Reactor Coolant System Flashcards

1
Q

Discuss Core Thermal Power.

A

3020 MWth
+14 MWth from RCPs => Total 3034 MWth

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2
Q

Discuss RCS Pressure.

A

Normal - 2250 psia
Design - 2500 psia
TS Safety Limit - 2750 psia

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3
Q

Discuss RCS Temperature.

A

Minimum Temp for Criticality – 515°F
No Load Tave - 532°F
Full Power Tave – 577.5°F

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4
Q

Discuss Load Change rates.

A

5% / minute Ramp
10% Step

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5
Q

Discuss RCS Heat-Up Rates.

A

Unit 1 - 70F/hr
Unit 2 - 50F/hr

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6
Q

Discuss RCS Cooldown Rates.

A

Unit 1
TR 13.4.1
A maximum cooldown of 100 °F in any 1-hour period
Transitions to lower values @180°F↓
Admin Limit: 85°F / HR

Unit 2
TR 13.4.1
A maximum cooldown of 100 °F in any 1-hour period
Transitions to lower values @212°F↓
Admin Limit: 85°F / HR

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7
Q

Discuss RCS Volume.

A

Unit 1
Hot: 62,500 gal
Cold: 80,000 gal

Unit 2
Hot: 66,891
Cold: 85,600

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8
Q

Discuss major RCS penetrations.

A
  • 2 Hot Legs & 4 Cold Legs
  • PZR surge line connected to ‘B’ Hot Leg
  • PZR Spray lines connected to B1 & B2 Cold Legs
  • SDC supplied from both Hot Legs & returned to all 4 Cold Legs
  • HP & LP Safety injection supplied to all 4 cold legs – 12” lines angled at 30 degrees towards the core
  • HPSI Hot Leg Injection – taps into the SDC hot leg suction lines
  • Charging supplied to A2 / B1 Cold Leg
  • Letdown from B1 Intermediate leg – 2” line shares the B1 RCP suction leg with low point drain.
  • RCGVS – vents PZR steam space and RX vessel head to 3 paths via orifices
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9
Q

What is indication of an Open RTD?

A

Reading fails high.

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10
Q

What is indication of a Shorted RTD?

A

Reading fails low.

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11
Q

Discuss Thot & Tcold instruments.

A

Thot & Tcold have both Control Channels & Safety Channels.

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12
Q

How do RTDs indicate on a power loss to circuit?

A

Power loss to circuit fails to minimum temperature indication.

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13
Q

What do RCS Control Channels provide input to?

A

Reactor Regulating System
LTOP
Alarms
Indication

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14
Q

What do RCS Safety Channels provide input to?

A

Reactor Protection System
ESFAS

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15
Q

How is Tavg signal generated?

A

Thot & Tcold inputs are summed for Tavg indication & control circuitry.

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16
Q

Discuss Hot Leg Safety Instruments.

A

(TE 1111X & 1121X)

Feeds RX Protection System - RPS 1112/1122(HA/HB/HC/HD)

17
Q

Discuss Hot Leg Control Instruments.

A

(TE 1111X & 1121X)

Feeds RX Regulating System for Tave input, RTGB alarms & RTGB recorder

Thot High Temp alarm (605F)

Unit 1 Only
Feeds Hand Switches 1102A/B/C/D on Unit 1 only – selects which channel is used for indication.

18
Q

Discuss Hot Leg Temperature RTDs.

A

5 RTD’s (4 Safety; 1 Control on each loop) – Unit 1 & 2 are the same.

19
Q

Discuss Cold Leg Temperature RTDs.

A

Cold Leg Temperature: 3 RTD’s (2 Safety; 1 Control on each loop).

20
Q

Discuss Cold Leg Control Instruments.

