Above the Line

Question 1

2.1.1 Reactor Core Safety Limits

Answer 1

In MODES 1 and 2

2.1.1.1 The departure from nucleate boiling ratio (DNBR) shall be maintained ≥ 1.14 for the WRB-2M DNB correlation.2.1.1.2 The peak fuel centerline temperature shall be maintained < 5080°F, decreasing by 58°F per 10,000 MWD/MTU of burnup.

Question 2

2.1.2 RCS Pressure Safety Limit

Answer 2

MODES 1, 2, 3, 4, and 5

the RCS pressure shall be maintained ≤ 2733.5 psig.

Question 3

TS 3.3.1 Reactor Trip System (RTS) Instrumentation

Answer 3

According to Table 3.3.1-1.

Separate Condition entry is allowed for each Function.

Question 4

TS 3.3.5 Reactor Trip System (RTS) Manual Actuation

Answer 4

According to Table 3.3.5-1.

The RTS manual actuation channels for each Function in Table 3.3.5-1 shall be OPERABLE.

Separate Condition entry is allowed for each Function.

Question 5

TS 3.3.8 Engineered Safety Feature Actuation System (ESFAS) Instrumentation

Answer 5

According to Table 3.3.8-1.

Separate Condition entry is allowed for each Function

Question 6

TS 3.3.9 Engineered Safety Feature Actuation System (ESFAS) Manual Initiation

Answer 6

According to Table 3.3.9-1.

Separate Condition entry is allowed for each Function

Question 7

TS 3.3.11 Engineered Safety Feature Actuation System (ESFAS) Startup Feedwater Flow Instrumentation

Answer 7

MODES 1, 2, and 3,MODE 4 with the Reactor Coolant System (RCS) not being cooled by the Normal Residual Heat Removal System (RNS).

Two channels of ESFAS Startup Feedwater Flow instrumentation for each startup feedwater line shall be OPERABLE.

Separate condition entry is allowed for each startup feedwater line.

Question 8

TS 3.3.18 – RSW

Answer 8

MODES 1,2,3,
MODE 4 Tave ≥ 350 degrees F

L.C.O. 3.0.4 not applicable

Question 9

TS 3.3.19 – DAS Manual Controls

Answer 9

Table

Question 10

TS 3.4.7 – RCS Operational Leakage

Answer 10

MODES 1,2,3,4

No Pressure boundary LEAKAGE
0.5 gpm unidentified LEAKAGE
10 gpm identified LEAKAGE from the RCS
150 gpd primary to secondary LEAKAGE through one steam generator
500 gpd primary to IRWST LEAKAGE through PRHR

Question 11

TS 3.4.17 – SG Tube Integrity

Answer 11

MODES 1,2,3,4

Separate condition entry allowed For EACH SG TUBE

Question 12

TS 3.7.1 – MSSVs

Answer 12

MODES 1,2,3
MODE 4 not on RNS

Separate condition entry allowed For EACH MSSV

Question 13

TS 3.7.2 – MSL Flowpath Isolation Valves

Answer 13

MODES 1,2,3,4

< 5 Seconds to Close

Question 14

TS 3.7.3 – MSIVs and MFIVs

Answer 14

MODES 1,2,3,4

Separate condition entry allowed For EACH MFW LINE

Question 15

TS 3.7.4 – Secondary Specific Activity

Answer 15

MODES 1,2,3,4

≤ 0.1 μCi/gm DOSE EQUIVALENT I-131

Question 16

TS 3.7.7 – SFW Isolation and Control Valves

Answer 16

MODES 1,2,3,4

1) May be unisolated under admin controls
2) separate condition entry allowed For EACH LOWPATH

Question 17

TS 3.7.8 – MSL Leakage

Answer 17

MODES 1,2,3,4

≤ 0.5 gpm

Question 18

TS 3.7.10 – SG Isolation Valves

Answer 18

MODES 1,2,3,4 (except PORV when on RNS)

1) May be unisolated under admin controls
2) separate condition entry allowed For EACH FLOWPATH

Question 19

TS 3.8.1 – DC Sources - Operating

Answer 19

MODES 1,2,3,4

> = 200 amps for >= 8 Hrs

Question 20

TS 3.8.2 – DC Sources - Shutdown

Answer 20

MODES 5, 6
During movement of fuel

L.C.O. 3.0.3 not applicable

Question 21

TS 3.8.3 – Inverters - Operating

Answer 21

MODES 1,2,3,4

Inverter may be disconnected for ≤ 72 hrs. Provided:

1) EA bus is energized from VRT
2) All other EA buses energized from OPERABLE inverters

Question 22

TS 3.8.4 – Inverters - Shutdown

Answer 22

MODES 5, 6
During movement of fuel

L.C.O. 3.0.3 not applicable

Question 23

TS 3.8.5 – Distribution Systems - Operating

Answer 23

MODES 1,2,3,4

The following Division A, B, C, and D electrical power distribution subsystems shall be OPERABLE:

a. DC; and
b. AC instrument and control

Question 24

TS 3.8.6 – Distribution Systems - Shutdown

Answer 24

MODES 5, 6
During movement of fuel

L.C.O. 3.0.3 not applicable

Question 25

TS 3.8.7 – Battery Parameters

Answer 25

When DC power sources required to be OPERABLE

Separate Condition Entry allowed For EACH BATTERY

> 2.07 V
< 2 Amps

Question 26

TRM 3.3.1 Diverse Actuation System (DAS)

Answer 26

MODES 1, 2, 3, 4, and 5,
MODE 6 with with upper internals in place,
MODE 6 with cavity level < 23 feet above the top of the reactor vessel flange.

DAS automatic actuation functions and DAS automatic actuation initiation signals listed in Table TR 3.3.1-1 shall be FUNCTIONAL.
DAS ATWS mitigation functions of reactor trip and turbine trip actuation are only required in MODE 1.

Question 27

TRM 3.8.1 AC Power Supplies – Operating

Answer 27

MODES 1, 2, 3, 4, and 5

One standby diesel generator shall be FUNCTIONAL.

SDG Fuel Tank > 50,000 gal
Transfer Pump Recirc > 8 gpm
Starts and Operates > 4000 kw for > 1 Hr

Question 28

TRM 3.8.2 AC Power Supplies – Reactor Coolant System (RCS) Open

Answer 28

MODE 5 with RCS pressure boundary open,
MODE 6 with with upper internals in place,
MODE 6 with cavity level < 23 feet above the top of the reactor vessel flange.

The following AC power supplies shall be FUNCTIONAL to support Normal Residual Heat Removal System (RNS) operation:

a. One offsite circuit; and
b. One standby diesel generator.

Question 29

TRM 3.8.3 AC Power Supplies - Long Term Shutdown

Answer 29

MODES 1, 2, 3, 4, 5, and 6

One ancillary diesel generator shall be FUNCTIONAL

Ancillary DG Fuel Tank > 600 gal
Starts and Operates for > 1 Hr for > 35 kW

Question 30

TR 3.8.4 Non Class 1E DC and UPS System (EDS)

Answer 30

MODES 1, 2, 3, 4, and 5,
MODE 6 with with upper internals in place,
MODE 6 with cavity level < 23 feet above the top of the reactor vessel flange

Power for DAS automatic actuation functions required by TR 3.3.1 shall be FUNCTIONAL.

120 V +/- 5%