Source: http://www.nrc.gov/reading-rm/doc-collections/cfr/part055/full-text.html
Timestamp: 2013-06-19 22:44:35
Document Index: 552020665

Matched Legal Cases: ['art 55', '§ 55', 'art 50', 'art 52', 'art\n54', '§ 55', 'arts 50', '§ 55', 'art 50', '§ 55', '§ 55', 'art 50', 'art 52', 'art 50', 'art 52', 'art 50', '§ 55', '§ 55', '§ 55', '§ 55', '§ 55', '§ 55', '§ 55', '§ 55', '§ 55', '§ 55', '§ 55', '§ 55', '§ 55', '§ 55', '§ 55', '§ 55', '§ 55', '§ 55', '§ 55', '§ 55', '§ 55', '§ 55', '§ 55', '§ 55', '§ 55', '§ 55', '§ 55', '§ 55', '§ 55', '§ 55', '§ 55', '§ 55', '§ 55', '§ 55', '§ 55', '§ 55', '§ 55', '§ 55', '§ 55', '§ 55', 'art 26', 'art 26', '§ 55', '§ 55', '§ 55', '§ 55', '§ 55', '§ 55', '§ 55', '§ 55', '§ 55', '§ 55', '§ 55', '§ 55', '§ 55', '§ 55', '§ 55', '§ 55', '§ 55', '§ 55', 'art 55']

NRC: 10 CFR Part 55—Operators' Licenses
55.8 Information collection requirements: OMB approval.
Authority: Atomic Energy Act secs. 107, 161, 181, 182, 68 Stat. 939, 948, 953, 223, 234 (42 U.S.C. 2137, 2201, 2231,
2232, 2273, 2282); Energy Reorganization Act secs. 201, 202 (42 U.S.C. 5841, 5842); Government Paperwork Elimination Act sec. 1704 (44
U.S.C. 3504 note). Sections 55.41, 55.43, 55.45, and 55.59 also issued under Nuclear Waste Policy Act sec. 306 (42 U.S.C. 10226).
[77 FR 39907, Jul. 6, 2012]
§ 55.1 Purpose.
(a) Establish procedures and criteria
for the issuance of licenses to operators
and senior operators of utilization
facilities licensed under the Atomic
Energy Act of 1954, as amended, or
Section 202 of the Energy
Reorganization Act of 1974, as
amended, and part 50, part 52, or part
54 of this chapter,
§ 55.2 Scope.
The regulations in this part apply to --
(a) Any individual who manipulates
the controls of any utilization facility
licensed under parts 50, 52, or 54 of this
(b) Any individual designated by a facility licensee to be responsible for directing any licensed activity of a licensed
§ 55.3 License requirements.
A person must be authorized by a license issued by the Commission to perform the function of an operator or a senior
operator as defined in this part.
Actively performing the functions of an operator or senior operator means that an individual has a position on the shift
crew that requires the individual to be licensed as defined in the facility's technical specifications, and that the individual
carries out and is responsible for the duties covered by that position.
Controls when used with respect to a nuclear reactor means apparatus and mechanisms the manipulation of which directly
affects the reactivity or power level of the reactor.
Facility means any utilization facility as defined in part 50 of this chapter. In cases for which a license is issued for
operation of two or more facilities, facility means all facilities identified in the license.
Performance testing means testing conducted to verify a simulation facility's performance as compared to actual or
predicted reference plant performance.
Physician means an individual licensed by a State or territory of the United States, the District of Columbia or the
Commonwealth of Puerto Rico to dispense drugs in the practice of medicine.
Reference plant means the specific nuclear power plant from which a simulation facility's control room configuration,
system control arrangement, and design data are derived.
Senior operator means any individual licensed under this part to manipulate the controls of a facility and to direct the
licensed activities of licensed operators.
(2) A Commission-approved simulator under § 55.46(b); or
(3) Another simulation device, including part-task and limited scope simulation devices, approved under § 55.46(b).
