ML20138F747

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)

Text

_ - _

I l

l TABLE 3.3-1 (Continued)

! REACTOR TRIP SYSTEM INSTRIDENTATION s

l M MINIfEM TOTAL NO. CHANNELS CHAlelELS APPLICABLE OF CHANNELS TO TRIP OPERABLE MODES- ACTION

, e FUNCTIONAL UNIT 5

d 19. Reactor Trip Breakers 2 1 2 1 2 9 12.

r. 2 1 2 3A , 4*, 5* Id tic Trip and Interlock 2 1 2 2 E 20. g 4*, 5* 0 9

A 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 <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 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  ; 1 perfoming maintenance to restore the breaker to OPERABLE status.

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 c CHANNEL DEVICE WHICH l

5 CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE l

5 FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST IS REQUIRED Manual Reactor Trip N.A.. N.A. 1, 2, 3* , 4* , S' l a.

1. N.A. N.A. Rhl)

I I m 2. Power Range, Neutron Flux 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. N.A. .1, 2 1, 2 b !

8. Overpower AT S R M N.A. N.A. ,

I

9. Pressurizer Pressure--Low S R M N.A. N.A. 1

10. Pressurizer Pressure--High S R H N.A. N.A. 1, 2 QoS) g

11. Pressurizer Water Level--High 5 R M N.A. N.A. I dR N.A. N.A.

E.$

C. 7

12. Low Reactor Coolant Flow 5 R M 1 Gi

- (> q v

d x

g TA8LE 4.3-1 (Continued)

E REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREENTS e

e ' " TRIP ACTUATING MODES FOR m

ANALOG 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. 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. N.A. M (7) 1, 2, 3*, 4*, 5*

U O

mb b O r

t. '

c 9

W h$Yl TABLE 4.3-1 (Continued)

(cwrWveo)

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.

1. 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 t

Neutron Flux channels the provisions of Specification 4.0.4 are not 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 j) @@"'*9 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

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