Outage GOP Flashcards
Describe the impact that atmospheric pressure has on the Refueling Pool and Spent Fuel Pool levels.
A pressure differential between the Fuel Building and Containment can affect the Fuel Canal level. This can cause the Fuel Canal level to be either higher or lower than Refueling Pool level. Changing the HVAC conditions in either the Fuel Building or Containment has caused flooding of Containment components and Fuel Building components.
State what can happen when the Gate between the Fuel Canal and the SFP is removed, including actions that could be taken to prevent an unwanted FBEVAS.
Removal of the Gate between the Fuel Canal and the SFP may cause radiation levels in the Fuel Building to rise, causing an unwanted FBEVAS. Examples of preventive actions which could preclude an unwanted FBEVAS include, but are not limited to, the following:
• Manual initiation of FBEVAS and CREFAS.
• Manual start of essential equipment that would be started by a FBEVAS.
This evolution should be carefully coordinated between the Control Room, RAMS, RP and Effluents. RP should carefully monitor radiation levels in the Fuel Building and halt gate movement if levels on RU-31 rise to ALERT. With appropriate management guidance it may also be reasonable to bypass RU-31 prior to removing the gate to prevent an unwanted FBEVAS/CREFAS which would be a reportable event.
Concerning RCS Chemical Cleanup, state the chemical that is added, what impact this chemical has on RCS crud, and what conditions are set up to increase its effectiveness.
The injection of hydrogen peroxide (H2O2) at an RCS temperature of less than 200°F should mobilize and transfer RCS corrosion products into a form which can be fixed on the Purification Ion Exchanger (IX) resins. Target temperature for H2O 2addition is 150°F to 180°F.
Concerning RCS Chemical Cleaning, state the major concern and what contingencies are in place to deal with it.
A major concern during the entire cleanup process is the potential for raising radiation levels in areas involved in the process (i.e.; RCS, CVCS, SI, SR, and Sampling System areas). Peak activity levels from the CRUD release are expected to occur within the first two hours of each H2O 2injection. The Outage GOP procedure requires posting the areas that are expected to have elevated radiation levels, and as much as possible, keep workers out of those areas until radiation levels have dropped.
Define a “Core Alteration” and describe the PVNGS Core Alterations position.
CORE ALTERATION shall be the movement or manipulation of any fuel, sources, or reactivity control components [excluding control element assemblies (CEAs) withdrawn into the upper guide structure], within the reactor vessel with the vessel head removed and fuel in the vessel. Suspension of CORE ALTERATIONS shall not preclude movement of a component to a safe position. PVNGS Position Statement on Core Alterations (reference letter 102-03641-AKK/NLT)
• Core Alteration is the movement or manipulation of any fuel, sources, or reactivity control components (excluding control element assemblies (CEAs) withdrawn into the upper guide structure), within the Reactor Vessel with the Reactor Vessel Head removed and fuel in the Reactor Vessel. Suspension of Core Alterations does not preclude movement of a component to a safe location.
• Core Alterations are considered to be suspended as long as the fuel, source and reactivity control components are in a static condition.
• Additionally, it is recommended that evolutions in the Reactor Vessel involving equipment or tools be evaluated to ensure that they would not create a direct radiation hazard, or create a significant increase in reactivity, such that Containment closure and operability of the Containment Purge Isolation System would be required.
• Any movement or manipulation of any fuel (whether contained in an intact assembly or as an individual rod) in the Reactor Vessel constitutes a core alteration. NRC approval of a Technical Specification change is required to allow recaging of a fuel assembly in the Reactor Vessel without instituting all core alteration Technical Specification requirements.
Describe the “Cessation of Core Alterations” and the communication requirements.
Brief administrative holds of core alterations are not formally considered Suspension of Core Alterations unless declared so by the Shift Manager or Refueling SRO. Core Alterations are considered to be administratively suspended when the movement or manipulation of any fuel, sources or reactivity control component within the Reactor Pressure Vessel has ceased, and the Refueling SRO has communicated the cessation of core alterations to the Control Room.
As long as no actual movement of any fuel, sources or reactivity control component within the Reactor Vessel is occurring, communications may be terminated, as long as a communications check is performed prior to resuming core alterations. During these intervals, the individuals associated with the core alteration can be contacted using the Plant Page System.
State the pressure and temperature that the use of a Containment Spray pump on SDC should be avoided.
RCS pressure shall be maintained less than 250 psia or RCS temperature shall be maintained less than 200°F when a Containment Spray Pump is aligned to the Shutdown Cooling System to preclude pump damage. Additionally, RCS pressure greater than 250 psig when a Containment Spray pump is operating on Shutdown Cooling will exceed the SI piping design pressure.
State the actions (including basis) required before a path is opened from an RCS Cold Leg to Containment.
Before opening a path from an RCS cold leg to Containment of greater than one square inch, a Hot Leg vent path must established. The vent path shall be shown by analysis to be of sufficient size to prevent uncovering the core due to pressurization of the RCS.
State the consequence of depressurizing the RCS with high gas concentrations.
High RCS total gas concentration may result in gases coming out of solution when the RCS is depressurized. This could inhibit Natural Circulation by gas binding the Steam Generator U-tubes.
State the required actions when it is desired to reduce SDC flow to 3780 gpm while in Mode 5 or 6.
IF SDC flow will be lowered to 3780 gpm, THEN ensure EW Inlet temperature vs. Time Post Shutdown requirements of the Safety Analysis Operational Data portion of the Core Data Book are met before SDC flow is lowered to 3780 gpm.
State when Seal Injection should be applied to the RCPs when the Plant is in Mode 6.
- Seal injection should be supplied to the RCPs whenever level is above the top of the cold legs.
- Seal injection shall be supplied to the RCPs when RCS temperature is equal to or greater than 195°F and pressure is greater than 215 psia.
