ML20155G506
| ML20155G506 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 11/02/1998 |
| From: | VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | |
| Shared Package | |
| ML20155G496 | List: |
| References | |
| NUDOCS 9811090071 | |
| Download: ML20155G506 (7) | |
Text
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VYNPS TABLE 3.2.1 EMERGENCY CORE COOLING SYSTEM AC1UATION INSTRUMCfTATION Core Spray - A & B (Note 1)
Minimum Number of Required Action When Minimum Conditions operable Instrument Channels per Trip for operation System Trio Function Trio Level Settina are Not satisfied 1 5 psig Note 2 2
2 High Drywell Pressure
__82.5* above top of Note 2 2
Low-Low Reactor vessel Water Level enriched fuel 1
Low Reactor Pressure 300 1 P 5 350 psig Note 2 l
(PT-2-3-56C/D(H))
2 Low Reactor Pressure 300 1 P 5 350 psig Note 2 l
(PT-2-3-56A/B(H) & 52C/D(H))
he.pij Note 2 1
(14A-K16A & B) onds 2
- Fu=y (E-so-1A/B) Discharge
>100 psig Note 5 Pressure 1
Auxiliary Power Monitor Note $
t I
Note 5 1
Pump Bus Power Monitor 1
Trip System Logic Note 5 I
9911090071 981102~
PDR ADOCK 05000271 P
PDR t
ja Anendment No. 44, 68, 449, 441,144,M2
VYNPS TABLE 3.2.1
~
(Cont'd)
D4EROENCY CORE COOLitK2 SYSTEM ACWATION INSTRUMENTATIotl Low Pressure Coolant Injection System A & B (Note ~1)
Required Action When Hinimum Number of Minimum conditions Operable Instrument.
for Operation Channele per Trip Trio Level Settina are Not Satisfied Trio Function System Note 2 1-Low Reactor Pressure 300 g p g 350 peig (PT-2-3-56C/D(H))
l Note 2 i
$.5 peig 2
2 High Drywell Pressure (PT-10-101A-D(H))
Low-Low Reactor vessel Water 182.5" above top of Note 2 2
enriched fuel Level
[
[
Note 5 l
M Delay (10A-K51A & J 0 seconds Note 5 1 /3 core height 2
Reactor Vessel Shroud Level 1
Note 5 1
Time Delhy (10A-K72A,p B) 560 seconds 1
'!== h (10A-K50A & B) haeconde 3 $ (, f f Note 5 Note"2-Pressure 100 g p 5 150 psig 1
n==u (PS-2-128A & B)
Note 5 RHR Pump A & C Discharge A100 peig 2 per pump Pressuro Note 2 i
$.5 psig 2
2 High Drywell Pressure (PT-10-101A-D(S1))
r Amendment flo. H, 44. 68, He, i.
- Egg, 3. 5.
(Cont'd) n e Degraded Grid Protective System has been installed to assure thatsubjected to sustaine safety-related electrical equipment will notThis system incorporates voltage relays on 41 be degraded voltage.
the minimum voltage Dnergency Buses 3 and 4 which are set to actuate at damage of saf ety-related equipment.
required to prevent for 10 seconds, either relay will If Degraded Grid conditions exist Based upon an actuate an alarm to alert operators of this condition.of these conditions the ope disconnect the off-site power.
In addition, if an ESP signal is assessment for initiated in conjunction with low voltage below the relay seepoint the off-site power will be automatically disconnected.
10 seconds, (RCIC) System provides makeup water to Reactor Core Isolation Cooling or replace reactor vessel during shutdown and isolation to supplementthe use of the Emergency C The the the normal makeup sources withoutThe RCIC System is initiated automatically upon rece of a Reactor vessel high water Systems.
reactor vessel low-low water level signal.
However, the system level signal results in shutdown of the RCIC System. reactor vessel low-low water level signal.
on a subsequent suction from the condensate will restart RCIC System is normally lined up to takeSuetion will automatically switch over from t We tank storage tank. tank to the suppression pool on low condensate storage storage level.
Upon receipt of a LOCA initiation signal, if normal AC power is available, all RHR pumps both Core Spray pumps start simultaneously with no intentional time delay. If normal AC power is not available, RHR pumps A and D start immediately on restoration of power, RHR pumps B and C start within 3 to 5 seconds of restoration of power and both Core Spray pumps start within 8 to 10 seconds of restoration of power. The purpose of these time delays is to stagger the star the RHR and Core Spray pumps on the associated Division I and Division 2 Buses, thus limiting the starting transients on the 4.16 kV emergency buses. De time delay functions are only necessary when power is being supplied from the standby power sources (EDGs). The time i
delays remain in the pump start logic at all times as the time delay relay contact is in pa the Auxiliary Power Monitor relay contact. Either contact closure will initiate pump start. Thus, the time delays do not affect low pressure ECCS pump operation with normal AC power available. With normal AC power not available, the pump start relays which would have started j
the B and C RHR pumps and both Core Spray pumps are blocked by the Auxiliary Power Monitor contacts and the pump start time delay relays become the controlling devices.
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1
)
79 Amendment No. 94, 111 f
VERMONT YANKEE NUCLEAR POWER CORPORATION Docket No.50-27i BV'Y 98 18.
