Term
| State the purpose of the Code of Federal Regulations (CFRs) |
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Definition
| CFRs are the Rules and Regulations that have been adopted and enforced by the NRC. The NRCs authority was established by the Atomic Energy Act of 1954. |
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Term
| Explain the purpose of 10 CFR 19 |
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Definition
| Establishes the requirements for notices, instructions and reports by licensees and regulated entities to individuals working at the nuclear plants. Also establishes the rights and responsibilities of the NRC and individuals during interviews. |
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Term
| For 10 CFR 19: List the notices that are required to be posted |
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Definition
o The regulations in this part and in part 20 of this chapter;
o The license, license conditions, or documents incorporated into a license by reference, and amendments thereto;
o The operating procedures applicable to licensed activities;
o Any notice of violation involving radiological working conditions, proposed imposition of civil penalty, or order issued.
o The operating procedures applicable to the activities regulated by the NRC which are being conducted by the applicant or holder; and
o Any notice of violation, proposed imposition of civil penalty, or order issued under subpart B of part 2 of this chapter, and any response from the applicant or holder.
o If posting of a document is not practicable, the licensee or regulated entity may post a notice which describes the document and states where it may be examined.
o Prominently post NRC Form 3, "Notice to Employees," dated August 1997. Later versions of NRC Form 3 that supersede the August 1997 version shall replace the previously posted version within 30 days of receiving the revised NRC Form 3. |
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Term
| For 10 CFR 19: List the notifications and reports that are required to be given to individuals. |
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Definition
o Radiation exposure data for an individual, and the results of any measurements, analyses, and calculations of radioactive material deposited or retained in the body of an individual, shall be reported to the individual as specified in this section.
o Each licensee shall make dose information available to workers as shown in records. The licensee shall provide an annual report to each individual monitored of the dose received in that monitoring year if:
The individual’s occupational dose exceeds 1 mSv (100 mrem) TEDE or 1 mSv (100 mrem) to any individual organ or tissue; or
The individual requests his or her annual dose report.
o At the request of a worker formerly engaged in licensed activities controlled by the licensee, each licensee shall furnish to the worker a report of the worker's exposure to radiation and/or to radioactive material.
o At the request of a worker who is terminating employment with the licensee that involved exposure to radiation or radioactive materials, during the current calendar quarter or the current year, each licensee shall provide at termination to each worker, or to the worker's designee, a written report regarding the radiation dose received by that worker from operations of the licensee during the current year or fraction thereof. If the most recent individual monitoring results are not available at that time, a written estimate of the dose must be provided together with a clear indication that this is an estimate. |
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Term
| Explain the purpose of 10 CFR 20. |
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Definition
| Standards for Protection Against Radiation. The regulations in this part establish standards for protection against ionizing radiation resulting from activities conducted under licenses issued by the Nuclear Regulatory Commission. |
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Term
| For 10 CFR 20: Explain the terms listed in section 20.1003. Special nuclear material means: |
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Definition
Plutonium, uranium-233, uranium enriched in the isotope 233 or in the isotope 235, and any other material that the Commission, pursuant to the provisions of section 51 of the Act, determines to be special nuclear material, but does not include source material; or
Any material artificially enriched by any of the foregoing but does not include source material. |
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Term
| For 10 CFR 20: Explain the Units of Radiation Dose listed in section 20.1004. |
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Definition
o Gray (Gy) is the SI unit of absorbed dose. One gray is equal to an absorbed dose of 1 Joule/kilogram (100 rads).
o Rad is the special unit of absorbed dose. One rad is equal to an absorbed dose of 100 ergs/gram or 0.01 joule/kilogram (0.01 gray).
o Rem is 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 (1 rem=0.01 sievert).
o Sievert is the SI unit of any of the quantities expressed as dose equivalent. The dose equivalent in sieverts is equal to the absorbed dose in grays multiplied by the quality factor (1 Sv=100 rems). |
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Term
| For 10 CFR 20: Explain the radiation standards for Restricted Areas |
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Definition
5 mR/hr – Radiation Area
100 mR/hr – High Radiation Area
1,000 mR/hr – Locked High Radiation Area
500,000 mR/hr – Very High Radiation Area |
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Term
| For 10 CFR 20: Explain the radiation standards for Airborne Exposure |
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Definition
When it is not practical to apply process or other engineering controls to control the concentrations of radioactive material in the air to values below those that define an airborne radioactivity area, the licensee shall, consistent with maintaining the total effective dose equivalent ALARA, increase monitoring and limit intakes by one or more of the following means--
• Control of access;
• Limitation of exposure times;
• Use of respiratory protection equipment; or
• Other controls.
If the licensee performs an ALARA analysis to determine whether or not respirators should be used, the licensee may consider safety factors other than radiological factors. The licensee should also consider the impact of respirator use on workers' industrial health and safety. |
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Term
| For 10 CFR 20: Explain the radiation standards for Minors |
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Definition
| Allowed to receive 10% of the dose specified for an adult |
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Term
| For 10 CFR 20: Explain the radiation standards for Unrestricted Areas |
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Definition
An area, access to which is neither limited nor controlled by the licensee.
