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Proposed Tech Specs,Incorporating Testing & Surveillance Requirements for Reactor Trip Breakers Per Generic Ltr 85-09
	ML20138F747
Person / Time
Site:	McGuire, Mcguire
Issue date:	12/07/1985
From:	; DUKE POWER CO.
To:	;
Shared Package
ML20138F716	List: ML20138F708; ML20138F747;
References
	GL-85-09, GL-85-9, NUDOCS 8512160162
	Download: ML20138F747 (6)
	v • d • e

_ -

I l

l TABLE 3.3-1 (Continued)

REACTOR TRIP SYSTEM INSTRIDENTATION l

s M

MINIfEM TOTAL NO.

CHANNELS CHAlelELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES-ACTION e

5 d

19.

Reactor Trip Breakers 2

1 2

9 12.

2 1

2 3, 4*, 5*

Id A

r.

E 20.

tic Trip and Interlock 2

1 2

2 g

4*, 5*

0 9A 5

P Y

I.

2.3.

s 8512160162 851207 PDR ADOCK 05000369 P

PDR

.M

ATTAdh* EvT f (courwuch)

TABLE 3.'3-1 (Continued)

ACTION STATEMENTS (Continued)

ACTION 9 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.1.1, provided the other channel is OPERA 8LE.

ACTION 10 - With the number of OPERABLE channels one less than the Minimum Channels JPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or open the Reactor trip breakers within the next hour.

ACTION 11 - With the number of OPERABLE channels less than the Total Number of Channels, operation may continue provided the inoperable channels are placed in the tripped condition within I hour.

ACTION f 2 With one of the diverse trip features (undervoltage or shunt trip attachnent) inoperable, restore it to OPERABLE status within I

48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the breaker inonerable and apply ACT!0ft

' The breaker shall not be bypassed while one of the diverse )rh trip features is inoperable except for the time requircd for perfoming maintenance to restore the breaker to OPERABLE status.

1 McGUIRE - UNITS 1 and 2 3/4 3-8

TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRLSENTATION SURVEILLANCE REQUIRBENTS E

TRIP ANALOG ACTUATING MODES FOR CHANNEL DEVICE WHICH c5 CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE l

l 5

FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST IS REQUIRED Rhl)

N.A.

1, 2, 3*, 4*, S' l

1.

Manual Reactor Trip N.A.

N.A.

N.A..

I a.

m 2.

Power Range, Neutron Flux I

l High Setpoint S

D(2,4),

M N.A.

N.A.

1, 2 l

M(3,4),

Q(4,6),

R(4,5) gg, Low Setpoint 5

R(4)

M N.A.

N.A.

1

,2 w

3..

Power Range, Neutron Flux, N.A.

R(4)

M N.A.

N.A.

1, 2 i

High Positive Rate l

"4 4.

Power Range,- Neutron Flux, N.A.

R(4)

M N.A.

N.A.

1, 2 High Negative Rate 5.

Intermediate Range, S

R(4,5)

S/U(1),M N.A.

N.A.

l

,2 Neutron Flux 6.

Source Range, Neutron Flux 5

R(4,5)

S/U(1),M(9)

N.A.

N. A.'

2, 3, 4, 5 7.

Overtemperature AT S

R M

N.A.

.1, 2 b !

8.

Overpower AT S

R M

N.A.

1, 2 I

QoS) 9.

Pressurizer Pressure--Low S

R M

N.A.

1 10.

Pressurizer Pressure--High S

R H

N.A.

1, 2 g

11. Pressurizer Water Level--High 5

R M

N.A.

I dR E.$

12.

Low Reactor Coolant Flow 5

R M

N.A.

1 C. 7 Gi

(> q v

d xg TA8LE 4.3-1 (Continued)

E REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREENTS e

' " TRIP e

ANALOG ACTUATING MODES FOR m

CHANNEL DEVICE idHICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST IS REQUIRED m

d.

Low Setpoint Power Range Neutron Flux, P-10 N.A.

R(4)

M (8)

N.A.

1, 2 e.

Turbine Impulse Chamber Pressure, P-13 N.A.

R M (8)

N.A.

M.A.

1 17 19.

Reactor Trip Breaker N.A N.A.

N.A.

M (7,2i)

N.A.

1, 2, 3*, 4*, 5*

R

20. Automatic Trip and y

Interlock Logic N.A.

N.A.

)

N.A.

M (7) 1, 2, 3*, 4*, 5*

U O

mb b

O r

t. '

c 9

W h$Yl (cwrWveo)

TABLE 4.3-1 (Continued)

TA8LE NOTATION With the Reactor Trip System breakers closed and the Control Rod Drive System capable of rod withdrawal.

N Below P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.

M Below P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.

1 (1) -

If not performed in previous 7 days.

(2)

Comparison of calorimetric to excore power indication above 15% of RATED THERMAL POWER.

Adjust excore channel gains consistent with calorimetric power if absolute difference is greater than 2%.. The provisions of Specification 4.0.4 are not applicable for entry into MDDE 2 or 1.

(3)

Single point comparison of incore to excore axial flux difference above 15% of RATED THERMAL POWER.

Recalibrate if the absolute difference is greater than or equal to 3%.

The provisions of Specification 4.0.4 are not appitcable for entry into MODE 2 or 1.

(4)

Neutron detectors may be excluded from CHANNEL' CALIBRATION.

(5)

Detector plateau curves shall be obtained, evaluated, and compared

, to manufacturer's data.

For the Intermediate Range and Power Range Neutron Flux channels the provisions of Specification 4.0.4 are not t

l applicable for entry into MODE 2 or 1.

l (6)

Incore - Excore Calibration, above 75% of RATED THERMAL POWER.

The provisions of Specification 4.0.4 are not applicable for entry into i

MODE 2 or 1.

(7)

Each train shall be tested at least every 62 days on a STAGGERED TEST BASIS.

(8)

With power greater than or equal to the interlock Setpoint the required operational test shall consist of verifying that the interlock is in the required state by observing the permissive l

annunciator window.

t (9)

Monthly surveillance in MODES 3*, 4* and 5* shall also include

(

verification that permissives P-6 and P-10 are in their required l

state for existing plant conditions by observation of the permissive l

annunciator window.

Monthly surveillance shall include verification 1

of the Baron Dilution Alarm Setpoint of less than or equal to five times background.

l (10) -

'Setpoint verification is not required.

2

.McGUIRE - UNITS 1 and 2 3/4 3-14 l

~TA&E 4.3 - 1 (counnusb ) @@"'*9 j

Tl4 BLG IUOTA7'lO/O (11)-

The TRIP ACTUATING DEVICE OPERATIONAL TEST shall independently verify i

the OPERASILITY of the undervoltane tnd shunt trip cinuits for the Menval Reactor Trip Function.

(12) -

The TRIP ACTUATING DEVICE OPERATI0flAL TEST shall independently verify the OPERABILITY of the undervoltane and shunt trip attachments of the Reactor Trip Breakers.

t i

fic6vinc -dvnS inas t 3/',3-p/q y

- - -

ML20138F747

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