Tech Specs Flashcards
Name sections of Tech Specs.
Use and application, Safety Limits, LCOs, Design Features, Admin Controls
Define Use and Application sections
Explains how to use and interpret technical specifications, including definitions, logical connectors, completion time convention, and surveillance requirement frequencies.
Define Safety Limits section.
The safety limits protect the integrity of the fuel and RCS pressure boundary.
Ensure specified acceptable fuel design limits are not exceeded during steady state operation, normal operational transients, and abnormalities.
Define LCO section.
The LCOs define the minimum equipment necessary to continue plant operation (based upon the Safety Analysis Report).
Define Design Features section.
Design features address the site location, reactor core design, and fuel storage.
Define Admin Controls section
Administrative controls defines the requirements for the site organization, procedure controls, and programs and corresponding controls.
Define actions
That part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.
Define allowable thermal power
The maximum steady state reactor core heat transfer rate to the reactor coolant permitted by consideration of the number and configuration of reactor coolant pumps (RCPs) in operation.
Define axial power imbalance
The power in the top half of the core, expressed as a percentage of RATED THERMAL POWER (RTP), minus the power in the bottom half of the core, expressed as a percentage of RTP.
Define APSRs
The control components with part length absorbers used to control the axial power distribution of the reactor core. The APSRs are positioned manually by the operator and are not trippable
Define channel calibration
The adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors.
Define channel check
The qualitative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.
Define core alteration
The movement of any fuel, sources, or reactivity control components, within the reactor vessel with the vessel head removed and fuel in the vessel. Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.
Define rated thermal power
A total steady state reactor core heat transfer rate to the reactor coolant of 2568 MWt.
Define thermal power
The total reactor core heat transfer rate to the reactor coolant.
Define operable/operability
A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).
Define identified leakage
Leakage from pump seals or valve packing (except RCP seal water or leakoff) injection that is captured and collected. Primary to secondary leakage.
Define unidentified leakage
All LEAKAGE (except RCP seal water injection and leakoff) that is not Identified Leakage
Define pressure boundary leakage
Leakage (except primary to secondary leakage) through a fault in an RCS component body, pipe wall, or vessel wall. Leakage past seals, packing, and gaskets is not pressure boundary leakage.
Define mode
One inclusive combo of core reactivity condition, power level, average reactor coolant temperature, and reactor vessel head closure bolt tensioning with fuel in the reactor vessel.
Define dose equivalent XE-133
concentration of Xe-133 (microcuries per gram) that alone would produce the same acute dose to the whole body as the combined activities of noble gas nuclides Kr-85m, Kr-85, Kr-87, Kr-88, Xe-131m, Xe-133m, Xe-133, Xe-135m, Xe-135, and Xe-138 actually present.
Define physics tests
Test performed to measure the fundamental nuclear characteristics of the core and related instrumentation.
Define quadrant power tilt
QPT= 100 x ((Power in any quadrant / Avg power in all quadrants) - 1)
Define Shutdown Margin
The instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming:
All full-length control rods are fully inserted except for the single control rod of highest reactivity worth assumed to be fully withdrawn. With any control rod not capable of being fully inserted, the reactivity worth of these control rods must be accounted for in the determination of SDM
The instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming:
In MODES 1 and 2, the fuel and moderator temperatures are changed to the nominal zero power design level; and
There is no change in APSR position
Define mode 1
Power Operation, >= 0.99 Keff, >5% power, Tave = N/A
Define mode 2
Startup, >= 0.99 Keff, <=5% power, Tave = N/A
Define mode 3
Hot Standby, < 0.99 Keff, N/A power, Tave >= 280F
Define mode 4
Hot Shutdown, < 0.99 Keff, N/A power, 280F > Tave > 200F
Define mode 5
Cold Shutdown, < 0.99 Keff, N/A power, Tave <= 200F
All closure bolts fully tensioned
Define mode 6
Refueling, N/A Keff, N/A power, Tave = N/A
1+ reactor vessel head closure bolts less than fully tensioned
Define DNBR
Departure from Nucleate Boiling Ratio = Critical heat flux/Actual Head Flux
95% probability @ 95% confidence
Completion time for subsequent inoperability on same system:
Add 24 hours from initial entry OR
Use stated completion time
Whichever is most restrictive
RCS Leakage Tech Spec
Modes 1-4 No pressure boundary leakage 1 GPM unidentified leakage 10 gpm identified leakage 150 gal/day primary to secondary leakage thru any 1 SG
Reactor Core Safety Limits
- 1.1.1 - max fuel pin centerline temp within spec
- 1.1.2 - DNBR within spec
- 1.1.3 - RCS core outlet temp and press maintained above and to the left of the Variable Low RCS Press-Temp Protective Limits as specified in COLR
ALL in MODES 1 and 2
RCS Pressure Safety Limit
2.1.2 - RCS Press maintained <= 2750 psig
Modes 1-5
Safety Limit Violations
- 1.1.1 centerline temp - Mode 3 within 1 hour
- 1.1.2 DNBR - Mode 3 within 1 hour
- 1.1.3 Core outlet temp & press - restore within limits AND be in Mode 3 within 1 hour
- 1.2 2750# - Modes 1 or 2 - Restore within limits AND Mode 3 in 1 hour
- 1.2 Modes 3, 4, or 5 - restore press to <=2750# within 5 min
Notify NRC within 1 hour
Define LCO 3.0.3
LCO not met, ACTION not provided, or if directed by ACTIONS, then within initiate actions within 1 hour to place the unit in:
Mode 3 within 7 hours,
Mode 4 within 13 hours, and
Mode 5 within 37 hours.
Modes 1-4
Shutdown Margin Tech Spec with time
SDM within limit specified in the COLR
Modes 3, 4, 5
Condition: SDM not within limit.
Action: Initiate boration to restore to within limits (15 min)
