ANS 3.2 Comp Side-By-Side 25.

81 Pages·2013·0.44 MB·English

ANS 3.2 Side-By Side Comparison
Proposed ANS 3.2 Wording 7/25/2012
Staff
American National Standard ANSI/ANS 3.2-2012
Comments/COLP Wording from ANS 3.2 1976 Wording from ANS 3.2 1982
Verification
Administrative Controls for the Operational Phase of Nuclear
power Plants
1. Scope, Applicability and Purpose
1.1 Scope and Applicability.
This standard provides requirements and recommendations for This Standard is intended to be consistent
managerial and administrative controls to ensure that activities with applicable criteria for quality
associated with operating a nuclear power plant are carried out assurance, including those given in Title
without undue risk to the health and safety of the public. 10, Code of Federal Regulations, Part 50,
"Licensing of Production and Utilization
This standard provides requirements for implementing Facilities," Appendix B. [1]1
managerial and administrative controls consistent with
requirements of 10 CFR 50, Appendix B [1].1
This standard is not specifically intended for application to test,
mobile, experimental reactors, nor reactors not subject to U.S.
Nuclear Regulatory Commission licensing. Although the standard
is based on USNRC requirements the approach is applicable with
modifications to reflect the regulatory requirements in the country
of application. Applicable sections of this standard may be used
in those cases for activities similar to those addressed herein.
1.2 Purpose.
This standard contains requirements for managerial and This Standard fully and completely
administrative controls for nuclear power plants during the describes the general requirements and
operational phase of plant life. This phase is generally considered guidelines of American National Standard
to commence prior to initial fuel loading at a time identified by the Quality Assurance Program Requirements
owner organization. Certain initial construction activities may for Nuclear Power Plants, N45.2-1971, [2]
extend past fuel loading and certain operational activities may as those requirements and guidelines
take place prior to fuel loading. The owner organization is apply during the operational phase of plant
expected to identify those activities that are included in these life.
overlapping time periods and are expected to specify whether the

1 Numbers in brackets refer to corresponding numbers in Sec. 4, “References.”
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activities are to be considered as operational or as construction
activities. This phase continues until the operating license is
withdrawn.
The managerial and administrative controls of this standard
promote safe, reliable and efficient plant operation. This standard
may be applied to other activities consistent with the degree to
which those activities affect plant reliability. In keeping with this
intent, the provisions in this standard may be applied to
operational activities other than those specified in the Scope,
consistent with the degree to which those activities affect these
functions, compliance with regulations specifying radiation dose
and contamination criteria, or plant reliability. Applicable portions
of this standard may also be used for activities at reactors
specifically excluded in the Scope.
This standard is intended to be implemented together with the
applicable elements of ASME NQA-1-2008 and the NQA-1a-2009
addenda [2]. ASME NQA-1 is the standard that provides the
appropriate Quality Assurance requirements for all phases. This
standard provides the managerial and administrative requirements
needed to assure safe operation of a facility.

2 Definitions 2. Definitions 2. Definitions
2.1 Glossary of Terms 2.2 Glossary or Term 2.2 Glossary of Terms

The terms defined in NQA-1 apply to this standard and are
not duplicated herein.

experiments: performance of those plant operations executed Experiments. Performance of those plant Experiments. Performance of those plant
under controlled conditions in order to establish characteristics or operational carried out under controlled operations carried out under controlled
values not previously known. conditions in ord., to establish conditions in order to establish
characteristics or values not previously
characteristics or values not previously
known.
known.
independent review: review completed by personnel not having Independent review. Review completed Independent review. Review completed by
direct responsibility or direct involvement in the work function by personnel not having direct personnel not having direct responsibility
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under review. responsibility for the work function under for the work function under review
review regardless of whether they operate regardless of whether they operate as a
part of an organizational unit or as
as a part of an organizational unit or as
individual staff members (see review).
individual staff members (see review ).
managerial and administrative controls: rules, orders, Administrative controls. Rules, order, Administrative controls •. Rules, order
instructions, procedures, policies, practices, and designations of instruction&, procedures, policies, instructions, procedures, policies,
authority and responsibility. practices and designations of authority and
practices and designations of authority
responsibility.
and responsibility.

