Systems Exam 1 - FSAR & 10CFR Flashcards

1
Q

Incorporation by reference

A

→documents referenced become the law, like the CFR is
→used to reduce size of CFR

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2
Q

10CFR19

A

Notices, Instructions and Reports to Workers; Inspections
→Licensee must keep radiation exposure record
→Prohibits employment discrimination by a licensee for going to NRC
→Workers must be trained in RP procedures

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3
Q

10CFR20

A

Standards for Protection Against Radiation
→establish industry standard to be ALARA
→exposure limits for workers and public

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4
Q

10CFR21

A

Reporting Defects and Non-Compliances
→notify NRC of failure to comply with Atomic Energy Act of 1954 or any rules and regulations that could be a substantial safety hazard or a defect in the construction or operation of a facility, its activities, or components

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5
Q

10CFR50

A

Domestic Licensing of Production and Utilization Facilities
→specifies the regulations that govern the licensing of nuclear facilities
→defines “controls” (anything that directly affects reactivity or power level of reactor)
→describes RCS pressure boundary
→controls special nuclear material
→source of 50.59 reviews

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6
Q

10CFR55

A

Operator Licensing
→procedures and criteria governing issuance and maintenance and renewal of licenses for operators
→license issued for term of 6 years
→submit renewal within 30 days of expiration
→medical exam req’d within 6 months of initial licensing and exam every 2 years
→physical/medical changes
→must stand certain number of watches
→licensed individual must notify NRC of felony convictions (30 days)
→staffing requirements

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7
Q

10CFR100

A

Reactor Site Criteria
→describes criteria which guide NRC in evaluation of suitability of proposed nuclear facilities
→defines Exclusion Area and Low Population Zone

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8
Q

FSAR and its approval methods

A

Describes facility and operation specific to plant.
→proves CPNPP meets the requirements of 10CFR50
→changes approved by Nuclear Licensing Manager and must be submitted to NRC every 18 months.

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9
Q

3 Reactor Site Criteria Considerations (10CFR100)

A
  1. Characteristics of reactor design and proposed operation.
  2. Population density and land use in the vicinity of the site.
  3. Physical characteristics of the site including geology, seismology, meteorology, and hydrology
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10
Q

For Control Room staffing, what mode is considered “operating”?

A

Mode 4 and higher

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11
Q

How many watches must be stood to maintain an Active Status?

A

seven 8-hour shifts per quarter or five 12-hour shifts per calendar quarter
(partial shifts don’t count)

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12
Q

Define a “Control” per 10CFR50

A

“Control” means any apparatus or mechanism that, if manipulated, directly affects the reactivity or power level of the reactor

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13
Q

Define RCS Pressure Boundary per 10CFR50

A

“Reactor Coolant System Pressure Boundary” is all pressure-containing components, such as pressure vessels, piping, pumps, and valves which are part of the reactor coolant system or are connected to the reactor coolant system, up to and including:

   1. The outermost containment isolation valve in system piping which penetrates the primary reactor containment, or
   2. The second of two valves normally closed during normal reactor operation in system piping which does not penetrate the primary reactor containment, or
   3. The reactor coolant system safety and relief valves
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