(a) Except as provided under a regional licensing program identified in paragraph (b) of this section, an applicant or licensee or
facility licensee shall submit any communication or report concerning the regulations in this part and shall submit any application filed
under these regulations to the Commission as follows:
(1) By mail addressed to—Director, Office of Nuclear Reactor Regulation or Director, Office of New Reactors, as appropriate, U.S.
Nuclear Regulatory Commission, Washington, DC 20555–0001; or
(3) Where practicable, by electronic submission, for example, via Electronic Information Exchange, or CD-ROM. Electronic submissions
must be made in a manner that enables the NRC to receive, read, authenticate, distribute, and archive the submission, and process and
retrieve it a single page at a time. Detailed guidance on making electronic submissions can be obtained by visiting the NRC’s Web
site at http://www.nrc.gov/site-help/e-submittals.html; by e-mail to MSHD.Resource@nrc.gov; or by writing the Office of
Information Services, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001. The guidance discusses, among other topics, the
formats the NRC can accept, the use of electronic signatures, and the treatment of nonpublic information.
(b)(1) Except for test and research reactor facilities, the Director, Office of Nuclear Reactor Regulation or Director, Office of New
Reactors, as appropriate, has delegated to the Regional Administrators of Regions I, II, III, and IV authority and responsibility under
the regulations in this part for the issuance and renewal of licenses for
operators and senior operators of nuclear power reactors licensed under 10 CFR part 50 or part 52 of this chapter
and located in these regions.
(2) Any application for a license or license renewal filed under the regulations in this part involving a nuclear power reactor
licensed under 10 CFR part 50 or part 52 of this chapter and any related inquiry, communication, information, or report must be submitted
to the Regional Administrator by an appropriate method listed in paragraph (a) of this section. The Regional Administrator or the
Administrator’s designee will transmit to the Director, Office of New Reactors or Director, Office of Nuclear Reactor Regulation, as
appropriate, any matter that is not within the scope of the Regional Administrator's delegated authority.
(i) If the nuclear power reactor is located in Region I, submissions must be made to the Regional Administrator of Region I.
Submissions by mail or hand delivery must be addressed to the Administrator at U.S. Nuclear Regulatory Commission, 2100 Renaissance
Boulevard, Suite 100, King of Prussia, PA 19406–2713; where email is appropriate it should be addressed to RidsRgn1MailCenter.Resource@nrc.gov.
(ii) If the nuclear power reactor is located in Region II, submissions must be made to the Regional Administrator of Region II.
Submissions by mail or hand delivery must be addressed to the Regional Administrator at U.S. Nuclear Regulatory Commission, 245
Peachtree Center Avenue, NE., Suite 1200, Atlanta, Georgia 30303–1257. Where e-mail is appropriate, it should be addressed to
RidsRgn2MailCenter@nrc.gov.
(iii) If the nuclear power reactor is located in Region III, submissions must be made to the Regional Administrator of Region
III. Submissions by mail or hand delivery must be addressed to the Administrator at U.S. Nuclear Regulatory Commission, 2443
Warrenville Road, Suite 210, Lisle, IL 60532–4352; where e-mail is appropriate it should be addressed to RidsRgn3MailCenter@nrc.gov.
(iv) If the nuclear power reactor is located in Region IV, submissions must be made to the Regional Administrator of Region IV.
Submission by mail or hand delivery must be addressed to the Administrator at U.S. Nuclear Regulatory Commission, 1600 E. Lamar Blvd.,
Arlington, TX 76011–4511; where email is appropriate, it should be addressed to RidsRgn4MailCenter@nrc.gov.