owner organization: the organization, including the on-site Owner organization. The organization,
operating organization, that has overall legal, financial, and including the onsite operating
technical responsibility for the operation of one or more nuclear
organization, which has overall legal,
power facilities.
financial and technical responsibility for
the operation of one or more nuclear

power plants.
operating organization: the organization concerned with daily New Definition
operation, maintenance, and related technical services. This
organization may include personnel located off-site who provide
operational support.

shall, should and may: the word "shall" is used to denote a shall, should and may. The word “shall” is
requirement; the word "should" to denote a recommendation; and used to denote a requirement; the word,
the word "may," to denote permission neither a requirement nor a
“should” to denote a recommendation; and
recommendation.
the word “may” to denote permission,
neither a requirement nor a

recommendation.
3 Requirements
3.1 Organization 3. Owner Organization 3. Owner Organization
3.1.1 General 3.1 General 3.1 General
Managerial and administrative controls which comply with this NQA-l, Basic The owner organization shall establish an The owner organization shall establish an
standard shall be established. The controls shall be in effect at all Requirement 2. Ok. administrative controls and quality administrative control and quality
times during the operational phase. The controls shall require that assurance program which complies with
assurance program which complies with
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decisions are made at the proper level and with the necessary this Standard. The program shall be in this standard. The program shall be in
reviews. The organization responsible for establishing and effect at all times during the operational effect at all times during the operational
executing the administrative controls in accordance with this phase to assure that operational phase phase to assure that operational phase
standard may delegate any or all of the work to others, but shall activities are carried out without undue risk
activities are carried out without undue risk
retain overall responsibility. to the health and safety of the public. The
to the health and safety of the public. The
program shall require that decision
program shall require that decisions affecting safety made at the proper level of
affecting safety are made at the proper responsibility and with the necessary
level of responsibility and with the technical advice and review. The owner
necessary technical advice and review. organization may delegate to other
organizations the work of establishing and
The owner organization may delegate to
executing the administrative controls and
other organizations the work of
Quality assurance program or any part.
establishing and executing the
thereof, in accordance with this standard.
administrative controls and quality but shall retain responsibility there for.
assurance program or any part thereof, in
accordance with this Standard, but shall
retain responsibility therefore.
3.1.2 Assignment of Authority and Responsibility. 3.2 Assignment of Authority and 3.2 Assignment of Authority and
Responsibility Responsibility
Lines of authority, responsibility, and communication shall be NQA-1, Basic It is essential that all members of the It is essential that all members of the
established and defined for the corporate, plant operating, and Requirement 2. Ok. organization involved in operation of organization involved in operation of
support organizations. These relationships shall be documented nuclear power plants, including those at nuclear power plants, including those at
and updated, as appropriate, in the form of organizational charts, the highest management levels, recognize the highest management levels, recognize
functional descriptions of departmental responsibilities and the necessity that the plants be operated the necessity that the plants be operated
relationships and job descriptions for key personnel positions or in under a well formulated and detailed under a well formulated and detailed

