Text

Proposed Tech Specs,Modifying Setpoint for Enabling Anticipatory Reactor Trip Upon Turbine Trip from Greater than 10% to 30% Reactor Power
	ML20235P607
Person / Time
Site:	Byron, Braidwood, 05000000
Issue date:	09/30/1987
From:	; COMMONWEALTH EDISON CO.
To:	;
Shared Package
ML20235P553	List: ML20235P550; ML20235P607;
References
	NUDOCS 8710070324
	Download: ML20235P607 (11)
	v • d • e

1

+

LIMITING SAFETY SYSTEM SETTINGS I

(

i BASES

)

Turbine Trio oc p-8 hp.7) or 30*4(P-Bh A Turbine trip initiates a Reactor trip.

On decreasing power the Turbine.

trip is automatically blocked by P-7 a power level of approximately 105 of RATED THERMAL POWER with a turbine impulse chamber pressure at approxima t

10%Aof full power equivalent); and ~on increasing power,. reinstated automatically F-by P-7er P-8 1

-[oe 30*/e(P-8)

Safety Injection Input from ESF If a Reactor trip has not.already been generated by the Reactor Trip.

1 System instrumentation, the ESF automatic actuation. logic channels will initiate a Reactor trip upon any signal which initiates a. Safety Injection.

The ESF instrumentation channels which initiate a Safety Injection signal are shown in Table 3.3-3.

Reactor Coolant Pump Breaker Position Trio l

e The Reactor Coolant Pump Breaker Position trips are anticipatory trips

(

which provide core protection against DNB.

The-Open/Close Position'. trips l

s assure a Reactor trip signal is generated before the Low Flow Trip Setpoint is reached.

No credit was taken in the accident analyses for operation of these 4

trips.

Their functional capability at the open/close position settings is required to enhance the overall reliability of tha Reactor Trip System.

Above P-7 (a power level of approximate 1y'10% of RATED THERMAL POWER or a turbine 1

impulse chamber pressure at approximately 10% of full power equivalent) an automatic Reactor trip will occur if more than one reactor coolant pump breaker is opened.

Below P-7 the trip function is automatically blocked.

i l

l l

l 8710070324 870930 DR ADOCK 050 4

l

A Reocher trip on Torhine. tvip is enabled above. P-7 (Io%) until the.

rnochRcaNow i s IMP cmenkd which enables R eacitv trip on Turbine _

i l

-M p above. T'- 8 ( 3o%).

-SYRON - UNITS 1 & 2 B 2 _ ______ _ --

i 1

+

LIMITING SAFETY SYSTEM SETTINGS b

BASES i

Reactor Trip System Interlocks t

The Reactor Trip System Interlocks perform the following functions:-

1 P-6 On increasing power, P-6 allows the manual block of the Source Range

{

Reactor trip (i.e., prevents premature block of Source Range trip),-

l provides an automatic backup block for Source Range Neutron Flux i

l doubling, and the manual block that de-energizes the high voltage to i

l the Source Range detectors.

On decreasing power, Source Range Level trips and Neutron Flux doubling circuits are automatically reactivated and high voltage restored.

P-7 On increasing power, P-7 automatically enables Reactor trips on low flow in more than one reactor coolant loop, more_ than one reactor.

coolant pump breaker open, reactor coolant pump bus undervoltage and underfrequency, Turbine trip, pressurizer low pressure and i

pressurizer high level.

On decreasing power, the above listed trips are automatically blocked.

fond Turbine.+ rip 3 P-8 On increasing power, P-8 automatically ' enables Reactor trips on iow flow 'in one or more reactor coolant loop On decreasing power, the P-8 automatically blocks the single loop {} low flow tripow,,d 7'vebi b

(

l

+ri p.

P-10 On increasing power, P-10 allows the manual block of the Intermediate Range Reactor trip and the Low Setpoint Power Range Reactor trip; and automatically blocks the Source Range Reactor trip and provides an automatic backup function to de-energize the Source Range high voltage power.

On decreasing power, the Intermediate Range Reactor trip and the Low Setpoint Power Range Reactor trip are automatically reactivated and Source Range high voltage to the detectors is restored if power decreases below the P-6 setpoint.

Provides input to P-7..

P-13 Provides input to P-7.

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A Rcodor trip on Twbine Mp d enaW d above. P-7 Me) Uhtil

%e. rnodiRcabow is implernenRd which enaWes Readw trip

(

on TLebine_ trip cibove. P-8 ( 30%).

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' LIMITING SAFETY SYSTEM' SETTINGS.~

t3 j

s BNSES kurbineTrip#

or P-7)

'(P-7 or;30 *4 (P-8N.."

A Turbine trip initiates a Reactor trip.