Required to be posted at 2mR/hr |
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Term
| For 10 CFR 20: Explain the personnel monitoring requirements. |
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Definition
o Each licensee shall monitor occupational exposure to radiation from licensed and unlicensed radiation sources under the control of the licensee and shall supply and require the use of individual monitoring devices by--
Adults likely to receive, in 1 year from sources external to the body, a dose in excess of 10 percent of the annual limit.
Minors likely to receive, in 1 year, from radiation sources external to the body, a deep dose equivalent in excess of 0.1 rem (1 mSv), a lens dose equivalent in excess of 0.15 rem (1.5 mSv), or a shallow dose equivalent to the skin or to the extremities in excess of 0.5 rem (5 mSv);
Declared pregnant women likely to receive during the entire pregnancy, from radiation sources external to the body, a deep dose equivalent in excess of 0.1 rem (1 mSv)
Individuals entering a high or very high radiation area. |
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Term
| For 10 CFR 20: List the events that require notifying the NRC immediately. |
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Definition
o Immediately after its occurrence becomes known to the licensee, any lost, stolen, or missing licensed material in an aggregate quantity equal to or greater than 1,000 times the quantity specified in appendix C to part 20 under such circumstances that it appears to the licensee that an exposure could result to persons in unrestricted areas.
o Immediate notification. Notwithstanding any other requirements for notification, each licensee shall immediately report any event involving byproduct, source, or special nuclear material possessed by the licensee that may have caused or threatens to cause any of the following conditions--
An individual to receive--
• A total effective dose equivalent of 25 rems (0.25 Sv) or more; or
• (ii) A lens dose equivalent of 75 rems (0.75 Sv) or more; or
• (iii) A shallow-dose equivalent to the skin or extremities of 250 rads (2.5 Gy) or more; or
o The release of radioactive material, inside or outside of a restricted area, so that, had an individual been present for 24 hours, the individual could have received an intake five times the annual limit on intake (the provisions of this paragraph do not apply to locations where personnel are not normally stationed during routine operations, such as hot-cells or process enclosures). |
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Term
| Explain the purpose of 10 CFR 50. |
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Definition
| The regulations in this part are promulgated by the Nuclear Regulatory Commission to provide for the licensing of production and utilization facilities. This part also gives notice to all persons who knowingly provide to any licensee, applicant, contractor, or subcontractor, components, equipment, materials, or other goods or services, that relate to a licensee's or applicant's activities subject to this part, that they may be individually subject to NRC enforcement action. |
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Term
| For 10 CFR 50: Explain the criteria for Technical Specifications. Safety limits, limiting safety system settings, and limiting control settings. (ii)(A) |
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Definition
| Safety limits for nuclear reactors are limits upon important process variables that are found to be necessary to reasonably protect the integrity of certain of the physical barriers that guard against the uncontrolled release of radioactivity. If any safety limit is exceeded, the reactor must be shut down. The licensee shall notify the Commission, review the matter, and record the results of the review, including the cause of the condition and the basis for corrective action taken to preclude recurrence. Operation must not be resumed until authorized by the Commission |
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Term
| For 10 CFR 50: Explain the criteria for Technical Specifications. Limiting conditions for operation. |
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Definition
A technical specification limiting condition for operation of a nuclear reactor must be established for each item meeting one or more of the following criteria:
• Criterion 1. Installed instrumentation that is used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary.
• Criterion 2. A process variable, design feature, or operating restriction that is an initial condition of a design basis accident or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.
• Criterion 3. A structure, system, or component that is part of the primary success path and which functions or actuates to mitigate a design basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.
• Criterion 4. A structure, system, or component which operating experience or probabilistic risk assessment has shown to be significant to public health and safety. |
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Term
| For 10 CFR 50: Explain the acceptance criteria for ECCS Systems. |
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Definition
o Peak cladding temperature. The calculated maximum fuel element cladding temperature shall not exceed 2200º F.
o Maximum cladding oxidation. The calculated total oxidation of the cladding shall nowhere exceed 0.17 times the total cladding thickness before oxidation.
o Maximum hydrogen generation. The calculated total amount of hydrogen generated from the chemical reaction of the cladding with water or steam shall not exceed 0.01 times the hypothetical amount that would be generated if all of the metal in the cladding cylinders surrounding the fuel, excluding the cladding surrounding the plenum volume, were to react.
o Coolable geometry. Calculated changes in core geometry shall be such that the core remains amenable to cooling.
