ML19347D002

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Revised Tech Specs Re Limiting Safety Sys Settings
ML19347D002
Person / Time
Site: Farley Southern Nuclear icon.png
Issue date: 03/04/1981
From:
ALABAMA POWER CO.
To:
Shared Package
ML19347D001 List:
References
NUDOCS 8103100502
Download: ML19347D002 (1)


Text

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LIMITING SAFETY SYSTEM SETTINGS -

BASES through the pressurizer safety valves. No credit was taken for operation of this trip in the accident analyses; however, its functional capability at the specified trip setting is required by this specification to enhance the overall reliability of the Raactor Protection System.

  • Loss of Flow _

The Loss of Flow trips provide core protection to prevent DNB in the event of a loss of one or more reactor coolant pumps.

Above 10 percent of RATED THERMAL POWER, an automatic reactor trip will occur if the flow in any two loops drop below 90% of nominal full loop flow. Above 36% (P-8) of RATED THERMAL POWER, autecatic reactor trip will occur if the flow in any single loop drops below 90% of ,

nominal full loop flow.

of the DNBR from going below This+rE+

latter tripnormal during will prevent-the minicum operational transients value. '5F l and anticipated transients whe loops are in operation and the Overtemperature AT trip set poi t is adjusted to the value specified for all loops in operation. With th Overtemperature aT trip set point adjusted to the value specified or 2 loop operation, the P-8 trip at 66% RATED THERMAL POWER will revent the minimum value of the DNBR from going below +P3+ ring nor 1 operational transients and antici- 1 pated transients with . s in peration.

Steam Generator Water Level The Steam Generator Water Level Low-Low trip provides core protec-tion by preventing operation with the steam generator water level below the minimum volume required for adequate heat removal capacity. The specified setpoint provides allowance that there will be sufficient water inventory in the steam generators at the time of trip to allow for starting delays of the auxiliary feedwater system.

Steam /Feedwater Flow Mismatch and Low Steam Generator WEter Level The Steam /Feedwater Flow Mismatch in coincidence with a Steam Generator low Water Level trip is not used in the transient and accident analyses but is included in Table 2.2-1 to ensure the functional caca- 1 bility of the specified trip settings and thereby enhance the overall M elosio ose-FARLEY -' UNIT-1 B 2-6

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