(3)(i) Any application for a license or license renewal filed under the regulations in this part involving a test and research reactor
facility licensed under 10 CFR part 50 and any related inquiry, communication, information, or report must be submitted to the Office of
Nuclear Reactor Regulation, Division of Regulatory Improvement Programs at the NRC's headquarters, by an appropriate method listed in
(ii) For all test and research reactor facilities located in the NRC's Regions, submissions must be made to the Office of Nuclear
Reactor Regulation, Director of the Division of Regulatory Improvement Programs at the NRC's headquarters, by an appropriate method listed
[52 FR 9460, Mar. 25, 1987, as amended at 53 FR 6139, Mar. 1, 1988; 53 FR 43421, Oct. 27, 1988; 55 FR 41335, Oct. 11, 1990; 59 FR
17466, Apr. 13, 1994; 61 FR 9902, Mar. 12, 1996; 67 FR 77653, Dec. 19, 2002; 68 FR 58812, Oct. 10, 2003; 70 FR 69421, Nov. 16, 2005; 71 FR
15011, Mar. 27, 2006; 72 FR 33386, Jun. 18, 2007; 72 FR 49560, Aug. 28, 2007; 73 FR 5724, Jan. 31, 2008; 74 FR 62682, Dec. 1, 2009; 75 FR
21980, Apr. 27, 2010; 76 FR 72085, Nov. 22, 2011; 77 FR 39907, Jul. 6, 2012]
§ 55.6 Interpretations.
§ 55.7 Additional requirements.
The Commission may, by rule, regulation, or order, impose upon any licensee such requirements, in addition to those
established in the regulations in this part, as it deems appropriate or necessary to protect health and to minimize danger to
§ 55.8 Information collection requirements: OMB approval.
(a) The Nuclear Regulatory Commission has submitted the information collection requirements contained in this part to the Office of Management and Budget
(OMB) for approval as required by the Paperwork Reduction Act (44 U.S.C. 3501 et seq.). The NRC may not conduct or sponsor, and a person is not required
to respond to, a collection of information unless it displays a currently valid OMB control number. OMB has approved the information collection requirements
contained in this part under control number 3150-0018.
(b) The approved information collection requirements contained in this part appear in §§ 55.11, 55.25, 55.27, 55.31, 55.35, 55.40, 55.41, 55.43, 55.45, 55.47, 55.53, 55.57, and 55.59.
(c) This part contains information collection requirements in addition to those approved under the control number specified in paragraph (a) of this section.
These information collection requirements and the control numbers under which they are approved are as follows:
(1) In §§ 55.23, 55.25, 55.27, 55.31, NRC Form 396 is approved under control number 3150-0024.
(2) In §§ 55.31, 55.35, 55.47, and 55.57, NRC Form 398 is approved under control number 3150-0090.
(3) in § 55.45, NRC Form 474 is approved under control number 3150-0138.
(4) In §§ 55.41, 55.43, 55.45, and 55.59, clearance is approved under control number 3150-0101.
§ 55.9 Completeness and accuracy of information.
Information provided to the Commission by an applicant for a license or by a licensee or information required by statute or
by the Commission's regulations, orders, or license conditions to be maintained by the applicant or the licensee shall be
§ 55.11 Specific exemptions.
The Commission may, upon application by an interested person, or upon its own initiative, grant such exemptions from the
requirements of the regulations in this part as it determines are authorized by law and will not endanger life or property and
are otherwise in the public interest.
The regulations in this part do not require a license for an individual who --
(a) Under the direction and in the presence of a licensed operator or senior operator, manipulates the controls of --
(2) A facility as a part of the individual's training in a facility licensee's training program as approved by the Commission to
qualify for an operator license under this part.
(b) Under the direction and in the presence of a licensed senior operator, manipulates the controls of a facility to load or
unload the fuel into, out of, or within the reactor vessel.
Subpart C--Medical Requirements
§ 55.21 Medical examination.
An applicant for a license shall have a medical examination by a physician. A licensee shall have a medical examination by a physician every two years. The physician shall determine that the applicant or licensee meets the requirements of § 55.33(a)(1).
§ 55.23 Certification.
To certify the medical fitness of the applicant, an authorized representative of the facility licensee shall complete and sign NRC Form 396, "Certification of Medical Examination by Facility Licensee," which can be obtained by writing the Office of Information Services, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, by calling (301) 415-5877, or by visiting the NRC's Web site at http://www.nrc.gov and selecting forms from the index found on the home page.