A

(TE 1111Y, 1115, 1121Y & 1125)

(1111Y/1121Y) – Input to RX Regulating System & CEA control

Tcold High Temp alarm (549 F)

(1115/1125) – Input to ERDADS, DDPS [DCS], and LTOPS

Unit 1 Only
Normal & Alternate switch allows feeds to RX Regulating System & LTOP Control through Hand Switches 1111 & 1121 on RTGB 103 Unit 1 only

21
Q

Discuss RCS Flow Instrumentation.

A

4 RCP Differential Pressure Transmitters – (1 per pump) Used for indication of pump performance.

4 Core Differential Pressure Transmitters – Used for Indications of core flow. Dual indicators/dual strip chart recorders on back of RTGB (1 per loop), W/X-loop A, Y/Z-loop B

4 S/G Differential Pressure Transmitters – Used for RCS loop low flow input to RPS / ESFAS / ATWS & indication on RTGB. 4 safety channels (A/B/C/D) on each S/G.

Normal D/P ~ 28 PSID [22 PSID]

Diff Pressure orifices - limit flow in case of rupture

22
Q

Discuss Reactor Vessel Level Monitoring System.

A

2 channels on QSPDS A/B fed by separate probe assembly in upper head. Each channel has 8 pairs of heated and unheated junction thermocouples (JTC). High delta T (>200F) indicates uncovering of the pair (HJTC can’t dissipate heat). >700F indicates uncovering of (UHJTC)

Rx Vessel Level [Refueling Level] – RVLMS not used during refueling ops, Narrow (0-48”) and Wide (0-400”) Range used in conjunction with tygon hose connected to A Hot Leg on high pressure side, top of PZR on low pressure side CRAC [PACB], Tygon hose connected to B1 RCP suction leg drain line and top of PZR

23
Q

Discuss Reactor Coolant Gas Vent System (RCGVS) Functions.

A

Primary: Removal of non-condensable gas, post-accident from vessel head & PZR.
Secondary: Allows vent path when draining the RCS during outages.

24
Q

Discuss Reactor Coolant Gas Vent System (RCGVS) System Flowpaths.

A

To CTMT (accident path) - ‘A’ 125 VDC Fail Closed Solenoid

To Quench Tank (accident B/U path) - ‘B’ 125 VDC Fail Closed Solenoid

To CTMT purge exhaust path via Accumulator and Charcoal Filter - ‘B’ 125 VDC Fail Closed Solenoid (CNMT Purge is Isolated during Power Operation)

25
Q

Discuss Reactor Coolant Gas Vent System (RCGVS) System Alarms.

A

Alarms on high pressure (>2000 psia) – Indicates solenoid isolation valve is leaking

Alarm can be reversed to indicate failure of outer seal.

26
Q

Discuss Low Temperature Overpressure Protection System.

A

Designed to prevent brittle fracture.

Receives input from PZR pressure and TCold.

Opens associated PORV if pressure setpoint is reached

Unit 1:
530 psia all less than or equal to 300°F (TS limit)
350 psia any less than or equal to 200°F (TS limit)

Unit 2:
490 psia less than or equal to 240°F (during a cooldown)
490 psia less than or equal to 252°F (during a heatup)

27
Q

Discuss Single Phase NC Indications.

A

Required to be met in at least one loop in order to maintain NC flow

  • Loop Delta T < full power Delta T (50F)
  • Tcold stable or decreasing
  • Thot stable or decreasing
  • Thot & CET’s approximately equal
  • Subcooling based on CET’s >20F
28
Q

Discuss RCS Sampling.

A

Sample Isolation Valves close on CIS [CIAS] – can be overridden to open valves:

  • ‘A’ Hot Leg
  • PZR Steam Space
  • PZR Surge Line
29
Q

Discuss Loss of Charging.

A

Letdown AUTO isolates, Lpzr decreases at 4 gpm (1%/12 min) from RCP seal leak off
No means to borate/dilute, No coolant purification ability

30
Q

Discuss Loss of Letdown.

A

Lpzr increases due to CHG pump running Cycle CHG pump to maintain Lpzr
Limited ability to borate/dilute, No coolant purification ability

31
Q

Discuss Lowered Inventory.

