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27 Cards in this Set
- Front
- Back
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Technical Specification Chapters |
1. Use and Application 2. Safety Limits 3. Limiting Conditions 4. Design Features 5. Administrative Controls |
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Parameters that Determine Mode |
1. Reactivity Coefficient (keff) 2. Rated Thermal Power (Excluding Decay Heat) 3. Average Reactor Coolant System Temperature |
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Mode 1 |
Power Operation Keff >= 0.99 % Rated Thermal Power > 5% Avg Reactor Coolant System Temperature N/A |
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Mode 2 |
Startup Keff >= 0.99 % Rated Thermal Power <= 5% Avg Reactor Coolant System Temperature N/A |
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Mode 3 |
Hot Standby Keff <0.99 % Rated Thermal Power N/A Average RCS Temperature >= 350F |
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Mode 4 |
Hot Shutdown Keff <= 0.99 % Rated Thermal Power N/A Avg RCS Temp is >200F, < 350F |
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Mode 5 |
Cold Shutdown Keff <= 0.99 % Rated Thermal Power N/A Avg RCS Temp is <= 200 (All Reactor Head Bolts are fully tensioned) |
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Mode 6 |
Refueling Keff, % Rated Thermal Power, Avg RCS is N/A
(Atleast one Reactor Head Bolts is NOT fully tensioned.)
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Safety Limits 2.1.1 |
2.1.1 Reactor Core SLs In MODES 1 & 2, the combination of THERMAL POWER, RCS highest loop average temperature, and pressurizer pressure shall not exceed the limits specified in the COLR, and the following SLs shall not be exceeded: --2.1.1.1 The Departure from nucleate boiling ratio(DNBR) shall be maintained >= 1.17 the WRB-1 DNB correlation. W-3 DNB correlation with a DNB correlation limit of >= 1.3 is used where the WRB-1 DNB correlation is not applicable.
--2.1.1.2 The peak fuel centerline temperature shall be maintained < 5080 F decreasing by 58F per 10,000 MWD/MTU of burnup. |
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Safety Limits 2.1.2 |
2.1.2 Reactor Coolant System Pressure SL
In MODES 1,2,3,4, and 5, The RCS pressure shall be mainainted <= 2735 psig |
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Safety Limits 2.2 |
SAFETY LIMIT VIOLATIONS
2.2.1 IF SL 2.1.1 is Violated, be in MODE3 within 1 hour
2.2.2 IF SL 2.1.2 is Violated: 2.2.2.1 In Mode 1 or 2, restore compliance and be in MODE 3 within 1 hour
2.2.2.2 in MODE 3,4, or 5 restore compliance within 5 minutes.
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Safety Limits Basis |
The reactor core SLs are established to preclude violation of the following fuel design criteria: 1. There must be at least 95% probability at a 95% confidence level (95/95 DNB criterion) that the hot fuel rod in the core does not experience DNB
2. There must be at least a 95% probability at a 95% confidence level that the hot fuel pellet in the core does not experience centerline fuel melting. |
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Limiting Condition for Operation |
The lowest functional capability for performance level of equipment required for safe operation of the facility. |
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LCO 3.0.1 |
LCO must be meet during mode of applicablilty
"LCOs shall be met during the MODES or other specified conditions in the Applicability, except as provided in LCO 3.0.2 and LCO 3.0.7" |
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LCO 3.0.2 |
Failure to meet the LCO, the actions of the condition must be met.
"Upon discovery of a failure to meet an LCO, the Required Actions of the associated Conditions shall be met, except as provided in LCO 3.0.5 and LCO 3.0.6.
If the LCO is met or is no longer applicable prior to expiration of the specified Completion Time (S), completion of the Required Action (s) is not required unless otherwise stated." |
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LCO 3.0.3 |
Actions not met or provided or directed then 1 hour preparation and 6 hours for mode 3.
"When an LCO is not met and the associated ACTIONS are not met, an associated ACTIONS is not provided, or if directed by the associated ACTIONS, the unit shall be placed in a MODE or other specified condition in which the LCO is not applicable. Action shall be initiated within 1 hour to place the unit as applicable, in a. MODE 3 within 7 hours b. MODE 4 within 13 hours; and c. MODE 5 within 37 hours Exceptions to this specification are stated in the individual Specifications.
Where corrective measures are completed that permit operation in accordance with the LCO or ACTIONS, completion of the actions required by LCO 3.0.3 is not required.
LCO 3.0.3 is only applicable in MODES 1,2,3,4" |
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LCO 3.0.4 |
LCO not met Mode Change allowed if Action allows continuous ops and Risk Assessment completed.
"When an LCO is not met, entry into a MODE or other specified condition in the Applicability shall only be made:
a. When the associated ACTIONS to be entered permit continued operation in the MODE or other specified conidition in the Applicability for an unlimited period of time;
b. After performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering the MODE or other specified condition in the Applicability, and establishment of risk management actions, if appropriate; exceptions to this specification are stated in the individual specifications, c. When an allowance is stated in the individual value, parameter or other specification.