(a) Form NRC-396 must certify that a physician has conducted the medical examination of the applicant as required in § 55.21. (b) When the certification requests a conditional license based on medical evidence, the medical evidence must be submitted on NRC Form 396 to the Commission and the Commission then makes a determination in accordance with § 55.33.
[52 FR 9460, Mar. 25, 1987, as amended at 53 FR 43421, Oct. 27, 1988; 68 FR 58813, Oct. 10, 2003; 70 FR 69421, Nov. 16, 2005]
§ 55.25 Incapacitation because of disability or illness.
The facility licensee shall document and maintain the results of medical qualifications data, test results, and each operator's
or senior operator's medical history for the current license period and provide the documentation to the Commission upon
request. The facility licensee shall retain this documentation while an individual performs the functions of an operator or
Subpart D--Applications
(1) Complete NRC Form 398, "Personal Qualification Statement--Licensee," which can be obtained by writing the Office of Information Services, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, by calling (301) 415-5877, or by visiting the NRC's Web site at http://www.nrc.gov and selecting forms from the index found on the home page;
(3) Submit a written request from an authorized representative of the facility licensee by which the applicant will be
employed that the written examination and operating test be administered to the applicant;
(6) Provide certification by the facility licensee of medical condition and general health on Form NRC - 396, to comply
with §§ 55.21, 55.23 and 55.33(a)(1).
(b) The Commission may at any time after the application has been filed, and before the license has expired, require futher
information under oath or affirmation in order to enable it to determine whether to grant or deny the application or whether
to revoke, modify, or suspend the license.
(c) An applicant whose application has been denied because of a medical condition or general health may submit a further
medical report at any time as a supplement to the application.
(d) Each application and statement must contain complete and accurate disclosure as to all matters required to be disclosed.
The applicant shall sign statements required by paragraphs (a)(1) and (2) of this section.
[52 FR 9460, Mar. 25, 1987, as amended at 53 FR 43421, Oct. 27, 1988; 66 FR 52667, Oct. 17, 2001; 68 FR 58813, Oct. 10, 2003; 70 FR 69421, Nov. 16, 2005]
§ 55.33 Disposition of an initial application.
(a) Requirements for the approval of an initial application. The Commission will approve an initial application for a
license pursuant to the regulations in this part, if it finds that --
(1) Health. The applicants medical condition and general health will not adversely affect the performance of assigned
operator job duties or cause operational errors endangering public health and safety. The Commission will base its finding
upon the certification by the facility licensee as detailed in § 55.23.
(2) Written examination and operating test. The applicant has passed the requisite written examination and operating test in accordance with §§ 55.41 and 55.45 or 55.43 and 55.45. These examinations and tests determine whether the applicant for an operator's license has learned to operate a facility competently and safely, and additionally, in the case of a senior operator, whether the applicant has learned to direct the licensed activities of licensed operators competently and safely.
(b) Conditional license. If an applicant's general medical condition does not meet the minimum standards under § 55.33(a)(1) of this part, the Commission may approve the application and include conditions in the license to accommodate the medical defect. The Commission will consider the recommendations and supporting evidence of the facility licensee and of the examining physician (provided on Form NRC-396) in arriving at its decision.
§ 55.35 Re-applications.
(a) An applicant whose application for a license has been denied because of failure to pass the written examination or
operating test, or both, may file a new application two months after the date of denial. The application must be submitted
on Form NRC-398 and include a statement signed by an authorized representative of the facility licensee by whom the
applicant will be employed that states in detail the extent of the applicant's additional training since the denial and certifies
that the applicant is ready for re-examination. An applicant may file a third application six months after the date of denial
of the second application, and may file further successive applications two years after the date of denial of each prior
application. The applicant shall submit each successive application on Form NRC-398 and include a statement of
(b) An applicant who has passed either the written examination or operating test and failed the other may request in a new
application on Form NRC-398 to be excused from re-examination on the portions of the examination or test which the
applicant has passed. The Commission may in its discretion grant the request, if it determines that sufficient justification is
Subpart E--Written Examinations and Operating Tests
§ 55.40 Implementation.
