Reactor Coolant System Flashcards

1
Q

Natural circulation indications

A

-RCS subcooling- acceptable
-SG Pressure- Stable or Decreasing
-RCS hot leg temps- stable or Decreasing
-RCS cold leg temps- At saturation temperature for intact SG pressures
-Average 10 Highest TCs-Stable or decreasing

How well did you know this?
1
Not at all
2
3
4
5
Perfectly
2
Q

Minimum RCS temperature(not for criticality)

A

70F Assures that vessel flange minimum of 60F when vessel head is tensioned

How well did you know this?
1
Not at all
2
3
4
5
Perfectly
3
Q

BGP 100-1 (Heatup procedure) oxygen limitation

A

The RCS Oxygen concentration shall be less than 0.1 ppm with RCS
temperature > 250F. See TRM 3.4.b for transient limitations.

How well did you know this?
1
Not at all
2
3
4
5
Perfectly
4
Q

BGP 100-6 (Refueling) temperature/RCP condition limitation

A

RCS Temperature shall not be raised above 160F until at least one RCP
is running for solid water, low pressure operation. (CM-1)

How well did you know this?
1
Not at all
2
3
4
5
Perfectly
5
Q

CV charging taps-which cold legs?

A

A and B. Use of the normal and alternate charging shall be alternated over plant life, such that neither should be used for more than 60% of design transients. The transfer should be done in cold shutdown to avoid transients, starting with CV8147 A loop in cycle 1.

How well did you know this?
1
Not at all
2
3
4
5
Perfectly
6
Q

Core bypass flow

A

5.8%
Head bypass 2.3
flow through Crs and instr thimbles 2
Inlet to outlet nozzle bypass 1
Former and baffle 0.5

How well did you know this?
1
Not at all
2
3
4
5
Perfectly
7
Q

Penetrations that extend into the RCS piping

A
  1. PZR spray lines
  2. NR Thot RTD thermowell
  3. WR RTD thermowell
  4. Chemistry sampling line
How well did you know this?
1
Not at all
2
3
4
5
Perfectly
8
Q

One reason for RCS subcooling:
(Delta T)

A

ensure delta-T is accurate indication of reactor power

How well did you know this?
1
Not at all
2
3
4
5
Perfectly
9
Q

NR RTD description

A

Fast response RTDs located directly in the RCS loops. Three for each hot leg and only one for each cold leg. Each hot leg RTDs are averaged to compensate for streaming.

How well did you know this?
1
Not at all
2
3
4
5
Perfectly
10
Q

RTD open circuit/short circuit indications

A

Open-High resistance, high temperature
Short- Low resistance, low temperature

How well did you know this?
1
Not at all
2
3
4
5
Perfectly
11
Q

Stop valve internal relief mechanism

A

Vents excess water to Reactor during isolated loop warmup
Vents excess water between disks

How well did you know this?
1
Not at all
2
3
4
5
Perfectly
12
Q

DNBR requirements from TRM
including when pressure limit doesn’t apply.

A

Flow 386000 gpm
PZR pressure >=2209 psig
Tave <=593.1F

PZR pressure limit doesn’t apply during thermal power ramp>5%/min or Thermal power step of >10%RTP

How well did you know this?
1
Not at all
2
3
4
5
Perfectly
13
Q

BGP-6 refuel precaution max boron concentration

A

2450ppm to prevent unnecessary reduction in the NI response

How well did you know this?
1
Not at all
2
3
4
5
Perfectly
14
Q

Purpose of the reactor vessel

A

The reactor vessel is the pressure boundary which contains the nuclear fuel. The reactor vessel internals align and support the fuel, direct support equipment and instrumentation into the vessel, and direct the flow of coolant through the core.

How well did you know this?
1
Not at all
2
3
4
5
Perfectly
15
Q

Reactor vessel head purpose

A
  1. Supports CRDMs, restrains upper internals, and forms upper pressure boundary.
  2. Head bolted and sealed to reactor vessel.
  3. Two O rings between head and vessel, leakage sensed if O rings leak.
How well did you know this?
1
Not at all
2
3
4
5
Perfectly
16
Q

upper support plate and columns

A

Support plate- supports upper core plate
support columns- support upper plate and transmit load to lower core plate

How well did you know this?
1
Not at all
2
3
4
5
Perfectly
17
Q

RCCA guide tubes

A

Guide and support the control rods into and out of the fuel assemblies

How well did you know this?
1
Not at all
2
3
4
5
Perfectly
18
Q

Upper core plate

A

Transmits upward forces of fuel assemblies to upper support plate.

How well did you know this?
1
Not at all
2
3
4
5
Perfectly
19
Q

Core barrel

A

Transmits core/fuel weight to vessel flange.

