Tech Specs

Question 1

Name sections of Tech Specs.

Answer 1

Use and application, Safety Limits, LCOs, Design Features, Admin Controls

Question 2

Define Use and Application sections

Answer 2

Explains how to use and interpret technical specifications, including definitions, logical connectors, completion time convention, and surveillance requirement frequencies.

Question 3

Define Safety Limits section.

Answer 3

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.

Question 4

Define LCO section.

Answer 4

The LCOs define the minimum equipment necessary to continue plant operation (based upon the Safety Analysis Report).

Question 5

Define Design Features section.

Answer 5

Design features address the site location, reactor core design, and fuel storage.

Question 6

Define Admin Controls section

Answer 6

Administrative controls defines the requirements for the site organization, procedure controls, and programs and corresponding controls.

Question 7

Define actions

Answer 7

That part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.

Question 8

Define allowable thermal power

Answer 8

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.

Question 9

Define axial power imbalance

Answer 9

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.

Question 10

Define APSRs

Answer 10

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

Question 11

Define channel calibration

Answer 11

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.

Question 12

Define channel check

Answer 12

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.

Question 13

Define core alteration

Answer 13

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.

Question 14

Define rated thermal power

Answer 14

A total steady state reactor core heat transfer rate to the reactor coolant of 2568 MWt.

Question 15

Define thermal power

Answer 15

The total reactor core heat transfer rate to the reactor coolant.

Question 16

Define operable/operability

Answer 16

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).

Question 17

Define identified leakage

Answer 17

Leakage from pump seals or valve packing (except RCP seal water or leakoff) injection that is captured and collected. Primary to secondary leakage.

Question 18

Define unidentified leakage

Answer 18

All LEAKAGE (except RCP seal water injection and leakoff) that is not Identified Leakage

Question 19

Define pressure boundary leakage

Answer 19

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.

Question 20

Define mode

Answer 20

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.

Question 21

Define dose equivalent XE-133

Answer 21

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.

Question 22

Define physics tests

Answer 22

Test performed to measure the fundamental nuclear characteristics of the core and related instrumentation.

Question 23

Define quadrant power tilt

Answer 23

QPT= 100 x ((Power in any quadrant / Avg power in all quadrants) - 1)

Question 24

Define Shutdown Margin

Answer 24

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

Question 25

Define mode 1

Answer 25

Power Operation, >= 0.99 Keff, >5% power, Tave = N/A

Question 26

Define mode 2

Answer 26

Startup, >= 0.99 Keff, <=5% power, Tave = N/A

Question 27

Define mode 3

Answer 27

Hot Standby, < 0.99 Keff, N/A power, Tave >= 280F

Question 28

Define mode 4

Answer 28

Hot Shutdown, < 0.99 Keff, N/A power, 280F > Tave > 200F

Question 29

Define mode 5

Answer 29

Cold Shutdown, < 0.99 Keff, N/A power, Tave <= 200F

All closure bolts fully tensioned

Question 30

Define mode 6

Answer 30

Refueling, N/A Keff, N/A power, Tave = N/A

1+ reactor vessel head closure bolts less than fully tensioned

Question 31

Define DNBR

Answer 31

Departure from Nucleate Boiling Ratio = Critical heat flux/Actual Head Flux

95% probability @ 95% confidence

Question 32

Completion time for subsequent inoperability on same system:

Answer 32

Add 24 hours from initial entry OR
Use stated completion time

Whichever is most restrictive

Question 33

RCS Leakage Tech Spec

Answer 33

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

Question 34

Reactor Core Safety Limits

Answer 34

2. 1.1.1 - max fuel pin centerline temp within spec
3. 1.1.2 - DNBR within spec
4. 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

Question 35

RCS Pressure Safety Limit

Answer 35

2.1.2 - RCS Press maintained <= 2750 psig

Modes 1-5

Question 36

Safety Limit Violations

Answer 36

2. 1.1.1 centerline temp - Mode 3 within 1 hour
3. 1.1.2 DNBR - Mode 3 within 1 hour
4. 1.1.3 Core outlet temp & press - restore within limits AND be in Mode 3 within 1 hour
5. 1.2 2750# - Modes 1 or 2 - Restore within limits AND Mode 3 in 1 hour
6. 1.2 Modes 3, 4, or 5 - restore press to <=2750# within 5 min

Notify NRC within 1 hour

Question 37

Define LCO 3.0.3

Answer 37

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

Question 38

Shutdown Margin Tech Spec with time

Answer 38

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)