, Page 1 of 1 '
ATTACHMENT 4 Revised New Technical Specification Paaae 1
1 i
1
'41 I l'
I l
t
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g p3 TABLE 3.2.1
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EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTAT*ON-i
.i Core Spray - A & B (Note 1)
[
Minimum Number of Required Action When
}
Operable Instrument Minimum Conditions Channels per Trip for Operation System Trip Function Trip Level Setting are Not Satisfied 2
High Drywell Pressure
$2.5 psig-Note 2
[
2 Low-Low Reactor Vessel Water
>82.5" above top of Note 2 Level enriched fuel j
1 Low Reactor Pressure 300 $ P $ 350 psig.
. Note 2 I
(PT-2-3-56C/D(M))
f 2
Low Reactor Pressure 300 $ P $ 350 psig Note 2 (PT-2-3-56A/B(M) & 52C/D(M))
l 1
Pump Start Time Delay 8 $ t $ 10 seconds Note 2 (14A-K16A & B) 2
. Pump (P-46-1A/B) Discharge
>100 psig-Note 5 I
Pressure i
L 1
. Auxiliary Power Monitor Note 5
{
1 Pump Bus Power Monitor Note 5
[
2 Trip System Logic Note 5 5
i
~r i
4 E
i
?
i Amendment No. 44, 68,. 4-14, 4M, 444, -142-38
[
i
l b
VYNPS TABLE a.2.1 (Cont'd)
EMERGENCY CORE COOLING SYSTE.M ACTUATION INSTRUMENTATION Low Pressure Coolant Injection System A & B (Note'1)-
Minimum Number of Required Action When
-[
Operable Instrument Minimum conditions Channels per Trip for Operation System Trip Function Trip Level Setting are Not Satisfied 1
Low Reactor Pressure 300 $ p $ 350 psig Note 2.
(PT-2-3-56C/D(Mi) 2 High Drywell Pressure
$2.5 psig Note 2 1
(PT-10-101A-D(M))
2 Low-Low Reactor Vessel Water 282.5" above top of Note 2 Level enriched fuel 1
Reactor Vessel Shroud Level 22/3 core height Note 5 1
Time Delay (10A-K72A & B)
<60 secands Note 5 t
l 1
Pump-Start Time Delay 3 $ t 3 5 seconds Note 5
~
(10A-K50A & B) 1 Low Reactor Pressure 100 $ p 5 150 psig Note 2 (PS-2-128A & B)
?
2 per pump RHR Pump A & C Discharge 2100 psig Note 5 i
Pressure 2
High Drywell Pressure
$2.5 psig Note 2 3
(PT-10-101A-D(S1))
l Amendment No. 44, 44, 68, 444, 44e 39 i
L I
VYNPS BASES: ' 3.2~ (Cont'd)
The Degraded Grid Protective System has been installed to assure that safety-related electrical equipment will not be subjected to sustained degraded voltage.
This system incorporates voltage relays on 4160 Volt Emergency Buses 3 and 4 which are set to actuate at the minimum voltage required to prevent damage of safety-related equipment.
If Degraded Grid conditions exist for 10 seconds, either relay will actuate an alarm to alert operators of this condition.
Based upon an assessment of these conditions the operator may choose to manually disconnect the off-site power.
In addition, if an ESF signal is initiated in conjunction with low voltage below the relay setpoint for 10 seconds, the off-site power will be automatically disconnected.
The Reactor Core Isolation Cooling (RCIC) System provides makeup water to the
]
reactor vessel during shutdown and isolation to supplement or replace the normal makeup sources without the use of the Emergency Core Cooling Systems.
The RCIC j
System is initiated automatically upon receipt of a reactor vessel low-low we.cer l
level signal.
Reactor vessel high water level signal results in shutdown of the RCIC System. However, the system will restart on a subsequent reactor vessel low-low water level signal.
The RCIC System is normally lined up to take suction from the condensate storage tank.
Suction will automatically switch
['
over from the condensate storage tank to the suppression pool on low condensate storage tank level.
Upon receipt of a LOCA initiation signal, if normal AC power is available, all
)
RHR pumps and both Core Spray pumps start simultaneously with no intentional time delay.
If normal AC power is not available, RHR pumps A and D start immediately on restoration of power, RHR pumps B and C start within 3 to 5 seconds of restoration of power and boch Core Spray pumps statt within 8 to 10 seconds of restoration of power. The purpose of these time delays is to stagger the start of the RHR and Core Spray pumps on the associated Division 1 and 1
Division 2 Buses, thus limiting the starting transients on the 4.16 kV emergency buses. The time delay functions are only necessary when power is being supplied from the standby power sources (EDGs). The time delays remain in the pump start logic at all times as the time delay relay contact is in parallel with the Auxiliary Power Monitor relay contact.
Either contact closure will initiate pump start. Thus, the time delays do not affect low pressure ECCS pump operation with normal AC power available. With normal AC power not available, the pump start relays which would have started the B and C RHR pumps and both Core Spray pumps are blocked by the Auxiliary Power Monitor contacts and the l
pump start time delay relays become the controlling devices.
Amendment No. M, 4M 79