Term
| Describe the purpose and implementation requirements of TS 5.1,"Responsibility". |
|
Definition
The plant manager shall be responsible for overall unit operation and shall
delegate in writing the succession to this responsibility during his absence.
The plant manager or his designee shall approve, prior to implementation, each
proposed test, experiment, or modification to systems or equipment that affects nuclear safety.
The shift supervisor shall be responsible for the control room command function.
During any absence of the shift supervisor from the control room complex while the unit is in MODE 1, 2, or 3, an individual with an active Senior Operator license shall be designated to assume the control room command function.
During any absence of the shift supervisor from the control room complex while the unit is in MODE 4 or 5, an individual with an active Senior Operator license or Operator license shall be designated to assume the control room command function. |
|
|
Term
| Describe the purpose and implementation requirements of TS 5.2,"Organization" |
|
Definition
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 safety of the nuclear power plant. |
|
|
Term
| TS 5.2.2 "Unit Staff" Requirements for Non-Licensed Operators: |
|
Definition
A 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, 2, or 3. |
|
|
Term
| TS 5.2.2 "Unit Staff" Requirements for radiation protection technicians: |
|
Definition
A radiation protection technician shall be on site when fuel is in the reactor.
The position may be vacant for not more than 2 hours, in order to provide
for unexpected absence, provided immediate action is taken to fill the
required position. |
|
|
Term
| TS 5.2.2 "Unit Staff" Requirements for Operations Manager License status: |
|
Definition
The operations manager shall hold a Senior Operator license or shall
formerly have held a Senior Operator license. If the operations manager
does not hold a Senior Operator license, another member of plant
management shall hold a Senior Operator license and shall be assigned to
the plant operations group on a long term basis (approximately 2 years).
This individual shall not be assigned to a rotating shift. |
|
|
Term
| TS 5.2.2 "Unit Staff" Requirements for Technical Assistance Personel (STAs): |
|
Definition
An individual shall provide advisory technical support to the unit operations
shift crew in the areas of thermal hydraulics, reactor engineering, and plant
analysis with regard to the safe operation of the unit. This individual shall
meet the qualifications specified by the Commission Policy Statement on
Engineering Expertise on Shift. |
|
|
Term
| Per TS 5.4 "Procedures", Written Procedures SHALL be established, implemented and maintained covering which activities? |
|
Definition
a. Procedures in Reg Guide 1.33
b. Emergency operating procedures
c. QA for effluent and environmental monitoring;
d. Fire Protection Program
e. All programs specified in TS 5.5. |
|
|
Term
| Explain the purpose and implementation of TS 5.5.1 Offsite Dose Calculation Manual (ODCM) |
|
Definition
The ODCM shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid
effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints, and in the conduct of the radiological environmental monitoring program.
The ODCM shall also contain the radioactive effluent controls and
radiological environmental monitoring activities |
|
|
Term
| Explain the purpose and implementation of TS 5.5.2 Primary Coolant Outside Containment Program |
|
Definition
This program provides controls to minimize leakage from those portions of
systems outside containment that could contain highly radioactive fluids during a serious transient or accident to levels as low as practicable. The systems include Core Spray, High Pressure Coolant Injection, Residual Heat Removal, Reactor Core Isolation Cooling, process sampling, and Standby Gas Treatment. The program shall include the following:
a. Preventive maintenance and periodic visual inspection requirements; and
b. Integrated leak test requirements for each system at least once per
24 months. |
|
|
Term
| Explain the purpose and implementation of TS 5.5.3 Radioactive Effluent Controls Program |
|
Definition
This program conforms to 10 CFR 50.36a for the control of radioactive effluents
and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable. The program shall be contained in the ODCM, shall be implemented by procedures, and shall include remedial actions to be
taken whenever the program limits are exceeded. |
|
|
Term
| Explain the purpose and implementation of TS 5.5.4 Component Cyclic or Transient Limit Program |
|
Definition
This program provides controls to track the USAR Table 4.2-1, cyclic and
transient occurrences to ensure that components are maintained within the
design limits. |
|
|
Term
| Explain the purpose and implementation of TS 5.5.7 Explosive Gas and Storage Tank Radioactivity Monitoring Program |
|
Definition
This program provides controls for potentially explosive gas mixtures contained in the Offgas Treatment System, the quantity of radioactivity contained in gas storage tanks or fed into the Offgas Treatment System, and the quantity of radioactivity contained in unprotected outdoor liquid storage tanks.