equivalent forms of documentation. administrative controls and quality administrative control and quality
assurance program to assure safety and assurance program to ensure safety and
efficiency. Lines of authority, responsibility efficiency. Lines of authority responsibility
and communication shall be established and communication shall be established
from the highest management level and well defined from the highest
through intermediate levels to and management level through intermediate
including the onsite operating organization level, to and including all onsite operating
(including those offsite organizational units organization position with involvement in
assigned responsibility for procurement, activities affecting the safety of the nuclear
design and construction, quality power plant including those offsite
assurance, and technical support organizational positioning under assigned
activities). responsibility for procurement, design and
construction, quality assurance and
These relationships shall be documented technical support activities.
and updated, as appropriate, in the form of
organizational charts, functional These relationships shall be documented
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descriptions or departmental and Updated, as appropriate in the form of
responsibilities and relationships and job organizational chart, functional description
descriptions for key personnel positions or of departmental responsibilities and
in equivalent forms of documentation. The relationships and job description for key
owner organization shall specify in writing personnel positioned or in equivalent forms
the authority and responsibility assigned to of documentation.
individuals and organizations involved in
establishing, executing and measuring the
overall effectiveness of the administrative
controls and quality assurance program
required by this Standard. The persons or
organizations responsible for defining and
measuring the overall effectiveness of the
program shall be designated, shall be
sufficiently independent from cost and
scheduling considerations when opposed
to safety considerations, shall have direct
access to responsible management at a
level where appropriate action can be
accomplished, and shall report regularly
on the effectiveness of the program to the
plant manager and the cognizant offsite
management. Persons or organizations
performing functions or assuring that the
administrative controls and quality
assurance program is established and
implemented or of assuring that an activity
has been correctly performed shall have
sufficient authority and organizational
freedom to: identify quality problems;
initiate, recommend or provide solutions,
through designated channels; and verify
implementation of solutions.
The organizational structure and the
functional responsibility assignments shall
be such that: (1) Attainment of program
objectives is accomplished by those who
have been assigned responsibility for
performing work. This may include interim
examinations, checks, and inspections of
the work by the individual performing the
work. (2) Verification or conformance to
established program requirements is
accomplished by a qualified person who
does not have responsibility for performing
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or directly supervising the work. The
method and extent or such verification
shall be commensurate with the
importance of the activity to plant safety
and reliability. In structuring the
organization and assigning responsibility,
quality assurance should be recognized as
an interdisciplinary function involving many
organizational component and, therefore,
should not be regarded as the sole domain
of a single quality assurance group. For
example, it may be more appropriate for
nuclear engineers to perform reviews of
plant nuclear engineering activities rather
than quality assurance engineers because
of the special .competence required to
perform these reviews. Quality assurance
encompasses many functions and
activities and extends to various levels in
all participating organizations. From the
top executive to all workers whose
activities may influence quality.
3.1.3 Plant Operating Organization 3 .4. 1 General 3 .4. 1 General
3.1.3.1 General NQA-1, Basic A number of factors influence A number of factors influence
Requirement 2. Ok. management in its decision regarding the management in its decision regarding the
Management shall establish and periodically assess the adequacy of establishment of an onsite operating
establishment of an onsite operating
the plant operating organization and shall ensure that necessary organization. organization.
changes to the organization are made in a timely manner.

