ML20133C321
| ML20133C321 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 09/30/1985 |
| From: | YANKEE ATOMIC ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20133C318 | List: |
| References | |
| NUDOCS 8510070315 | |
| Download: ML20133C321 (4) | |
Text
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a-f ATTACHMENT A l
Summary of Technical Specifi(ation Changes Delete The Following Pages Insert The Following Pages 2-6 2-6 B 2-5 B 2-5 3/4 3-14 3/4 3-14 pse"PeitB"sa'"ggg' L
t
!ll A
$y TABLE 2.2-1 (continued)
REACTOR PROTECTIVE SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT TRIP SETPOINT 8.
High Main Coolant System Pressure 1 2300 psig 9.
Low Main Coolant System Pressure 1 1800 psig 10.
High Pressurizer Water Level 1 200 inches 11.
Low Steam Generator Water Level 1 - 13"*
[
12.
Turbine Trip Not Applicable 13.
Generator Trip Not Applicable 14.
Main Steam Isolation Trip Logic 1 262.5 psig 1
s ao.
g
- Where O inches corresponds to 10" above the feed ring centerline.
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n 4
LIMITING SAFETY SYSTEM SETTINGS BASES Steam Generator Water Level The Low steam Generator Water Level trip provides core protection by preventing operation with the steam generator water level below the minimum volume required for adequate heat removal capacity.
Th'e specified setpoint provides allowance that there will be sufficient water inventory in the steam generators at the time of trip to provide 15 minutes, as assumed in the accident analysis, for starting delays of the emergency feedwater system.
Turbine and Generator Trip A Turbine or Generator Trip causes a direct reactor trip when operating above 15 MWe.
Each of the turbine trips provide turbine protection and reduce the severity of the ensuing transient. No credit was taken in the accident analyses for operation of these trips. Their functional capability is required to enhance the overall reliability of the Reactor Protection System.
Main Steam Isolation Trip A Main Steam Isolation Trip closes the main steam line noneeturn valves and causes a direct reactor trip. This trip reduces the severity of,the cooldown and the ensuing transient effects resulting from a main steam line break. This trip also serves to assure the availability of a secondary system heat sink following a seismic event, until the Safe Shutdown System is available to provide feedwater to the steam generators.
Its functional capability enhances the overall reliability of the Reactor Protection System.
Main Coolant System High pressure The Main Coolent System High Pressure Trip is provided to ensure protection against main coolant system overpressurization caused by a loss of 1.oad incident.
Its functional capability enhances the overall reliability of the Reactor Protection System.
YANKEE-ROWE B 2-5 Amendment No. 89
TABLE 3.3-3 ENGINEERED SAFEGUARDS SYSTEM INSTRUMENTATION TRIP SETPOIETS FUNCTIONAL UNIT TRIP SETPOINT 1.
SAFETY INJECTION a.
Actuation Channel # 1
- 1) RPS Low Main Coolant -
Loop 1 Pressuro Channel 2 1700 psig
- 2) High Containment Pressure Sensor s 5 psig
- 3) Manual Initiation Not Applicable b.
Actuation Channel # 2
- 1) RPS Low Main Coolant -
Loop 2 Pressure Channel 1 1700 psig
- 2) High Containment Pressure Sensor S 5 psig
- 3) Manual Initiation Not Applicable 2.
CONTAINMENT ISOLATION a.
Manual Initiation Not Applicable b.
Actuation Channel A
- 1) High Containment Pressure Sensor s 5 psig
- 2) Safety Injection (All Safety Injection Setpoints) c.
Actuation Channel B
- 1) High Containment Pressure Sensor s 5 psig
- 2) Safety Injection (All Safety Injection Setpoints) 3.
MAIN STEAM ISOLATION a.
Low Steam Line Pressure 1 262.5 psig b.
Automatic Trip Logic Not Applicable c.
Manual Initiation Not Applicable d.
High Containment Pressure Trip
. containment Isolation s 5 psig Amendment No. % [ M ff' YANKEE-ROWE 3/4 3-14 L