A

RCS Water level less than the RX Flange (36’), but above 33’

32
Q

Discuss Reduced Inventory.

A

RCS Water level is ≤ 33’ to 31’ 3”

33
Q

Discuss Mid Loop Condition.

A
  • Water level below Top of Hot Leg; Top of Hot Leg = 31’ 3”; Centerline of Hot Leg = 29’6”;
  • Use 2 LPSI Pumps with Flow Reduced to 1800 [1500] GPM per pump when on SDC in this condition to avoid vortexing. Vortex Formation is caused by Air Entrainment into the suction of the LPSI Pumps while on SDC due to lowering RCS level < 29’8”
  • Remove SG manway and install SG nozzle dams between {29’9.5” and 30’}[29’11.4”-29’8.2”]
  • To prevent RCS pressurization and loss of inventory on loss of SDC, hot legs opened before cold legs = Th manways off first/on last and Tc nozzle dams in first/out last
34
Q

Discuss RCS Fill and Vent.

A

Limits and Precautions include, but are not limited to, the following:
* Do NOT attempt to vent if the RCS temperature is above 200°F.

  • Fill water shall have a boron concentration equal to or greater than that required to maintain Shutdown Margin in accordance with 1[2]-NOP-100.04, Surveillance Requirements for Shutdown Margin, Modes 2, 3, 4 and 5
  • Placing Seal Injection in service to an uncoupled Reactor Coolant Pump may result in significant seal damage.
  • Seal Injection is required to be in service when filling the RCS from below the Seal Cartridge to above the Seal Cartridge to prevent contaminants on the surface of the Reactor Vessel water from entering the seals.
  • When the RCS is in Solid Pressure Control, Then close scrutiny should be given to any action that could result in the de-energizing any portion of the Class 1E 125V DC System. This could cause both isolation of the RCS while solid and the simultaneous failure of one PORV, thereby challenging the LTOP single failure design criteria.
35
Q

Discuss Draining the RCS.

A

Limits and Precautions include, but are not limited to, the following:
* When RCS level is being lowered below 30% in the Pzr, BOTH of the following independent level indications shall be operable: The tygon hose & LI-1117-1
* When venting through the RCGVS, the maximum drain down rate is limited to 500 gpm due to 7/16” orifices installed in the vent lines from the Reactor Head and the Pressurizer.
* If there is evidence of leaking fuel rods or if recommended by Chemistry Department, the RCS should be drained to the Hold-up Tanks.
* RCS drain down should be stopped based on the lowest indicated level.
* If the tygon level hose is being monitored by remote video indication and the video signal is lost or the indication is obstructed, the drain down shall be stopped until monitoring of the tygon hose is restored.

36
Q

Discuss Spray Delta T.

A

Exceeding the TS DT requires Documentation & Tracking

Unit 1
350F DT per TR 13.4.1

Unit 2
200F DT per 2-GOP-504 P&L

37
Q

What is Identified Leakage?

A

Identified LEAKAGE
1. LEAKAGE, such as that from pump seals or valve packing (except reactor coolant pump (RCP) seal water injection or leakoff), that is captured and conducted to collection systems or a sump or collecting tank;
2. LEAKAGE into the containment atmosphere from sources that are both specifically located and known to not interfere with the operation of leakage detection systems; or
3. Reactor Coolant System (RCS) LEAKAGE through a steam generator to the Secondary System (primary to secondary LEAKAGE);

38
Q

What is Unidentified Leakage?

A

Unidentified LEAKAGE
All LEAKAGE (except RCP seal water injection or leakoff) that is not identified LEAKAGE

39
Q

What is Pressure Boundary Leakage?

A

Pressure Boundary LEAKAGE
LEAKAGE (except primary to secondary LEAKAGE) through a fault in an RCS component body, pipe wall, or vessel wall. LEAKAGE past seals, packing, and gaskets is not pressure boundary LEAKAGE.