On decreasing power the Turbine trip.is automatically blocked by P-7i(a power level of approximately 10%[o'f

,i RATED THERMAL POWER with a turbine impulse chamber pressure at approximately 10 of fell power equivalent); and on increasing power, reinstated automatically i '

(P-7)_Py7or P-8,or 30% (P-8),

y l

l Safety Injection Input from ESF i

If a Reactor trip has not already been generated by the Reactor Trip 4

System instrumentation, the ESF automatic actuation logic _ channels will i

initiate a Reactor trip upon any signal which initiates a Safety Injection..

sThe ESF. instrumentation channels which initiate a Safety Injection signal are i

lshowninTable3.3-3.

j t 'l l

].

i t

1 p g actor Coolant Pump' Breaker Position Trip

\\

/

i The Reactor Coolant Pump Breaker Position trips are anticipatory trips

{

l l'

i which provide core protection against DNB.

The Open/Close Position trips i

assure a Reactor trip signal is generated before the Low Flow Trip Setpoint is

}

i 9

reached.

No credit was taken in the accident analyses for operation of these

{

l trips.

Their functional capability at the open/close position settings-is l

3 s'

3 required to enhance the overall reliability of the Reactor Trip System.

Above

+

P-7 (a power level of approximately 10% of RATED THERMAL POWER or a turbine j

q,-

2 l

ll,-

impulse chamber pressure at approximately 10% of full power equivalent) an l'y automatic Reactor trip will occur if more than one reactor coolant pump breaker L.

is opened.

Below P-7 the trip function is automatically blocked.

l l

1 l

i I

A Readoc 4de on M"' 4d? is enabled above : P-7 [lD *bh u n4il 4Le-sodi[icafien is Wp/mented wfici enn6/c5 Reacler 4 rip on Tur}ine-frip Move-p. 8- (30%),

ERAIDWOOD - UNITS 1 & 2 B 2 %

4 g MITING SAFETY SYSTEM SETTINGS BASES Reactor Trip System Interlocks The Reactor Trip System Interlocks perform the following functions:

P-6 On increasing power, P-6 allows the manual block of the Source Range f

Reactor trip (i.e., prevents premature block of Source Range trip),

provides an automatic backup block for Source Range Neutron Flux doubling, and the manual block that de-energizes the high voltage to the Source Range detectors.

On decreasing power, Source Range Level trips and Neutron Flux doubling circuits are automatically reactivated and high voltage restored.

n increasing power, P-7 automatically enables Reactor trips on low

{

P-7 0

flow in more than one reactor coolant loop, more than one reactor coolant pump breaker open, reactor coolant pump bus undervoltage and underfrequency, Turbine trip, pressurizer low pressure and pressurizer high level.

On decreasing power, the above listed trips are automatically blocked.

g

n increasing power, P-8 automatically enables Reactor trips on low P-8 0

flow in one or more reactor coolant loops On decreasing power, the l

P-8 automatically blocks the single loop low flow tripand Thrb,ne-l

+r i P.

P-10 On increasing power, P-10 allows the manual block of the Intermediate l

Range Reactor trip and the Low Setpoint Power Range Reactor trip; and automatically blocks the Source Range Reactor trip and provides an 1

automatic backup function to de-energize the Source Range high voltage power.

On decreasing power, the Intermediate Range Reactor trip and the Low Setpoint Power Range Reactor trip are automatically reactivated and Source Range high voltage to the detectors is restored if power decreases below the P-6 setpoint.

Provides input to P-7.

P-13 Provides input.to P-7.

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s enabkct above. P-7 60 /d unfil N A Reac[or drip on Ter Lnc. fr/

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+he nodi 0edlen is inpleutnied which enables l}eac 4e, f7;p on Lbine hip abouc. P-8 GO % ),

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i ATTACHMENT C-1 EVALUATION OF SIGNIFICANT HAZARDS CONSIDERATION I

d commonwealth Edison has evaluated this proposed amendment and determined that it involves no significant hazards consideration. According to 10 CPR 50.92(c), a proposed amendment to an operating license involves no significant hazards consideration if operation of the facility in accordance with the amendment would not:

)

I 1)

Involve a significant increase in the probability or consequences j

l of an accident previously evaluated; or j

l I

2)

Create the possibility of a new or different kind of accident from any accident previously evaluated; or l

3)

Involve a significant reduction in a margin of safety.

1

)

This amendment involves a modification to revise the setpoint at which the anticipatory reactor trip following turbine trip is enabled. A change in a setpoint to enable an anticipatory reactor trip that is not taken credit for in any accident analysis does not affect the probability or consequences of previously evaluated accidents.

This amendment will have the effect that turbine trips below 30%

power will no longer result in an anticipatory reactor trip. A turbine trip I

from 100% power without an anticipatory reactor trip has already been analyzed. This is the same event initiated from a more severe condition.

As a result, operation of the plant in accordance with this amendment will not create the possibility of a new or different kind of accident.

l As previously demonstrated in the accident analysis for a turbine trip from 100% power, margins of safety are provided by the functioning of the reactor protection system, pressurizer safety valves and steam generator safety valves. This modification does not affect those features.

Therefore, this modification results in no reduction in a margin of safety.

For the reasons stated above, Commonwealth Edison believes this 3

proposed amendment involves no significant hazarde consideration, l

3654K

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ML20235P607

Text

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