This specification shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit." |
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LCO 3.0.5 |
Allows Testing under admin control
"Equipment removed from service or declared inoperable to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment. This is an exception to LCO 3.0.2 for the system returned to service under administrative control to perform the testing required to demonstrate operability" |
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LCO 3.0.6 |
Do not need to cascade unless loss of safety function.
"When a supported system LCO is not met solely due to a support system LCO not being met, the Conditions and Required Actions associated with this supported system are not required to be entered. Only the support system LCO actions are required to be entered. This is an exception to LCO 3.0.2 for the supported system. In this event, an evaluation shall be performed in accordance with Specification 5.5.13, "Safety Function Determination Program (SFDP)." If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered.
When a support system's Required Action directs a supported system to be declared inoperable or directs entry into Conditions and Required Actions for a supported system, the applicable Conditions and Required Actions shall be entered in accordance with LCO 3.0.2." |
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LCO 3.0.7 |
Physic Tests
"Test Exception LCO 3.1.8 "PHYSICS TESTS Exceptions - MODE 2" allows Technical specification (TS) Requirements to be changed to permit performance of special tests and operations. Unless otherwise specified, all other TS requirements remain unchanged. Compliance with Test Exception LCOs is optional. When a Test Exception LCO is desired to be met is not met, the ACTIONS of the Test Exception LCO shall be met. When a Test Exception LCO is not desired to be met, entry into a MODE or other specified condition in the Applicability shall be made in accordance with the other applicable Specifications." |
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SR 3.0.1 |
Surveillance requirements must be met
"SRs shall be met during the MODES or other specified conditions in the Applicability for individual LCOs, unless otherwise stated in the SR. Failure to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be failure to meet the LCO. Failure to perform a Surveillance within the specified Frequency shall be a failure to meet the LCO except as provided in SR 3.0.3. Surveillances do not have to be performed on inoperable equipment or variables outside specified limits. |
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SR 3.0.2 |
Grace 25%
"The specified Frequency for each SR is met if the Surveillance is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met. For Frequencies specified as "once", the above interval extension does not apply. If a completion TIme required periodic performance on a "once per ..." basis the above frequency extension applies to each performance after the initial performance.
Exceptions to this Specification are stated in the individual Specifications." |
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SR 3.0.3 |
Missed Surveillance Meet within 24 hours or Normal Surveillance Frequency. Which ever is greater.
"If it is discovered that a surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the LCO not met may be delayed, from the time of discovery, up to 24 hours or up to the limit of the specified frequency, whichever is greater. This delayed period is permitted to allow performance of the Surveillance. A risk evaluation shall be performed for any surveillance delayed greater than 24 hours and the risk impact shall be managed.
If the Surveillance is not performed within the delay period, the LCO must immediately be declared not me, and the applicable Condition (S) must be entered.
When the Surveillance is performed within the delay period and the Surveillance is not met, the LCO must immediately be declared not met and the applicable Conditions must be entered." |
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SR 3.0.4 |
LCO surveillances must be met before mode change.
"Entry into a MODE or other specified condition in the Applicability of an LCO shall only be made when the LCO's Surveillances have been met within their specified Frequency, except as provided by SR 3.0.3. When an LCO is not met due to Surveillances not having been met, entry into a MODE or other specified condition in the Applicability shall only be made in accordance with LCO 3.0.4.
This provision shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit."
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Section 5.1 |
Responsibility The plant manager shall be responsible for overal unit operation and shall delegate in writing the sucession to this responsibility during his absence. Plant Manager or designee shall approve, prior to implementation, each proposed test, experiment, or modification to systems or equipment that affects nuclear safety.
The shift manager shall be responsibile for the control room command function. Durring any absence of the shift manager from the control room complex while the unit is in MODE 1,2,3,4 an individual with an active Senior Operator License shall be designated to assume the control room command function. During any absence of the shift manager from the control room complex while the unit is in MODE 5 or 6, an individual with an active Senior Operator license or Operator license shall be designated to assume control room command function. |
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Section 5.2.1 |
Onsite and Offsite Organizations Onsite and offsite organizations shall be established for Unit Operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting the safety of the Nuclear Plant.
-Lines of authorities, documented in organizational charts. Titles and responsibilities delineated TS and UFSAR -Plant Manager shall be resonsible for overall safe operation of the plant. -Specified corporate officer shall have corporate responsibility to ensure accepetabl performance. -Operation trainers, RP or PA may report to a manager but must remain independant of operating pressures. |
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Section 5.2.2 |
The unit shall be staffed -Non licensed operator shall be assigned to each reactor containing fuel and an additional non-licensed operator shall be assigned for each control room from which a reactor is operating in MODES 1-4. -Shift crew may be less than 10CFR.54 for a period of 2 hours to accomodate unexpected absence. -RP tech shall be onsite when fuel is in the reactor. May not be vacated more than 2 hours. -Operations manager must hold or have held a SRO license at Cook or similar. Otherwise a line Operations manager shall hold license for directing operations activities. -Modes 1-4 must have an STA (requirements from the Commission Policy statement on engineering expertiese shift) |
