ML20205T176

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Proposed Tech Specs,Reflecting Mod to Core Spray Sparger Differential Pressure Instrumentation Alarm Setpoints
ML20205T176
Person / Time
Site: Hatch  Southern Nuclear icon.png
Issue date: 03/27/1987
From:
GEORGIA POWER CO.
To:
Shared Package
ML20205T140 List:
References
TAC-65248, TAC-65249, NUDOCS 8704070230
Download: ML20205T176 (2)


Text

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Table 3.2-6 E INSTRUMENTATION WillCH INITIATES OR CONTROLS CORE SPRAY Re r. Instrument Trip Hequired T rip Setting Remarks

~ No. Condition Ope rab l e (a) Nomenc1ature ChanneIs per Trip 4

System (b)

1. Reactor Vessel Wa te r Leve l Low Low Low 2-113 inches initiates CS.

(tevel 1) 2

2. Drywe l l Pressure High 2 11.92 psig Initiates CS. Also initiates HPCI and LPCI mode of RHR and provides a permissive signal to ADS.
3. Reactor Vessel Steam Dome Low 2 2422 psig* Permissive to open CS Pres su re injection va lves.
4. Core Spray Sparger 1(*8 5 3.1 psid Monitors integrity of CS Di rre rent ia l Pressure greater ( less piping inside vessel (between

' negative) than the nozzle and core shroud).

the normal 00 indicated AP at rated core power

'm and flow, a

Z 5. CS Pump Discha rge Flow Low 1 2610 gpm Minimum flow bypass line is (2 4.13 inches) closed when low flow signal i s not present.

6. Core Spray Logic Power 1 Not Applicable Monitors availability of fa ilure Monitor power to logic system.
  • This trip runction shall be 5500 psig.
a. The column entitled "Ref. No." is only for convenience so that a one-to-one relationship can be established between items in Table 3.2-6 and items in Table 4.2-6.

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O b. Whenever any CCCS subsystem is required to be operable by Section 3.5, there shall be two operable trip 3 systems. If the required number or operable channels cannot be met for one of the trip systems, that sys tem sha l l be repa i red o r the reac to r sha l l be placed in the Cold Shutdown Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> y after this trip system is made or round to be inoperable, c.

c. Ala rm only. When inoperable, verify that the core spray dirrerential pressure is within limits at least once per d 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or, declare. the associated cos e spray loop i nope ra b le, o

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  • Jh R 8704070230 870327 g PDR ADOCM 05000321 g P PDR

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o EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

! 2. Performing a CHANNEL CALIBRATION of the core. spray header AP instrumentation and verifying the set point to be s 3.1 psid greater (less negative) than the normal indicated AP at rated core power and flow.

d. At least once per 18 months by performing a system functional test which includes simulated automatic actuation of the system throughout its emergency operating sequence and veri-fying that each automatic valve in the flow path actuates to its correct position. Actual injection of coolant into the reactor vessel may be excluded from this test.

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HATCH - UNIT 2 3/4 5-6 Proposed TS/0094q/86-XX 4

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