(a) The Commission shall use the criteria in NUREG-1021, "Operator Licensing Examination Standards for Power Reactors,"1 in effect six months before the examination date to prepare the written examinations required by §§ 55.41 and 55.43 and the operating tests required by § 55.45. The Commission shall also use the criteria in NUREG-1021 to evaluate the written examinations and operating tests prepared by power reactor facility licensees pursuant to paragraph (b) of this section.
(b) Power reactor facility licensees may prepare, proctor, and grade the written examinations required by §§ 55.41 and 55.43 and may prepare the operating tests required by § 55.45, subject to the following conditions:
(1) Power reactor facility licensees shall prepare the required examinations and tests in accordance with the criteria in NUREG-1021 as described in paragraph
(2) Pursuant to § 55.49, power reactor facility licensees shall establish, implement, and maintain procedures to control examination security and integrity;
(3) An authorized representative of the power reactor facility licensee shall approve the required examinations and tests before they are submitted to the
Commission for review and approval; and
(c) In lieu of paragraph (b) of this section and upon written request from a power reactor facility licensee pursuant to § 55.31(a)(3), the Commission shall, for that facility licensee, prepare, proctor, and grade, the written examinations required by §§ 55.41 and 55.43 and the operating tests required by § 55.45. In addition, the Commission may exercise its discretion and reject a power reactor facility licensee's determination to elect paragraph (b) of this section, in which case the Commission shall prepare, proctor, and grade the required written examinations and operating tests for that facility licensee.
(d) The Commission shall prepare, proctor, and grade the written examinations required by §§ 55.41 and 55.43 and the operating tests required by § 55.45 for non-power reactor facility licensees.
[64 FR 19878, Apr. 23, 1999 as amended at 69 FR 76600, December 22, 2004]
1. Copies of NUREGs may be purchased from the Superintendent of Documents, U.S. Government Printing Office, P.O. Box 38082, Washington, DC
20402-9328. Copies are also available from the National Technical Information Service, 5285 Port Royal Road, Springfield, VA 22161. A copy is available for
inspection and/or copying in the NRC Public Document Room, One White Flint North, 11555 Rockville Pike (0-1F23), Rockville, MD.
(a) Content. The written examination for an operator will contain a representative selection of questions on the knowledge,
skills, and abilities needed to perform licensed operator duties. The knowledge, skills, and abilities will be identified, in
part, from learning objectives derived from a systematic analysis of licensed operator duties performed by each facility
licensee and contained in its training program and from information in the Final Safety Analysis Report, system description
manuals and operating procedures, facility license and license amendments, Licensee Event Reports, and other materials
requested from the facility licensee by the Commission.
(b) The written examination for an operator for a facility will include a representative sample from among the following 14
items, to the extent applicable to the facility.
(1) Fundamentals of reactor theory, including fission process, neutron multiplication, source effects, control rod effects,
criticality indications, reactivity coefficients, and poison effects.
(2) General design features of the core, including core structure, fuel elements, control rods, core instrumentation, and
(5) Facility operating characteristics during steady state and transient conditions, including coolant chemistry, causes and
effects of temperature, pressure and reactivity changes, effects of load changes, and operating limitations and reasons for
these operating characteristics.
(7) Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure
modes, and automatic and manual features.
(a) Content. The written examination for a senior operator will contain a representative selection of questions on the
knowledge, skills, and abilities needed to perform licensed senior operator duties. The knowledge, skills, and abilities will
be identified, in part, from learning objectives derived from a systematic analysis of licensed senior operator duties
performed by each facility licensee and contained in its training program and from information in the Final Safety Analysis
Report, system description manuals and operating procedures, facility license and license amendments, Licensee Event
Reports, and other materials requested from the facility licensee by the Commission.
(4) Radiation hazards that may arise during normal and abnormal situations, including maintenance activities and various
contamination conditions.
(5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency
(6) Procedures and limitations involved in initial core loading, alterations in core configuration, control rod programming,
and determination of various internal and external effects on core reactivity.