o Long-term cooling. After any calculated successful initial operation of the ECCS, the calculated core temperature shall be maintained at an acceptably low value and decay heat shall be removed for the extended period of time required by the long-lived radioactivity remaining in the core. |
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Term
| For 10 CFR 50: Explain the criteria for Fire Protection. |
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Definition
o The objectives of the fire protection program are to--
Reasonably prevent these fires from occurring;
Rapidly detect, control, and extinguish those fires that do occur and that could result in a radiological hazard; and
Ensure that the risk of fire-induced radiological hazards to the public, environment and plant personnel is minimized. |
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Term
| For 10 CFR 50: Explain the minimum Control Room staffing requirements. |
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Definition
o For Monticello – Single Unit Operation
During Power Operation – 2 SRO and 2 RO per shift
During Shutdown – 1 SRO and 1 RO per shift |
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Term
| For 10 CFR 50: Explain the acceptance criteria for ATWS. |
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Definition
o Each boiling water reactor must have an alternate rod injection (ARI) system that is diverse (from the reactor trip system) from sensor output to the final actuation device.
o Each boiling water reactor must have a standby liquid control system (SLCS).
o Each boiling water reactor must have equipment to trip the reactor coolant recirculating pumps automatically under conditions indicative of an ATWS. |
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Term
| For 10 CFR 50: Explain the criteria for Station Blackout. |
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Definition
o The specified station blackout duration shall be based on the following factors:
• The redundancy of the onsite emergency ac power sources;
• The reliability of the onsite emergency ac power sources;
• The expected frequency of loss of offsite power; and
• The probable time needed to restore offsite power. |
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Term
| For 10 CFR 50: List the events that require notifying the NRC immediately. |
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Definition
o The licensee shall notify the NRC immediately after notification of the appropriate State or local agencies and not later than one hour after the time the licensee declares one of the Emergency Classes.
o Non-emergency events--(1) One-hour reports. If not reported as a declaration of an Emergency Class under paragraph (a) of this section, the licensee shall notify the NRC as soon as practical and in all cases within one hour of the occurrence of any deviation from the plant's Technical Specifications authorized pursuant to Sec. 50.54(x) of this part. |
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Term
| Explain the purpose of 10 CFR 55. |
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Definition
| Establish procedures and criteria for the issuance of licenses to operators and senior operators, provide for the terms and conditions upon which the Commission will issue or modify these licenses, and provide for the terms and conditions to maintain and renew these licenses. |
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Term
| For 10 CFR 55: Explain the licensee requirements if incapacitated due to a disability or illness. |
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Definition
| If, during the term of the license, the licensee develops a permanent physical or mental condition that causes the licensee to fail to meet the license requirements the facility licensee shall notify the Commission, within 30 days of learning of the diagnosis. |
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Term
| For 10 CFR 55: Explain the content of the written and operating exams. |
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Definition
| 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. |
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Term
| For 10 CFR 55: List the conditions required to maintain an active license. |
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Definition
o Neither the license nor any right under the license may be assigned or otherwise transferred.
o The license is limited to the facility for which it is issued.
o The license is limited to those controls of the facility specified in the license.
o The license is subject to, and the licensee shall observe, all applicable rules, regulations, and orders of the Commission.
o 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.
o The licensee shall notify the Commission within 30 days about a conviction for a felony.
o The licensee shall complete a requalification program.
o The licensee shall have a biennial medical examination.
o 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.
o Each licensee at power reactors shall participate in the drug and alcohol testing programs. |
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Term
| For 10 CFR 55: List the requalification requirements. |
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Definition
o Successfully complete a requalification program developed by the facility licensee that has been approved by the Commission. This program shall be conducted for a continuous period not to exceed 24 months in duration.
o Pass a comprehensive requalification written examination and an annual operating test. |
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Term
| Explain the purpose of 10 CFR 73. |
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Definition
| Established requirements for the protection of special nuclear material at fixed sites, in transit and of plants in which special nuclear material is used. |
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Term
| For 10 CFR 73: List the one-hour reporting requirements. |
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Definition
| Each licensee shall notify the NRC within one hour after discovery of the loss of any shipment of SNM or spent fuel, and within one hour after recovery of or accounting for such lost shipment. |
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Term
| Explain the purpose of 10 CFR 100. |
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Definition
| Established what is required to choose a site for a new nuclear facility. |
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Term
| For 10 CFR 100: Explain the criteria for determining Exclusion, Low Population Zone, and Population Center Distance. |
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Definition
o An exclusion area of such size that an individual located at any point on its boundary for two hours immediately following onset of the postulated fission product release would not receive a total radiation dose to the whole body in excess of 25 rem or a total radiation dose in excess of 300 rem to the thyroid from iodine exposure.
o A low population zone of such size that an individual located at any point on its outer boundary who is exposed to the radioactive cloud resulting from the postulated fission product release (during the entire period of its passage) would not receive a total radiation dose to the whole body in excess of 25 rem or a total radiation dose in excess of 300 rem to the thyroid from iodine exposure.
o A population center distance of at least one and one-third times the distance from the reactor to the outer boundary of the low population zone. In applying this guide, the boundary of the population center shall be determined upon consideration of population distribution. Political boundaries are not controlling in the application of this guide. Where very large cities are involved, a greater distance may be necessary because of total integrated population dose consideration. |
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