
the atmosphere than the quantity specified in paragraphs B.1 and
B.2 may be deemed to meet the requirements for keeping levels of
radioactive material in gaseous effluents as low as practicable if
the applicant provides reasonable assurance that the proposed
higher quantity will not result in annual doses to an individual in
an unrestricted area in excess of 5 millirems to the total body or
15 millirems to the skin.
C. For radioactive iodine and radioactive material in
particulate form above background released to the atmosphere:
1. The calculated annual total quantity of all radioactive
iodine and radioactive material in particulate form from all
light-water-cooled nuclear power reactors at a site should not
result in an annual dose or dose commitment to any organ of an
individual in an unrestricted area from all pathways of exposure in
excess of 15 millirems. In determining the dose or dose commitment
the portion thereof due to intake of radioactive material via the
food pathways may be evaluated at the locations where the food
pathways actually exist; and
2. The calculated annual total quantity of iodine-131 in gaseous
effluents should not exceed 1 curie for each light-water-cooled
nuclear power reactor at a site.
3. Notwithstanding the guidance in paragraphs C.1 and C.2 for a
particular site, if an applicant for a permit to construct a
light-water-cooled nuclear power reactor has proposed baseline
in-plant control measures 3 to reduce the possible sources of
radioactive iodine releases, and the calculated annual quantities
taking into account such control measures exceed the design
objective quantities set forth in paragraphs C.1 and C.2, the
requirements for design objectives for radioactive iodine and
radioactive material in particulate form in gaseous effluents may
be deemed to have been met provided the calculated annual total
quantity of all radioactive iodine and radioactive material in
particulate form that may be released in gaseous effluents does not
exceed four times the quantity calculated pursuant to paragraph
C.1.
3 Such in-plant control measures may include treatment of steam
generator blowdown tank exhaust, clean steam supplies for turbine
gland seals, condenser vacuum systems, containment purging exhaust
and ventilation exhaust systems and special design features to
reduce contaminated steam and liquid leakage from valves and other
sources such as sumps and tanks, as appropriate for the type of
reactor.
[40 FR 19442, May 5, 1975, as amended at 40 FR 40818, Sept. 4,
1975; 40 FR 58847, Dec. 19, 1975; 41 FR 16447, Apr. 19, 1976; 42 FR
20139, Apr. 18, 1977; 51 FR 40311, Nov. 6, 1986; 61 FR 39303, July
29, 1996; 72 FR 49507, Aug. 28, 2007]