(a) Content. The operating tests administered to applicants for operator and senior operator licenses in accordance with
paragraph (b)(1) of this section are generally similar in scope. The content will be identified, in part, from learning
objectives derived from a systematic analysis of licensed operator or senior operator duties performed by each facility
requested from the facility licensee by the Commission. The operating test, to the extent applicable, requires the applicant
to demonstrate an understanding of and the ability to perform the actions necessary to accomplish a representative sample
from among the following 13 items.
(1) Perform pre-startup procedures for the facility, including operating of those controls associated with plant equipment
that could affect reactivity.
(6) Perform control manipulations required to obtain desired operating results during normal, abnormal, and emergency
(7) Safely operate the facility's heat removal systems, including primary coolant, emergency coolant, and decay heat
removal systems, and identify the relations of the proper operation of these systems to the operation of the facility.
(8) Safely operate the facility's auxiliary and emergency systems, including operation of those controls associated with
plant equipment that could affect reactivity or the release of radioactive materials to the environment.
(9) Demonstrate or describe the use and function of the facility's radiation monitoring systems, including fixed radiation
monitors and alarms, portable survey instruments, and personnel monitoring equipment.
(10) Demonstrate knowledge of significant radiation hazards, including permissible levels in excess of those authorized,
and ability to perform other procedures to reduce excessive levels of radiation and to guard against personnel exposure.
(11) Demonstrate knowledge of the emergency plan for the facility, including, as appropriate, the operator's or senior
operator's responsibility to decide whether the plan should be executed and the duties under the plan assigned.
(12) Demonstrate the knowledge and ability as appropriate to the assigned position to assume the responsibilities associated
with the safe operation of the facility.
(13) Demonstrate the applicant's ability to function within the control room team as appropriate to the assigned position, in
such a way that the facility licensee's procedures are adhered to and that the limitations in its license and amendments are
(b) Implementation--Administration. The operating test will be administered in a plant walkthrough and in either--
(1) A simulation facility that the Commission has approved for use after application has been made by the facility licensee under § 55.46(b);
§ 55.46 Simulation facilities.
§ 55.47 Waiver of examination and test requirements.
(a) On application, the Commission may waive any or all of the requirements for a written examination and operating test,
if it finds that the applicant --
(1) Has had extensive actual operating experience at a comparable facility, as determined by the Commission, within two
years before the date of application;
(3) Has learned the operating procedures for and is qualified to operate competently and safely the facility designated in the
(b) The Commission may accept as proof of the applicant's past performance a certification of an authorized representative
of the facility licensee or of a holder of an authorization by which the applicant was previously employed. The certification
must contain a description of the applicant's operating experience, including an approximate number of hours the applicant
operated the controls of the facility, the duties performed, and the extent of the applicant's responsibility.
(c) The Commission may accept as proof of the applicant's current qualifications a certification of an authorized
representative of the facility licensee or of a holder of an authorization where the applicant's services will be utilized.
§ 55.49 Integrity of examinations and tests.
Applicants, licensees, and facility licensees shall not engage in any activity that compromises the integrity of any application, test, or examination required by
this part. The integrity of a test or examination is considered compromised if any activity, regardless of intent, affected, or, but for detection, would have
affected the equitable and consistent administration of the test or examination. This includes activities related to the preparation and certification of license
applications and all activities related to the preparation, administration, and grading of the tests and examinations required by this part.
Subpart F--Licenses
§ 55.51 Issuance of licenses.
Operator and senior operator licenses. If the Commission determines that an applicant for an operator license or a senior
operator license meets the requirements of the Act and its regulations, it will issue a license in the form and containing any
conditions and limitations it considers appropriate and necessary.
§ 55.53 Conditions of licenses.
(e) If a licensee has not been actively performing the functions of an operator or senior operator, the licensee may not
resume activities authorized by a license issued under this part except as permitted by paragraph (f) of this section. To
maintain active status, the licensee shall actively perform the functions of an operator or senior operator on a minimum of
seven 8-hour or five 12-hour shifts per calendar quarter. For test and research reactors, the licensee shall actively perform
the functions of an operator or senior operator for a minimum of four hours per calendar quarter.