How well did you know this?
1
Not at all
2
3
4
5
Perfectly
20
Q

Neutron pads

A

Attenuate fast neutrons, minimize embrittlement of the vessel wall.

How well did you know this?
1
Not at all
2
3
4
5
Perfectly
21
Q

Lower core plate

A

Aligns and supports fuel assemblies and distributes coolant flow to fuel assemblies.

How well did you know this?
1
Not at all
2
3
4
5
Perfectly
22
Q

Lower support columns

A

Transmits weight of lower core plate and the core to the core support.

How well did you know this?
1
Not at all
2
3
4
5
Perfectly
23
Q

Core support

A

Transmits weight of the lower core plate and core to the core barrel.

24
Q

Core baffle and former plates

A

Converts cylinder shape of core to box shape of fuel assemblies, minimizes bypass flow.

25
Loop isolation valves status at power
Deenergized open at power, no isolation capability at power
26
LCO 3.4.1
3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits LCO 3.4.1 RCS DNB parameters for pressurizer pressure, RCS average temperature (Tavg), and RCS total flow rate shall be within the limits specified below: a. Pressurizer pressure within the limit specified in the COLR; b. RCS average temperature (Tavg) within the limit specified in the COLR; and c. RCS total flow rate  386,000 gpm and within the limit specified in the COLR. ----------------------------NOTE---------------------------- Pressurizer pressure limit does not apply during: a. THERMAL POWER ramp > 5% RTP per minute; or b. THERMAL POWER step > 10% RTP. ----------------------------------------- 2 hour to restore
27
LCO 3.4.2 Minimum temp for criticality
3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.2 RCS Minimum Temperature for Criticality LCO 3.4.2 Each RCS loop average temperature (Tavg) shall be >= 550F. APPLICABILITY: MODE 1, MODE 2 with keff >= 1.0. 30 minutes to Mode 2, <1.0 keff
28
3.4.3 PTLR
3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.3 RCS Pressure and Temperature (P/T) Limits LCO 3.4.3 RCS pressure, RCS temperature, and RCS heatup and cooldown rates shall be maintained within the limits specified in the PTLR. APPLICABILITY: At all times.
29
3.4.4 RCS loops operating
3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.4 RCS Loops-MODES 1 and 2 LCO 3.4.4 Four RCS loops shall be OPERABLE and in operation. APPLICABILITY: MODES 1 and 2.
30
3.4.5 mode 3
3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.5 RCS Loops-MODE 3 LCO 3.4.5 Two RCS loops shall be OPERABLE, and either: a. Two OPERABLE RCS loops shall be in operation when the Rod Control System is capable of rod withdrawal; or b. One OPERABLE RCS loop shall be in operation when the Rod Control System is not capable of rod withdrawal. ----------------------------NOTE---------------------------- All reactor coolant pumps may be removed from operation for  1 hour per 8 hour period provided: a. No operations are permitted that would cause reduction of the RCS boron concentration; and b. Core outlet temperature is maintained  10F below saturation temperature. ------------------------------------------------------------ APPLICABILITY: MODE 3.
31
What constitutes an operable SG per loop definition?
An OPERABLE RCS loop consists of one OPERABLE RCP and one OPERABLE SG, which has the minimum water level specified in SR 3.4.5.2. An RCP is OPERABLE if it is capable of being powered and is able to provide forced flow if required. SR 3.4.5.2 Verify steam generator secondary side narrow range water level is >=18% for each required RCS loop.
32
3.4.6 Loops Mode 4
3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.6 RCS Loops-MODE 4 LCO 3.4.6 Two loops consisting of any combination of RCS loops and Residual Heat Removal (RHR) loops shall be OPERABLE, and one OPERABLE loop shall be in operation. ----------------------------NOTES--------------------------- 1. All Reactor Coolant Pumps (RCPs) and RHR pumps may be removed from operation for  1 hour per 8 hour period provided: a. No operations are permitted that would cause reduction of the RCS boron concentration; and b. Core outlet temperature is maintained >= 10F below saturation temperature. 2. No RCP shall be started with any RCS cold leg temperature <= 350F unless the secondary side water temperature of each Steam Generator (SG) is <= 50F above each of the RCS cold leg temperatures. ------------------------------------------------------------ APPLICABILITY: MODE 4.
33
3.4.7
