ML041460377
| ML041460377 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 05/12/2004 |
| From: | Sean Peters NRC/NRR/DLPM/LPD2 |
| To: | Jamil D Duke Energy Corp |
| References | |
| TAC MC0498, TAC MC0499 | |
| Download: ML041460377 (2) | |
Text
ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 5 of 5)
Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER NOMINAL SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT
- 7. Automatic Switchover to Containment Sump
- a.
Automatic Actuation Logic and Actuation Relays
- b.
Refueling Water Storage Tank (RWST) Level -
Low Coincident with Safety Injection 1,2,3,4 1,2.3,4 2 trains 4
C SR 3.3.2.2 SR 3.3.2.4 SR 3.3.2.6 N
SR 3.3.2.1 SR 3.3.2.7 SR 3.3.2.9 SR 3.3.2.10 NA 2 162.4 Inches NA 177.15 Inches Refer to Function 1 (Safety Injection) for all Initiation functions and requirements.
- 8. ESFAS Interlocks
- a.
Reactor Trip, P-4
- b.
Pressurizer Pressure, P-1 1
- c.
Tag-Low Low, P-12 1,2.3 12,3 1,2,3 1 per train, 2 trains 3
1 per loop F
SR 3.3.2.5 SR 3.3.2.9 O
SR 3.3.2.5 SR 3.3.2.9 NA 2 1944 and
- 1966 psig 2 5500F NA 1955 psig 5530F
- 9. Containment Pressure Control System
- a.
Start Permissive
- b.
Termination 1,2,3,4 1,2,3,4 4 per train 4 per train P
SR 3.3.2.1 SR 3.3.2.7 SR 3.3.2.9 P
SR 3.3.2.1 SR 3.3.2.7 SR 3.3.2.9
- to psid 0.9 psid I
2 0.25 psid 0.35 psid I
- 10. Nuclear Service Water Suction Transfer - Low Pit Level 1,2,3,4 3 per pit QR SR 3.3.2.1 SR 3.3.2.9 SR 3.3.2.11 SR 3.3.2.12 2 El. 555.4 ft El. 557.5 ft Catawba Units 1 and 2 3.3.2-1 5 Amendment Nos. 214 & 208
ESFAS Instrumentation B 3.3.2 BASES APPLICABLE SAFETY ANALYSES, LCO, and APPLICABILITY (continued) decreasing temperature, the P-12 interlock removes the arming signal to the Steam Dump System to prevent an excessive cooldown of the RCS due to a malfunctioning Steam Dump System.
Since Tavg is used as an indication of bulk RCS temperature, this Function meets redundancy requirements with one OPERABLE channel in each loop. These channels are used in two-out-of-four logic. This Function must be OPERABLE in MODES 1, 2, and 3 when a secondary side break or stuck open valve could result in the rapid depressurization of the steam lines. This Function does not have to be OPERABLE in MODE 4, 5, or 6 because there is insufficient energy in the secondary side of the unit to have an accident.
- 9.
Containment Pressure Control System Permissives The Containment Pressure Control System (CPCS) protects the Containment Building from excessive depressurization by preventing inadvertent actuation or continuous operation of the Containment Spray and Containment Air Return Systems when containment pressure is at or less than the CPCS permissive setpoint. The control scheme of CPCS is comprised of eight independent control circuits (4 per train), each having a separate and independent pressure transmitter and current alarm module.
Each pressure transmitter monitors the containment pressure and provides input to its respective current alarm. The current alarms are set to inhibit or terminate containment spray and containment air return systems when containment pressure falls to or below 0.25 A.
The alarm modules switch back to the permissive state (allowing the systems to operate) when containment pressure is greater than or equal to 1.0 Dsid.
This function must be OPERABLE in MODES 1, 2, 3, and 4 when there is sufficient energy in the primary and secondary sides to pressurize containment following a pipe break. In MODES 5 and 6, there is insufficient energy in the primary and secondary sides to significantly pressurize the containment.
- 10.
Nuclear Service Water System Suction Transfer - Low Pit Level Upon an emergency low pit level signal from either NSWS pit, interlocks isolate the NSWS from Lake Wylie, align NSWS to the standby nuclear service water pond, close particular crossover Catawba Units 1 and 2 B 3.3.2-30 Revision No. 2