The quantity of radioactivity after 12 hours holdup contained in each gas storage tank shall be < or = 22,000 Ci of noble gases
The quantity of liquid radioactive waste contained in each unprotected outdoor liquid storage tank shall be < or = 10 Ci. |
|
|
Term
| Explain the purpose and implementation of TS 5.5.9 Tech Spec Bases Control Program |
|
Definition
This program provides a means for processing changes to the Bases of these
Technical Specifications.
a. Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.
b. Licensees may make changes to Bases without prior NRC approval
provided the changes do not require either of the following:
1. A change in the TS incorporated in the license; or
2. A change to the USAR or Bases that requires NRC approval pursuant to 10 CFR 50.59. |
|
|
Term
| Explain the purpose of TS 5.5.6 Ventilation Filter Testing Program |
|
Definition
A program shall establish the required testing of Engineered Safety Feature
(ESF) filter ventilation systems. Tests described in Specifications 5.5.6.a and
5.5.6.b shall be performed once per 24 months and following painting, fire, or
chemical release in any ventilation zone communicating with the subsystem
while it is in operation that could adversely affect the high efficiency particulate air (HEPA) filters or charcoal adsorber capability. |
|
|
Term
| Explain the purpose of TS 5.5.5 Inservice Testing Program |
|
Definition
| This program provides controls for inservice testing of ASME Code Class 1, 2,and 3 pumps and valves. |
|
|
Term
| Explain the purpose of TS 5.5.10 Safety Function Determination Program (SFDP) |
|
Definition
| This program ensures loss of safety function is detected and appropriate actions taken. Upon entry into LCO 3.0.6, an evaluation shall be made to determine if loss of safety function exists. Additionally, other appropriate actions may be taken as a result of the support system inoperability and corresponding exception to entering supported system Condition and Required Actions. This program implements the requirements of LCO 3.0.6. |
|
|
Term
| Explain the purpose of TS 5.5.11 Primary Containment Leak Rate Testing Program |
|
Definition
A program shall establish the leakage rate testing of the containment as
required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, "Performance- Based Containment Leak-Test Program," |
|
|
Term
| Explain the purpose of TS 5.5.13 Control Room Envelope (CRE) Habitability Program |
|
Definition
A Control Room Envelope (CRE)Habitability Program shall be established and implemented to ensure that CRE habitability is maintained such that, with an OPERABLE Control Room Emergency Filtration (CREF) System, CRE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a smoke challenge. The program shall ensure that adequate radiation protection is provided to permit access and occupancy of the CRE under design basis accident (DBA) conditions without personnel
receiving radiation exposures in excess of 5 rem total effective dose equivalent (TEDE) for the duration of the accident. |
|
|
Term
| Explain the purpose of TS 5.5.8 Diesel Fuel Oil Testing Program |
|
Definition
| A diesel fuel oil testing program to implement required testing of both new fuel oil and stored fuel oil shall be established. The program shall include sampling and testing requirements, and acceptance criteria, all in accordance with applicable ASTM Standards |
|
|
Term
| Explain the purpose of TS 5.5.12 Battery Monitoring and Maintenance Program |
|
Definition
This Program provides for battery restoration and maintenance, based on the recommendations of IEEE Standard 450-1995, "IEEE Recommended Practice
for Maintenance, Testing, and Replacement of Vented Lead-Acid Batteries for Stationary Applications" |
|
|
Term
| Explain the purpose and reporting requirements of the Annual Radiological Environmental Report |
|
Definition
The Annual Radiological Environmental Operating Report covering the operation
of the unit during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. |
|
|
Term
| Explain the purpose and reporting requirements of the Radioactive Effluent Release Report |
|
Definition
The Radioactive Effluent Release Report covering the operation of the unit
during the previous year shall be submitted prior to May 15 of each year in accordance with 10 CFR 50.36a. The report shall include a summary of the
quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. |
|
|
Term
| Explain the purpose and reporting requirements of the Core Operating Limits Report |
|
Definition
Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:
1. The APLHGR for Specification 3.2.1;
2. The MCPR for Specification 3.2.2;
3. The LHGR for Specification 3.2.3;
4. Control Rod Block Instrumentation Allowable Value
5. Reactor Protection System Instrumentation Delta W Allowable Value
6. Reactor Protection System Instrumentation Period Based Detection
Algorithm trip setpoints |
|
|
Term
| Explain the purpose and reporting requirements of the Post Accident Monitoring Report |
|
Definition
When a report is required by Condition B or F of LCO 3.3.3.1, "Post Accident