3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.7 RCS Loops-MODE 5, Loops Filled LCO 3.4.7 One Residual Heat Removal (RHR) loop shall be OPERABLE and in operation, and either: a. One additional RHR loop shall be OPERABLE; or b. The secondary side water level of at least two Steam Generators (SGs) shall be >= 18%. ----------------------------NOTES--------------------------- 1. The RHR pump may be removed from operation for <= 1 hour per 8 hour period provided: a. No operations are permitted that would cause reduction of the RCS boron concentration; and b. Core outlet temperature is maintained >= 10F below saturation temperature. 2. One required RHR loop may be inoperable for <= 2 hours for surveillance testing provided that the other RHR loop is OPERABLE and in operation. 3. No reactor coolant pump shall be started with any RCS cold leg temperature <= 350F unless the secondary side water temperature of each SG is >= 50F above each of the RCS cold leg temperatures. 4. All RHR loops may be removed from operation during planned heatup to MODE 4 when at least one RCS loop is in operation. ------------------------------------------------------------ APPLICABILITY: MODE 5 with RCS loops filled.
34
3.4.8
3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.8 RCS Loops-MODE 5, Loops Not Filled LCO 3.4.8 Two Residual Heat Removal (RHR) loops shall be OPERABLE and one OPERABLE RHR loop shall be in operation. ----------------------------NOTES--------------------------- 1. All RHR pumps may be removed from operation for <= 1 hour provided: a. No operations are permitted that would cause a reduction of the RCS boron concentration; b. The core outlet temperature is maintained >=10F below saturation temperature; and c. No draining operations are permitted that would further reduce the RCS water volume. 2. One RHR loop may be inoperable for <= 2 hours for surveillance testing provided that the other RHR loop is OPERABLE and in operation. ------------------------------------------------------------ APPLICABILITY: MODE 5 with RCS loops not filled.
35
3.4.9 Pressurizer
3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.9 Pressurizer LCO 3.4.9 The pressurizer shall be OPERABLE with: a. Pressurizer water level <= 92%; and b. Two groups of pressurizer heaters OPERABLE with the capacity of each group >=150 kW and capable of being powered from redundant Engineered Safety Features (ESF) power supplied buses. APPLICABILITY: MODES 1, 2, and 3.
36
3.4.10 safety valves
3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.10 Pressurizer Safety Valves LCO 3.4.10 Three pressurizer safety valves shall be OPERABLE with lift settings >= 2411 psig and <= 2509 psig. ----------------------------NOTE---------------------------- The lift settings are not required to be within the LCO limits during MODE 3 for the purpose of setting the pressurizer safety valves under ambient (hot) conditions. This exception is allowed for 54 hours following entry into MODE 3 provided a preliminary cold setting was made prior to heatup. ------------------------------------------------------------ APPLICABILITY: MODES 1, 2, and 3. 15 minutes to restore or mode 3 in 6 hours
37
3.4.11 PORVs
3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.11 Pressurizer Power Operated Relief Valves (PORVs) LCO 3.4.11 Each PORV and associated block valve shall be OPERABLE. APPLICABILITY: MODES 1, 2, and 3. ACTIONS ------------------------------------- NOTE------------------------------------ Separate Condition entry is allowed for each PORV and each block valve. -----------------------------------------------------------------------------
38
If PORV capable of being cycled but inop? If not capable of being cycled?
Porv inop but can be cycled- block valve closed with power PORV inop, can not be cycled- block valve closed, deenergized
39
3.4.12 LTOP
3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.12 Low Temperature Overpressure Protection (LTOP) System LCO 3.4.12 An LTOP System shall be OPERABLE with: a. A maximum of one charging pump (centrifugal) capable of injecting into the RCS; b. No Safety Injection (SI) pumps capable of injecting into the RCS; c. Each SI accumulator isolated, whose pressure is greater than or equal to the maximum RCS pressure for the existing RCS cold leg temperature allowed by the P/T limit curves provided in the PTLR; and d. One of the following pressure relief capabilities: 1. Two Power Operated Relief Valves (PORVs) with lift settings within the limits specified in the PTLR, 2. Two Residual Heat Removal (RHR) suction relief valves with setpoints <= 450 psig, 3. One PORV with a lift setting within the limits specified in the PTLR and one RHR suction relief valve with a setpoint <= 450 psig, or 4. The RCS depressurized and an RCS vent of <= 2.0 square inches. ----------------------------NOTES--------------------------- 1. Operation in MODE 4 with all SI pumps and charging pumps capable of injecting into the RCS is allowed when all RCS cold legs exceed 330F. 2. For the purpose of protecting the decay heat removal function, one or more SI pumps may be capable of injecting into the RCS in MODE 5 and MODE 6 when the reactor vessel head is on provided pressurizer level is ≤ 5 percent. ------------------------------------------------------------ APPLICABILITY: MODES 4 and 5, MODE 6 when the reactor vessel head is on.
40
