Sro Fuel Pool

Front 1

Question 1-1 What is the function of the Fuel Pool Cooling and Cleanup System?

Back 1

Answer 1-1 The function of the FPCCS is to maintain the SFP water temperature below its prescribed limits by removing the decay heat generated by stored spent fuel assemblies. It is also designed to remove impurities from the water in the SFP, Fuel Transfer Canal, Refueling Pool, and Cask Loading Pool. Removal of the impurities is done to ensure optical clarity, and to limit the concentration of specific activity in the water.

Front 2

Question 2-1 The Spent Fuel Storage Facility is designed to keep personnel radiation exposure to .

Back 2

Answer 2-1 less than 2.5 mrem/hour during normal operations and less than 10 mrem/hour during refueling operations

Front 3

Question 2-2 Why is a 3-inch vent hole in the return line is located at the 2043 foot elevation, slightly under the normal water surface?

Back 3

Answer 2-2 Prevent inadvertent siphoning of the water from the pool.

Front 4

Question 2-3 The two Fuel Pool Cooling pump motor breakers are provided with what protection?

Back 4

Answer 2-3 Protection for a loss of suction and motor over current.

Front 5

Question 3-1 During normal cool-down of the reactor, when the Residual Heat Removal (RHR) System is used to remove core decay heat, the RHR Heat Exchanger could represent enough CCW demand to require that CCW flow be terminated to the FPCCS Heat Exchangers. What is the maximum temperature the SFP temperature is allowed to rise to, and how soon must CCW flow be restored?

Back 5

Answer 3-1 A maximum of 160¡F with a fully irradiated core in the pool. The CCW flow to the Fuel Pool Cooling heat exchanger must be restored within four hours.

Front 6

Question 4-1 Some of the major plant systems that interact with the Spent FPCCS include.

Back 6

Answer 4-1 * Area Radiation Monitoring System. * Boron Recycle System. * Component Cooling Water System. * Electrical Distribution System. * Essential Service Water System. * Floor And Equipment Drain System. * Fire Protection System. * Nuclear Sampling System. * Plant Heating, Air Conditioning, and Ventilation System. * Radwaste Building HVAC. * Reactor Coolant Drain Tank. * Reactor Makeup Water System. * Refueling Cavity. * Refueling Water Storage Tank. * Instrument And Service Air System.

Front 7

Question 4-2 Why do we use the Reactor Makeup System to increase SFP level? (Assume that level decrease was caused by evaporation only.)

Back 7

Answer 4-2 As most of the water loss from the SFP is through evaporation, only water is lost, and not boron. To prevent over-boration of the SFP, pure un-borated water is added to the pool from the Reactor Makeup Water System.

Front 8

Question 6-1 Indication of SFP level is provided where?

Back 8

Answer 6-1 * EC LI-39A MCB panel RL021 * EC LI-39B NB01 Switch-gear Room * EC LIT-39 NB02 Switch-gear Room

Front 9

Question 6-2 How is SFP level checked in the Fuel Building?

Back 9

Answer 6-2 A local indicator is mounted on the north wall of the SFP, and provides gross indication of normal level and the Technical Specification limit. It does this by use of two crossbars located at the 2046 elevation for normal level, and at the 2043 feet, 8.3 inch elevation for the Technical Specification limit.

Front 10

Question 6-3 True or False. The trip of the Fuel Pool Cooling pumps on low SFP level gives a MCB alarm.

Back 10

Answer 6-3 False

Front 11

Question 6-4 Which conditions will trip the Fuel Pool Cooling Pumps?

Back 11

Answer 6-4 * Low Spent Fuel Pool level. * A load shed signal. * Breaker overload.

Front 12

Question 7-1 How are the gates in the SFP protected against a loss of service air?

Back 12

Answer 7-1 Backup nitrogen bottles are provided near each gate.

Front 13

Question 9-1 How fast will the SFP heat up following a LOCA with loss of offsite power with temperature starting at 140 degrees?

Back 13

Answer 9-1 The pool will heat up at a maximum rate of 4.91 degrees per hour.

Front 14

Question 11-1 What design feature ensures that the SFP has adequate shutdown margin?

Back 14

Answer 11-1 The criticality analysis (including the associated assumptions and input parameters) is given in USAR Appendix 9.1A. This analysis shows that the spacing between fuel assemblies in the storage racks is sufficient to maintain the array, when fully loaded and flooded with non-borated water, in a sub critical condition, i.e., a Keff of less than 0.95. This is based on fuel with enrichments of up to 5 weight percent U-235.