(f) If paragraph (e) of this section is not met, before resumption of functions authorized by a license issued under this part,
an authorized representative of the facility licensee shall certify the following:
(2) That the licensee has completed a minimum of 40 hours of shift functions under the direction of an operator or senior
operator as appropriate and in the position to which the individual will be assigned. The 40 hours must have included a
complete tour of the plant and all required shift turnover procedures. For senior operators limited to fuel handling under
paragraph (c) of this section, one shift must have been completed. For test and research reactors, a minimum of six hours
must have been completed.
(h) The licensee shall complete a requalification program as described by § 55.59.
(j) The licensee shall not consume or ingest alcoholic beverages within the protected area of power reactors, or the
controlled access area of non-power reactors. The licensee shall not use, possess, or sell any illegal drugs. The licensee
shall not perform activities authorized by a license issued under this part while under the influence of alcohol or any
prescription, over-the-counter, or illegal substance that could adversely affect his or her ability to safely and competently
perform his or her licensed duties. For the purpose of this paragraph, with respect to alcoholic beverages and drugs, the
term "under the influence" means the licensee exceeded, as evidenced by a confirmed positive test, the lower of the cutoff
levels for drugs or alcohol contained in 10 CFR part 26, appendix A, of this chapter, or as established by the facility
licensee. The term "under the influence" also means the licensee could be mentally or physically impaired as a result of
substance use including prescription and over-the-counter drugs, as determined under the provisions, policies, and
procedures established by the facility licensee for its fitness-for-duty program, in such a manner as to adversely affect his or
her ability to safely and competently perform licensed duties.
(k) Each licensee at power reactors shall participate in the drug and alcohol testing programs established pursuant to 10
CFR part 26. Each licensee at non-power reactors shall participate in any drug and alcohol testing program that may be
established for that non-power facility.
(l) The licensee shall comply with any other conditions that the Commission may impose to protect health or to minimize
§ 55.55 Expiration.
(a) Each operator license and senior operator license expires six years after the date of issuance, upon termination of
employment with the facility licensee, or upon determination by the facility licensee that the licensed individual no longer
needs to maintain a license.
(b) If a licensee files an application for renewal or an upgrade of an existing license on Form NRC-398 at least 30 days
before the expiration of the existing license, it does not expire until disposition of the application for renewal or for an
upgraded license has been finally determined by the Commission. Filing by mail or telegram will be deemed to be complete
at the time the application is deposited in the mail or with a telegraph company.
§ 55.57 Renewal of licenses.
(a) The applicant for renewal of a license shall --
(2) File an original of NRC Form 398 with the appropriate Regional Administrator specified in § 55.5(b).
(3) Provide written evidence of the applicant's experience under the existing license and the approximate number of hours
that the licensee has operated the facility.
(4) Provide a statement by an authorized representative of the facility licensee that during the effective term of the current
license the applicant has satisfactorily completed the requalification program for the facility for which operator or senior
operator license renewal is sought.
(5) Provide evidence that the applicant has discharged the license responsibilities competently and safely. The Commission
may accept as evidence of the applicant's having met this requirement a certificate of an authorized representative of the
facility licensee or holder of an authorization by which the licensee has been employed.
(6) Provide certification by the facility licensee of medical condition and general health on Form NRC-396, to comply with §§ 55.21, 55.23 and 55.27.
(b) The license will be renewed if the Commission finds that --
(1) The medical condition and the general health of the licensee continue to be such as not to cause operational errors that endanger public health and safety. The Commission will base this finding upon the certification by the facility licensee as described in § 55.23.
(2) The licensee --
(ii) Has successfully completed a requalification program that has been approved by the Commission as required by § 55.59; and
(iii) Has passed the requalification examinations and annual operating tests as required by § 55.59.