When establishing the plant operating organization, the owner NQA-1, Basic These include the owner organization's These include the owner organization's
organization should evaluate the physical size and complexity of the Requirement 2. Ok. established staffing policies, the physical established staffing policies, the physical
nuclear power plant, the number of units, the extent of assistance
size and complexity of the nuclear power size and complexity of the nuclear power
provided by technical support organizations, and the extent of plant, the number of units, the extent of plant, the number of units, the extent of
reliance on consultants and the availability of qualified personnel
assistance provided by offsite technical' assistance provided by offsite technical
from other sources.
support organizations, the extent of support organizations the extent of
reliance on consultants and the availability reliance on consultants and the availability
of qualified personnel (room other sources of qualified personnel from other sources
to assist in activities. such as initial to assist in activities such as initial startup
startup, refueling. maintenance or refueling, maintenance or modification
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modification work. work.
3.1.3.1.1 Requirements for the Plant Operating Organization 3. 4. 2 Requirements for the Onsite 3. 4. 2 Requirements for the Onsite
Operating Organization Operating Organization
The plant operating organization shall include one or more NQA-1, Basic The onsite operating organization shall The Onsite operating organization shall
individuals knowledgeable in the following fields: nuclear power plant Requirement 1. Ok. include one or more individuals include. At a minimum, one or more
operation; nuclear power plant mechanical systems; nuclear power knowledgeable in the following field. : individual knowledgeable in the following
plant electrical systems; instrumentation and control (electronic) nuclear power plant operation; nuclear fields: nuclear power plant operation:
systems; nuclear engineering; heat transfer, fluid flow and power plant mechanical, electrical and nuclear power plant mechanical systems;
thermodynamics; chemistry and radiochemistry; radiation protection; electronic systems; nuclear engineering nuclear power plant electrical and
risk assessment; and quality assurance. chemistry and radiochemistry; radiation electronic systems; nuclear engineering;
protection; and quality assurance. Initial heat transfer, fluid flow and
incumbents or replacements (or members thermodynamics; chemistry and
of the onsite operating organization and radiochemistry; radiation protection; and
offsite technical sup. port organizations quality assurance. Initial incumbents or
shall have appropriate experience; training replacements for members of the onsite
and retraining to assure that necessary operating organization shall have
competence is maintained in accordance appropriate experience, training and
with the provisions of American National retraining to assure that necessary
Standard for Selection and Training of competence is maintained in accordance
Nuclear Power Plant Personnel, NIS.1- with the provisions of American National
1971 Standard for Selection. Qualification
Personnel whose qualifications do not and Training of Personnel for Nuclear
meet those specified in NlS.l and who are Power Plants, ANS UAN & S.1-l981.
performing inspection. examination, and
testing activities during the operations
phase of the plant, including
preoperational and start-up testing, shall
be qualified to American National
Standard Qualifications of Inspection,
Examination and Testing Personnel for the
Construction Phase of Nuclear Power
Plants N45.2.6-1973 . except that the QA
experience cited for Levels I, II, and III
should be interpreted to mean actual
experience in carrying out the types of
inspection. examination. or testing a being
performed.
Staffing requirements for positions in the plant’s operating Staffing should be in The owner organization shall designate The owner organization shall designate
organization that are to be filled by personnel holding NRC alignment with 50.54. those positions in the onsite operating those positions in the onsite operating
operator and senior operator licenses are normally delineated in organization which shall be filled by organization which shall be filled by
the plant’s Safety Analysis Report. These positions shall be personnel holding NRC reactor operator personnel holding NRC reactor operator
specified. Requirements for the minimum number of personnel and senior reactor operator licenses. and senior reactor operator licenses.
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holding such licenses who are to be present at the plant under Requirements for the minimum number of Requirements for the minimum number of
various operating conditions and situations shall also be specified, personnel holding such licenses who shall personnel holding such licenses who shall
normally in the plant’s Technical Specifications. be present at the plant under various be present at the plant under various
operating conditions and situations shall operating conditions and situations shall
also be specified. also be specified.
3.1.3.1.2 Technical Support for the On-Duty Operating Staff 3.4.3 Technical Support of the Off-Duty
Operating Staff.
The shift staffing shall include, or have available for consultation,
individuals in technical areas that are related to the safe operation
The owner organization shall establish
of the facility. The technical areas include thermodynamics and
provisions for assuring that the shift
fluid flow, reactor engineering, systems engineering, transient and
organization includes, or has available for
accident analysis, instrumentation and controls, quality assurance,
radiation protection, and chemistry and radiochemistry. consultation, persons with professional
level expertise in technical areas that are
related to the safe operation of the plant.
The technical areas include, as a
minimum, thermodynamics/fluid flow,
reactor engineering, systems engineering
transient and accident analysis, radiation
protection, and chemistry radiochemistry.
These personnel shall be available (at the
station or on call and capable of
responding to the plant within two hours)
for the purpose of providing technical
advice to the shift supervisor on a 24-hour-
a-day basis. They may be part of the plant
organization or they may be part of the
offsite technical support for the plant staff,
except that an individual appropriately
Qualified in the first four areas listed above
shall be onsite and capable of responding
to the control room within ten minutes after
the start of an emergency.
3.1.4 Operating Organization Authorities and Responsibilities 5.2.1 Responsibilities and Authorities
Of Operating Personnel
Responsibilities and authorities of plant operating personnel and Essentially, equivalent The responsibilities and authorities of the See 5.2.1.2 below.
those persons assigned to provide immediate support for the plant to 1976 version, plant operating personnel shall be
operations personnel shall be delineated for both normal and
delineated. These shall include, as a
emergency conditions. The following requirements shall be
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established: Section 5.2.1. Ok. minimum:
(1) The reactor operator's Authority and
responsibility for shutting the reactor down
when he determines that the safety of the
reactor is in jeopardy or when operating
parameters exceed any of the reactor
protection safety system set points and
automatic shutdown does not occur.
(2) The responsibility to determine the
circumstances, analyze the cause, and
determine that operations can proceed
safely before the reactor is returned to
power after a trip or An unscheduled or
unexplained power reduction.
(3) The senior reactor operator's
responsibility to be present at the plant
and to provide direction for returning the
reactor to power following a trip or an
unscheduled or unexplained power
reduction.
(4) The responsibility to believe and
respond conservatively to instrument
indications unless they are proved to be
incorrect.
(5) The responsibility to adhere to the
plant's Technical Specifications.
(6) The responsibility to review routine
operating data to assure safe operation.
3.1.4.1 Plant Control Responsibilities 5.2.1 Responsibilities andAuthorities 5.2.1 Control of Plant Operations
or Operating Personnel
Responsibilities and authorities shall be established so that at all Essentially, (1) The reactor operator's Authority and Responsibilities and authorities of onsite
times it is clear which individuals have responsibility for directing equivalent to 1976 responsibility for shutting the reactor down operating personnel and those person!
the various plant operating and control room activities. In assigned to provide immediate support for
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addition, there shall be clear identification of the individual(s) version, Section when he determines that the safety of the the onsite operations personnel shall be
responsible for determining the circumstances, analyzing the 5.2.1(1) & (2). reactor is in jeopardy or when operating delineated for both normal and emergency
cause, and determining that operations may proceed safely after conditions. at minimum. These rules of
parameters exceed any of the reactor
an unexplained event or before the reactor is returned to power protection safety system set points and practice shall establish the following:
after a trip.
automatic shutdown does not occur.

