Tech Specs Flashcards

1
Q

State the Legal Document that describes the Required content of Tech Specs.

A
  • 10CFR50.36
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2
Q

List the 6 sections of the Tech Specs

A
Definitions
Safety limits and Limiting Safety System Setting
Limiting Conditions for Operation
Surveillance requirements
Design Features
Administrative Controls
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3
Q

Define Definitions per Tech Specs

A

o Certain key terms are specially defined to avoid misapplication of misinterpretation

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4
Q

Define Safety Limits and Limiting Safety System Setting Section of TS

A

Limits upon important plant parameters which protects the integrity of certain physical barriers which guard against the uncontrolled release of radioactivity

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5
Q

Define Surveillance Requirements Section of TS

A

Requirements relating to test, calibration or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the LOC’s will be met.

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6
Q

Define Design Features Section of TS

A

Those features of the facility such as materials of constructions and geometric arrangements, which if altered or modified, would have a significant effect on safety and are not covered in other sections.

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7
Q

Define Administrative Controls Section of TS

A

This section presents the provisions relating to organization and management, procedures, record keeping, review and audit, reporting.

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8
Q

Define Axial Flux Difference

A

The difference in normalized flux signals between the top and bottom halves of a two section
excore neutron detector

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9
Q

Define Containment Integrity

A

All penetrations required to be closed by an operable containment automatic isolation valve system, or
Closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed positions

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10
Q

Define Core Alteration

A

The movement of any fuel, sources, or reactivity control components within the reactor vessel with the vessel head removed and fuel in the vessel

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11
Q

Define Controlled Leakage

A

Shall be that seal water flow supplied to the RCP pump seals

T.S. Limit of 40 GPM

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12
Q

Define Identified Leakage

A

Leakage (except controlled leakage) into closed systems, such as pump seal or valve packing leaks that are captured and conducted to a sump or collecting tank,
T.S. limit of 10 GPM
Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of Leakage Detection Systems or not to be Pressure Boundary Leakage, or
RCS leakage through a SG to the secondary coolant system. T.S. Limit of 150 GPD

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13
Q

Define Operable – Operability

A

When a system, subsystem, train, component or device when it is capable of performing its specified safety function(s), and when all necessary attendant items that are required for the item to perform its specified safety functions(s) are also capable of performing their related support function(s)

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14
Q

Define Operational Mode

A

The MODE that corresponds to the combinations of core reactivity (Keff), power level, and average coolant temperature

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15
Q

Define Rated thermal Power

A

Total reactor core heat transfer to the RCS of 3648Mwt

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16
Q

Define Shutdown Margin

A

The Instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from it present condition assuming all full-length rod Cluster assemblies are fully inserted except for the single rod cluster of highest reactivity worth which is assumed to be fully withdrawn

17
Q

Define Unidentified leakage

A

All leakage which is not Identified Leakage or Controlled Leakage
T.S. limit 1 GPM

18
Q

Describe the relationship between a limiting safety system setting and the safety limits

A

A LSSS is specified for a parameter on which a safety limit has been placed to ensure that the automatic protective action will correct the abnormal situation before a safety limit is exceeded.
This is done to ensure that the core and RCS are prevented from exceeding their safety limits during normal operation and design basis anticipated operational occurrences and to assist ESFAS in mitigating the consequences of an accident.

19
Q

List and describe the two safety limits and the protection afforded by each. Describe the bases for each of those limits

A

Reactor Core Safety Limits (2.1.1)
Combination of Thermal Power, RCS highest Tave, and RZR Pressure shall not exceed limits of the COLR.
DNBR shall be kept greater than or equal to 1.14
Peak centerline Temp shall be less than 5080F
These prevent overheating of the fuel and cladding
If violated restore compliance and be in Mode 3 within 1 hour
Reactor Coolant System Safety Limits (2.1.2)
In modes 1 – 5 RCS pressure shall be kept less than 2735#
Protects the integrity of the RCS against over pressurization
If violated restore compliance and be in Mode 3 within 1 hour, or 5 min (Mode 3 to 5)

20
Q

Describe the relationship between a limiting condition for operation and safe operation of the facility

A

The lowest function capability or performance level of equipment for SAFE operation of the facility. When a LCO for operation of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the Tech Spec until the condition can be met.

21
Q

Describe what must be done if a limiting condition for operation cannot be met

A

Perform the applicable action statement

22
Q

Describe what must be done if the plant cannot meet the minimum requirements of an LCO action statement

A

When a LCO is not met, except as provided in
the associated ACTION requirements, within 1 hour action
shall be initiated to place the unit in a MODE in which the
specification does not apply by placing it, as applicable, in:
a. At least HOT STANDBY within the next 6 hrs,
b. At least HOT SHUTDOWN within the following 6 hrs, and
c. At least COLD SHUTDOWN within the subsequent 24 hrs

23
Q

State the functions of the surveillance requirements

A

Requirements relating to test, calibration or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the LOC’s will be met.

24
Q

State the general requirements of sections of sections 3.0.4 and 4.0.4

A

State the general requirements of sections of sections 3.0.4 and 4.0.4

3. 0.4: When an LCO is not met entry into a mode shall only be made if:
	1) the associated actions to be entered permit continued operation in the mode or other specified conition in the Applicability for an unlimited period of time.
	2) after performance of a risk assessment
	3) when an allowance is stated in the 
4. 0.4: Cannot enter new mode unless:
	- all LCO’s for that mode are met without reliance on provisions in the action requirements.
	- Apply T.S. 3.0.4 if surveillances can not be met
25
Q

State the general requirements of section 4.0.2 for surveillance performance intervals

A

Each Surveillance requirement shall be performed within the specified interval with a maximum allowable extension not to exceed 25% of the specified surveillance interval.

26
Q

Describe the purpose and use of the Tech Requirements Manual

A

SSTR manual is part of the UFSAR

Has part of the Tech specs that were removed for ease of change from cycle to cycle

27
Q

State the shift manning requirements for all modes per 6.2.2

A
SM 1 – all modes
SRO 1 – 1-4 only
RO 2 -1-4, 1, 5-6
NSO 2 1-4, 1 5-6
STA 1 1-4 only
28
Q

List the modes of operation

A

1) Power Operation ≥ .99 Keff > 5% power ≥ 350F
2) Start up ≥ .99 Keff ≤ 5% power ≥ 350F
3) Hot stand by < .99 Keff 0% power ≥350F
4) Hot Shutdown < .99 Keff 0% power 350 > Tave > 200
5) Cold Shutdown < .99 Keff 0% power ≤ 200F
6) Refueling ≤ .95 Keff 0% power ≤ 140F