Monitoring (PAM) Instrumentation," a report shall be submitted within the
following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status. |
|
|
Term
| Explain the purpose and implementation of TS 5.7, "Control of High Radiation Areas" |
|
Definition
| Required per 10 CFR Part 20. Controls differ depending on Dose rates above or below 1.0 REM/hour and above or below 500 rads/hour. |
|
|
Term
Identify the SSCs which are included in the scope of the Operability/
Functionality Determination process. |
|
Definition
| Applies to all owner controllled SSCs described in Tech Specs |
|
|
Term
Discuss time requirements and considerations for an Operability/
Functionality Determination. |
|
Definition
|
|
Term
|
Definition
| LCOs shall be met during the MODES or other specified conditions in the Applicability, except as provided in LCO 3.0.2, LCO 3.0.7, LCO 3.0.8, and LCO 3.0.9. |
|
|
Term
|
Definition
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. |
|
|
Term
|
Definition
When an LCO is not met and the associated ACTIONS are not met, an
associated ACTION 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 2 within 7 hours;
b. MODE 3 within 13 hours; and
c. MODE 4 within 37 hours. |
|
|
Term
| When is LCO 3.0.3 applicable? |
|
Definition
| LCO 3.0.3 is only applicable in MODES 1, 2, and 3. |
|
|
Term
| Where is the exceptions to LCO 3.0.3? |
|
Definition
| Exceptions to this Specification are stated in the individual Specifications. |
|
|
Term
| How is LCO 3.0.3 affected when corrective measures are completed that permit operation in accordance with the LCO or ACTIONS? |
|
Definition
Completion of the actions required
by LCO 3.0.3 are not required. |
|
|
Term
|
Definition
When an LCO is not met, entry into a MODE or other specified condition in the Applicability shall only be made:
a. Assocoated ACTIONS to be entered permit continued operation.
b. After performing a Risk Assesment with the results determining it is acceptable to enter the MODE or other specified condition, or
c. When an allowance is stated in the Specification. |
|
|
Term
| What is and exception to LCO 3.0.4? |
|
Definition
LCO 3.0.4 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. |
|
|
Term
|
Definition
| INOPERABLE equipment may be returned to service under administrative control only to prove its own operability or the operability of other equipment. |
|
|
Term
|
Definition
If a support system is inoperable, the supported system's LCO is invoked if and only if the supporting system does not have its own LCO.
If supported system on the opposite divition becomes INOPERABLLE, both divisions supported systems become INOPERABLE. |
|
|
Term
| What must be performed when you invoke LCO 3.0.6? |
|
Definition
An evaluation shall be performed in accordance with Specification 5.5.10, "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. |
|
|
Term
|
Definition
Special Operations LCOs in Section 3.10 allow specified Technical
Specifications (TS) requirements to be changed to permit performance of
special tests and operations. Unless otherwise specified, all other TS
requirements remain unchanged. |
|
|
Term
|
Definition
An INOPERABLE snubber needs not invoke its supported subsystem until:
a. 72 hours if the snubber supports a single subsystem, or
b. 12 hours if a snubber supports multiple subsystems. |
|
|
Term
|
Definition
When one or more required barriers are unable to perform their related support function, any supported system LCO9(s) are not required to be declared for up to 30 days provided that at
least one division or subsystem of the supported system is OPERABLE
and supported by barriers capable of providing their related support
function(s), and risk is assessed and managed. |
|
|
Term
| What barriers are not covered in LCO 3.0.9? |
|
Definition
This provision does not apply to barriers which support ventilation
systems or to fire barriers. |
|
|
Term
| What are the initiating event categories for LCO 3.0.9? |
|
Definition
• Loss of coolant accidents;
• High energy line breaks;
• Feedwater line breaks;
• Internal flooding;
• External flooding;
• Turbine missile ejection; and
• Tornado or high wind. |
|
|
Term
| Which systems safety related systems can not apply LCO 3.0.9? |
|
Definition
High Pressure Coolant Injection
(HPCI) system, the Reactor Core Isolation Cooling (RCIC) system, and
the Automatic Depressurization System (ADS) are considered
independent subsystems of a single system. |
|
|
Term
|
Definition
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.
Surveillances do not have to be performed on inoperable equipment or variables outside specified limits. |
|
|
Term
|
Definition
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.
Exceptions to this Specification are stated in the individual Specifications. |
|
|
Term
|
Definition
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.
A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours and the risk impact shall be managed. |
|
|
Term
|
Definition
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. |
|
|