(2) The responsibility to determine the
circumstances, analyze the cause, and
determine that operations can proceed
safely before the reactor is returned to
power after a trip or An unscheduled or
unexplained power reduction.
3.1.4.2 General Authorities and Responsibilities of Operating 5.2.1 Responsibilities and Authorities 5.2.1.2 General Authorities and
Personnel Of Operating Personnel responsibilities of Operating Personnel
The general authorities and responsibilities of operating personnel Essentially, equivalent The responsibilities and authorities of the Rules of practice shall clearly delineate the
shall be clearly delineated and shall include the following: to 1976 version, plant operating personnel shall be general authorities and responsibilities of
delineated. These shall include, as a operating personnel, including the
Section 5.2.1(1) & (2).
(1) the authority and responsibility of licensed personnel for minimum: following:
shutting down the reactor when it is determined that the safety of (1) The reactor operator's Authority and 1) The reactor operator's authority and

the reactor is in jeopardy or when operating parameters exceed responsibility for shutting the reactor down responsibility (or shutting down the reactor
any of the reactor protection system set points and automatic when he determines that the safety of the when be determines that; the safety of the
shutdown does not occur. reactor is in jeopardy or when operating reactor is in jeopardy or when operating
parameters exceed any of the reactor parameters exceed any of the reactor
(2) the responsibility to respond conservatively to instrument protection system set points and automatic protection system set points and automatic
indications unless they are determined to be incorrect. shutdown does not occur. shutdown does not occur.
(2) The responsibility to determine the (2) The responsibility to behave and
(3) the responsibility to adhere to plant procedures (see also circumstances, analyze the cause, and respond conservatively to instrument
Section 3.5.1). determine that operational can proceed indications unless they are proved to be
safely before the reactor is returned to incorrect
(4) the responsibility to adhere to the plant's License Conditions power after a trip or An unscheduled (3) The responsibility to adhere to the
and Technical Specifications. unexplained power reduction. plant's operational and emergency
(3) The senior reactor operator's procedures. (see also 5.2.21.)
(5) the responsibility to review routine operating data to ensure responsibility to be present at the plant (4) The responsibility to adhere to the
safe operation. and to provide direction for returning the plant's Technical Specification.
reactor to power following a trip or an (5) The responsibility to review routine
unscheduled or unexplained power operating data to assure safe operation.
reduction.
(4) The responsibility to believe and
respond conservatively to instrument
indications unless they are proved to be
incorrect.
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