(3) There is a continued need for a licensee to operate or for a senior operator to direct operators at the facility designated in
(4) The past performance of the licensee has been satisfactory to the Commission. In making its finding, the Commission
will include in its evaluation information such as notices of violations or letters of reprimand in the licensee's docket.
§ 55.59 Requalification.
(a) Requalification requirements. Each licensee shall —
(i) The written examination will sample the items specified in §§ 55.41 and 55.43 of this part, to the extent applicable to the facility, the licensee, and any limitation of the license under § 55.53(c) of this part.
(ii) The operating test will require the operator or senior operator to demonstrate an understanding of and the ability to perform the actions necessary to accomplish a comprehensive sample of items specified in § 55.45(a) (2) through (13) inclusive to the extent applicable to the facility.
(3) On-the-job training. The requalification program must include on-the-job training so that —
(G) Loss of coolant, including —
(3) Large and small, including lead-rate determination
(v) A simulator may be used in meeting the requirements of paragraphs (c) (3)(i) and (3)(ii) of this section, if it reproduces the general operating characteristics of the facility involved and the arrangement of the instrumentation and controls of the simulator is similar to that of the facility involved. If the simulator or simulation device is used to administer operating tests for a facility, as provided in § 55.45 (b)(1), the device approved to meet the requirements of § 55.45(b)(1) must be used for credit to be given for meeting the requirements of paragraphs (c)(3)(i) (G through AA) of this section.
(4) Evaluation. The requalification program must include —
(iv) Simulation of emergency or abnormal conditions that may be accomplished by using the control panel of the facility involved or by using a simulator. When the control panel of the facility is used for simulation, the actions taken or to be taken for the emergency or abnormal condition shall be discussed; actual manipulation of the plant controls is not required. If a simulator is used in meeting the requirements of paragraph (c)(4)(iii) of this section, it must accurately reproduce the operating characteristics of the facility involved and the arrangement of the instrumentation and controls of the simulator must closely parallel that of the facility involved. After the provisions of § 55.46 have been implemented at a facility, the Commission approved or plant-referenced simulator must be used to comply with this paragraph.
(iii) If there is a conflict between the Commission's regulations in this part, and any license condition, or other written Commission approval or authorization pertaining to the retention period for the same type of record, the retention period specified for these records by the regulations in this part apply unless the Commission, pursuant to § 55.11, grants a specific exemption from this record retention requirement.
(7) Applicability to research and test reactor facilities. To accommodate specialized modes of operation and differences in control, equipment, and operator skills and knowledge, the requalification program for each licensed operator and senior operator of a research reactor or test reactor facility must conform generally but need not be identical to the requalification program
outlined in paragraphs (c) (1) through (6) of this section. Significant deviations from the requirements of paragraphs (c) (1) through (6) of this section will be permitted only if supported by
written justification and approved by the Commission.
Subpart G--Modification and Revocation of Licenses
§ 55.61 Modification and revocation of licenses.
(a) The terms and conditions of all licenses are subject to amendment, revision, or modification by reason of rules,
regulations, or orders issued in accordance with the Act or any amendments thereto.
(2) Because of conditions revealed by the application or statement of fact or any report, record, inspection or other means
that would warrant the Commission to refuse to grant a license on an original application,
(3) For willful violation of, or failure to observe any of the terms and conditions of the Act, or the license, or of any rule,
regulation, or order of the Commission, or
(5) For the sale, use or possession of illegal drugs, or refusal to participate in the facility drug and alcohol testing program,
or a confirmed positive test for drugs, drug metabolites, or alcohol in violation of the conditions and cutoff levels
established by § 55.53(j) or the consumption of alcoholic beverages within the protected area of power reactors or the
controlled access area of non-power reactors, or a determination of unfitness for scheduled work as a result of the
§ 55.71 Violations.
(a) The Commission may obtain an injunction or other court order to prevent a violation of the provisions of --
(1) For violations of --
attempted violation of, or conspiracy of violate, any regulation issued under sections 161b, 161i, or 161o of the Act. For
purposes of section 223, all the regulations in part 55 are issued under one or more of sections 161b, 161i, or 161o, except