ML20138A806

Proposed Tech Specs,Revising Setpoints for Main Steam Line Radiation Monitor Instruments to Allow Performance of Tests of Hydrogen Injection Into Primary Coolant

ML20138A806
Person / Time
Site:	Hatch
Issue date:	03/07/1986
From:	Beckham J GEORGIA POWER CO.
To:
Shared Package
ML20138A796	List: ML20138A793 ML20138A806
References
TAC-60895, NUDOCS 8603200097
Download: ML20138A806 (6)

Text

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a l

i l Table 3.1-1 (Cont'd) -

)

1

] Scram Operable

. Number Source of Scram Trip Signal Channels Scram Trip Setting Source of Scram Signal is *

(a) Required to be Operable Required Per

- Trip System Except as Indicated Below -

i (b) d b

H 8 .APRM Downscale 2 >3/125 of full scale The APRM downscale trip is

! active only when the Mode j Switch is in RUN. The

. APRM downscale trip is

automatically bypassed when i the IRM instrumentation is. -

i operable and not tripped.

j 15% Flux 2 415/125 of full The APRM 15% Scram is auto-

! scale Tech Spec natically bypassed when the j 2.1.A.1.b. Mode Switch is in the RUN 4

position.

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l 7 9 Main Steam Line Radiation 2 43 times normal Not' required if all steam

Eackground at rated lines are isolated. . g thermal power (c).

4 l 10 Main Steam Line Isolation 4 410% valve closure Automatically bypassed when j Valve Closure Trom full open the Mode Switch is not in

] Tech Spec 2.1.A.S. the RUN position. %e design permits closure of any two

lines without a scram being j initiated.

1 11 Turbine Control Valve 2 Within 30 milli- Automatically bypassed when Fast Closure seconds of the start turbine steam flow is below-of control valve that corresponding to 30% of fast closure rated thermal power as measured Tech Spec 2.1.A.4. by turbine first stage pressure.

kk P

DO h1

Table 3.1-1 (Cont'd) -

Scram Operable Number Source of Scram Trip Signal Channels Scram Trip Setting Source of Scram Signal is (a) Required Per Required to be Operable Trip System Except as Indicated Below h (b)

H w

12 Turbine Stop Valve 4 <10% valve closure Automatically bypassed when Closure from full open turbine steam flow is below

]

Tech Spec 2.1.A.3. that corresponding to 30% of rated thermal power as

^

measured by turbine first ,

j stage pressure. \j j

Notes for Table 3.1-1

.'# a. The column entitled " Scram Number" is for convenience so that a one-to-one relationship can be established

(( between items in Table 3.1-1 and items in Table 4.1-1.

! b. There shall be two operable or tripped trip systems fcr each potential scram signal. If the number of operable channels cannot be met for one of the trip syatems, that trip system shall be tripped. However, i one trip signal channel of a trip system may be inopersble for up to two (2) hours during periods of required surveillance testing without tripping the associated tri.; system, provided that the other remaining channel (s) monitoring that parameter within that trip system is (are) operable.

c. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the planned src-i of the hydrogen injection test with the reactor power at greater ttsn 20% rated power, the normal full power radiation background level and associated trip setpoints may be 6 hanged based on a calculated value of the radiation level expected during the test. The background radiation level and

! associated trip setpoints may be adjusted during the test based on either calculations or measurements of actual.

radiation levels resulting from hydrogen injection. The background radiation level shall be determined

and associated trip setpoints shall be set within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of re-establishing normal radiation levels after

completion of hydrogen injection and prior to establishing reactor power levels below 20% rated power.

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1 Notes for Table 3.1-1 (cont) 1 For SCRAMS 1 thru 7 and 8 APRM 15% Flux, if the number of operable channels is not met for both trip systems;

, initiate insertion of all control rods capable of being moved by control rod drive pressure and complete their insertion within four (4) hours.

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! H For SCRAM 8 (APRM High Trips, Inoperative, and Downscale), if the number of operable channels in not met F" for both trip systems; initiate insertion of all control rods capable of being moved by control rod drive l

pressure and complete their insertion within four hours or reduce power to the IRM range and go to the l START & HOT STANDBY position of the Mode Switch within eight hours.

I j For SCRAMS 9 and 10, if the number of operable channels is not met for both trip systems; reduce turbine load and close main steam line isolation valves within eight hours or initiate insertion of all control rods capable of being moved by control rod drive pressure and complete their insertion within four hours.

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! For SCRAMS 11 and 12, if the number of operable channels is not met for both trip systems, reduce reactor i power to 25% of rated thermal power or less within eight hours.