3.4.13 Leakage
3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.13 RCS Operational LEAKAGE LCO 3.4.13 RCS operational LEAKAGE shall be limited to: a. No pressure boundary LEAKAGE; b. 1 gpm unidentified LEAKAGE; c. 10 gpm identified LEAKAGE; and d. 150 gallons per day primary to secondary LEAKAGE through any one steam generator (SG). APPLICABILITY: MODES 1, 2, 3, and 4.
41
3.4.14 PIV leakage limits
3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage LCO 3.4.14 Leakage from each RCS PIV shall be within limits. APPLICABILITY: MODES 1, 2, 3, and 4. ACTIONS -------------------------------------NOTES ----------------------------------- 1. Separate Condition entry is allowed for each flow path. 2. Enter applicable Conditions and Required Actions for systems made inoperable by an inoperable PIV. ------------------------------------------------------------------------------
42
Hot 57 chevy low rider Cold 6 pack of lowenbreau
Valve 455A Auct. WR Low Thot and PT-407 5 Low Hot 7 Valve 456 Auct WR Low Tcold and PT-406 6 Low Cold 6 LOWenbreau
43
3.4.15 RCS leakage detection
3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.15 RCS Leakage Detection Instrumentation LCO 3.4.15 The following RCS leakage detection instrumentation shall be OPERABLE: a. One containment sump monitor; and b. One containment atmosphere radioactivity monitor (gaseous or particulate). APPLICABILITY: MODES 1, 2, 3, and 4.
44
3.4.16 RCS specific activity
3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.16 RCS Specific Activity LCO 3.4.16 RCS DOSE EQUIVALENT I-131 and DOSE EQUIVALENT XE-133 specific activity shall be within limits. APPLICABILITY: MODES 1, 2, 3, and 4. SR 3.4.16.1 Verify reactor coolant DOSE EQUIVALENT XE-133 specific activity <= 603 Ci/gm. SR 3.4.16.2 Verify reactor coolant DOSE EQUIVALENT I-131 specific activity <= 1.0 Ci/gm.
45
3.4.17 loop isolation valves
3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.17 RCS Loop Isolation Valves LCO 3.4.17 Each RCS hot and cold leg loop isolation valve shall be open with power removed from each isolation valve operator. APPLICABILITY: MODES 1, 2, 3, and 4. ACTIONS -------------------------------------NOTE------------------------------------- Separate Condition entry is allowed for each RCS loop isolation valve. ------------------------------------------------------------------------------
46
3.4.18 loop isolations shutdown
3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.18 RCS Loops-Isolated LCO 3.4.18 Each RCS isolated loop shall remain isolated with: a. The hot and cold leg loop stop isolation valves closed if boron concentration of the isolated loop is less than the required SDM boron concentration of the unisolated portion of the RCS; and b. The cold leg loop stop isolation valve closed if the cold leg temperature of the isolated loop is > 20°F below the highest cold leg temperature of the unisolated portion of the RCS. APPLICABILITY: MODES 5 and 6.
47
3.4.19 SG tube integrity
3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.19 Steam Generator (SG) Tube Integrity LCO 3.4.19 SG tube integrity shall be maintained. AND All SG tubes satisfying the tube plugging criteria shall be plugged in accordance with the Steam Generator Program. APPLICABILITY: MODES 1, 2, 3, and 4. ACTIONS --------------------------------NOTE----------------------------------------- Separate Condition entry is allowed for each SG tube. -----------------------------------------------------------------------------
48
3 control functions that use the validated second highest Tavg
Rod Control, Steam dump control and pressurizer level control
49
RCP start logic
1. Hot and cold leg isol valves open or hot leg open/bypass open 2. Control switch to start 3. Lift pressure >600 psig
50
Auto open and auto close of 8114 and 8116 CV mini recircs:
Auto open: 2/4 WR pressure >=1643psig SI Auto Close with: -SI -2/4 WR Press < 1448 psig (4030 will show ¾ required to be < 1643 psig to close) WR PT403/405/408/409
51
RH suction valve open interlocks?
Can open when RCS pressure <=360 psig admin <=337# interlock Connect to A and C hot legs PT403 and 405
52
Physics test exceptions:
RCS Tave>=530F SDM wi/in 1300 pcm Therm power <=5% LCOs suspended: 3.1.3 MTC 3.1.4 Rod group alignment 3.1.5 SDBIL 3.1.6 CBIL 3.4.2 RCS minimum temp for criticality
53
OTdeltaT delta I bands
-18% to +10% Penalties above 10% and below -18%
54
OPdelta T and OT delta T baseline setpoints
107.2%-penalties and 132.5%+-penalities
55
Tave and delta T setpoints for control and alarm
Tave>Tref 3F will bring alarm 2nd highest validated Tave and delta T used for : -Rod control, rod insertion limit, steam dump, pzr level control delta T -computer, rod insertion limit
56
TS 3.4.6, if a required loop inoperable, what actions required? What if RHR is not operable?
Restore immediately and be in Mode 5 within 24 hours. If RHR not operable stay in mode 4.