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RP J ,

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I TABLE 3.2-1 INSTRUMENTATION WlIICH INITIATES REACTOR VESSEL AND PRIMARY -

! CONTAINMENT ISOLATION

, Required

}  % Ref. Trip Operable Action to be taken if H No. Instrument Condition Channels Trip Setting number of channels is

^

b (a) Nomenclature per Trip not met for both trip Remarks (d)

' System (b)

) systems (c) i

g 1 Reactor Vessel Low (level 3) 2 >8.5 inches Initiate an orderly Initiates Group 2 & 6

{ g Water Level Narrow Range shutdown and achieve isolation.

l the Cold Shutdown

, Condition within 24 ,

l hours or isolate the shutdown cooling

! system.

}

} Low Low 2 >-55 inches Initiate an orderly Starts the SGTS, j; (Level 2) shutdown and achieve initiates Group 5 the Cold Shutdown isolation, and i to Condition within 24 initiates j N hours. secondary containment i N isolation.

Low Low Low 2 >-121.5 inches Initiate an orderly Initiates Group 1 l (Level 1) shutdown and achieve isolation.

] the Cold Shutdown Con-

{ dition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

l 2 Reactor Pressure High 1 4135 psig Isolate shutdown Isolates the shutdown j (Shutdown Cooling cooling, cooling suction valves l Mode) of the RHR system, i

< 3 Drywell Pressure. High 2 <2 psig Initiate an orderly Starts the standby shutdown and achieve gas treatment system, i the Cold Shutdown initiates Group 2 i Condition within 24 isolation and second-3 hours, ary containment

! isolation.

l l 4 Main Steam Line High 2 <3 times j Radiation normal full Initiate ca orderly load Initiates Group 1 j power reduction and close MSIVs isolation. l

! background (e) within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. I i

Notes for Table 3.2-1

a. The column entitled "Ref. No." is only for convenience so that a one-to-one relationship can be established between lines in Table 3.2-1 and items in- Table 4.2-1.

i G b. Primary containment integrity shall be maintained at all times prior to withdrawing control rods for the h! pur g

212goseofgoingcritical,whenthereactoriscritical,orwhenthereactorwatertemperatureisabove F and fuel is in the reactor vessel except while performing low power physics tests at atmospheric pressure at power levels not to exceed 5 MWt.

When primary containment integrity is required, there shall be two operable or tripped trip systems for each function.

c. If the number of operable channels cannot be met for one of the trip systems, that trip system shall be tripped. However, one trip signal channel of a trip system may be inoperable for up to two (2) hours during v, periods of required surveillance testing without tripping the associated trip system, provided that the other g, remaining channel (s) monitoring that same parameter within that trip system is (are) operable.

E

d. The valves associated with each Group isolation are given in Table 3.7-1.

e. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the planned start of the hydrogen injection test with the reactor power at greater than 20% rated power, the normal full power radiation background level and associated trip setpoints may be changed based on a calculated value of the radiation level expected during the test. The background radiation level and associated trip setpoints may be adjusted during the test based on either calculations or measurements of actual radiation levels resulting from hydrogen injection. The background radiation level shall be determined and associated trip setpoints shall be set within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of re-establishing normal radiation levels after completion of hydrogen injection and privr to establishing reactor power levels below 20% rated power.

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TABLE 3.2-8 (cont.) $

)

Required g Ref. Trip Operable Action to be taken if

! No. Instrument Condition Channels Trip Setting there are not two operable (a) Nomenclature per Trip or tripped trip systems Remarks j System (b) ll H

e

5. Main Steam Line Hi 2 f,3 times Isolate the mechanical One trip per trip-Radiation Monitor normal full vacuum pump and the logic system will power background gland seal condenser isolate the

(e) exhauster mechanical vacuum l l

pump and the gland seal ~ condenser

exhauster.

l

u

+

'm a. The column entitled "Ref. No." is only for convenience so that a one-to-one relationship can be established 4

ua between items in Table 3.2-8 and items in Table 4.2-8.

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b. Whenever the systems are required to be operable, there shall be two operable or tripped trip systems.

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If this cannot be met, the indicated action shall be taken.

i c. In the event that both off-gas post treatment radiation monitors become inoperable, the reactor shall be j placed in the Cold Shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless one monitor is sooner made operable, or adequate alternative-monitoring facilities are available.

d. From and after the date that one of the two off-gas post treatment radiation monitors is made or found to be inoperable, continued reactor power operation is permissible during the next fourteen days (the allowable repair time), provided that the inoperable monitor is tripped in the downscale position.

e. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the planned start of the hydrogen injection test with the reactor power at greater than 20% rated power, the normal full power radiation background level and associated trip setpoints may be changed based on a calculated value of the radiation level expected during the test. The background radiation level and associated trip setpoints may be adjusted during the test based on either calculations or measurements of actual radiation levels resulting from hydrogen injection. The background radiation level shall be determined and associated trip

setpoints shall be set within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of re-establishing normal radiation levels after completion

of hydrogen injection and prior to establishing reactor power levels below 20% rated power.

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