Text

Amends 106 & 99 to Licenses NPF-2 & NPF-8,respectively, Incorporating Changes Allowing Longer STIs & AOTs for RTS & ESFAS Instrumentation Into TSs
	ML20069A075
Person / Time
Site:	Farley
Issue date:	05/16/1994
From:	Bateman W; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20069A077	List: ML20069A075; ML20069A079;
References
	NUDOCS 9405240234
	Download: ML20069A075 (50)
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UNITED STATES NUCLEAR REGULATORY COMMISSION n

h WASHINGTON, D. C. 20555

.,o SOUTHERN NUCLEAR OPERATING COMPANY. INC.

DOCKET NO. 50-348 JOSEPH M. FARLEY NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.106 License No. NPF-2 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Southern Nuclear Operating Company, Inc., dated October 14, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR.Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications, as indicated in the attachment to this license amendment; and paragraph 2.C.(2) of Facility Operating License No.

NPF-2 is hereby amended to read as follows:

9405240234 940516 PDR ADOCK 05000348 P

PDR

. (2)

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.106, are hereby incorporated in the license.

Southern Nuclear Operating Company, Inc., shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION h

William H. Bateman, Director Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: May 16, 1994

ATTACHMENT TO LICENSE AMENDMENT N0.106 IQ FACILITY OPERATING LICENSE N0. NPF-2 DOCKET N0. 50-348 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.

Remove Paaes Insert Paagi 3/4 3-4 3/4 3-4 3/4 3-5 3/4 3-5 3/4 3-6 3/4 3-6 3/4 3-7 3/4 3-7 3/4 3-8 3/4 3-8 3/4 3-9 3/4 3-9 3/4 3-12 3/4 3-12 3/4 3-13 3/4 3-13 3/4 3-16 3/4 3-16 3/4 3-17 3/4 3-17 3/4 3-19 3/4 3-19 3/4 3-20 3/4 3-20 3/4 3-21 3/4 3-21 3/4 3-22 3/4 3-22 3/4 3-23 3/4 3-23 3/4 3-24 3/4 3-24 3/4 3-33 3/4 3-33 3/4 3-34 3/4 3-34 3/4 3-35 3/4 3-35 3/4 3-36 3/4 3-36 3/4 3-37 3/4 3-37 B3/4 3-1 B3/4 3-1

TABLE 3.3-1 (Continued)

REACTOR TRIP SYSTEM IMTRUMENTATION E

MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION Z

17.

Turbine Trip A.

Low Auto Stop 011 Pressure 3

2 2

1 7#

B.

Turbine Throttle Valve 4

4 1

1 6#

l Closure 18.

Safety Injection Input from ESF 2

1 2

1, 2 15 l

19.

Reactor Coolant Pump Breaker Position Trip A.

Above P-8 1/ breaker 1

1/ breaker 1

10 B.

Above P-7 1/ breaker 2.

1/ breaker 1

118 R

per oper-ating loop 20.

Reactor Trip System Interlocks A.

Intermediate Range Neutron Flux, P-6 2

1 2

2, and*

8 B.

Low Power Reactor Trips Block, P-7 P-10 Input 4

2 3

1 8

P-13 Input 2

1 2

1 8

C.

Power Range Neutron Flux, P-8 4

2 3

1 8

M-5 D.

Power Range Neutron M

Flux, P-10 (Input to P-7) 4 2

3 1, 2 8

'i E.

Turbine Impulse Chamber z

Pressure,~P-13 2

1 2

1 8

3 F.

Power Range Neutron g

Flux, P-9 4

2 3

1 8

cn

- - - ~

a e.

TABLE 3.3-1 (Continued) 5 EE REACTOR TRIP SYSTEM INSTRUMENTATION h

e 25 MINIMUM

-d TOTAL NO.

CHANNELS CHANNELS APPLICABLE

~~

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

21. Reactor Trip Breakers 2

1 2

1, 2 1, 14 3*,

4*, 5*

13

22. Automatic Trip Logic 2

1 2

1, 2 15 l

3*, 4*, 5*

13 w

Jm u,

t 5

Ezb 5

L

TABLE 3.3-1 (Continued)

+

TABLE NOTATION With the reactor trip system breakers in the closed position, the control rod drive system capable of rod withdrawal, and fuel in the reactor vessel.

The channel (s) associated with the protective functions derived from the out of service Reactor Coolant Loop-shall be placed in the tripped condition.

The provisions of Specification 3.0.4 are not applicable.

1. High voltage to detector may be de-energized above P-6.

Indication only.

1. 1. 1. The provisions of Specification 3.0.3 are not applicable if THERMAL POWER level 2: 10% of RATED THERMAL POWER.

ACTION STATEMENTS ACTION 1 - With the number of OPERABLE channels one less than required by the Minimum Channels OPERABLE requirement, be in 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.

ACTION 2 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a.

The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

l b.

The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for l

surveillance testing of the other channels per Specification 4.3.1.1.

c.

Either, THERMAL PC'ER is restricted to less than or equal to 75%

of RATED THERMAL POWER and the Power Range Neutron Flux trip setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; or, the QUADRANT POWER TILT RATIO from the remaining 3 detectors is monitored at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months per Specification 4.2.4.2.

FARLEY-UNIT 1 3/4 3-6 AMENDMENT N0. p 106

4 TABLE 3.3-1 (Continued)

ACTION 3 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

a.

Below the P-6 (Block of Source Range Reactor Trip) setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER-above the P-6 setpoint.

b.

Above the P-6 (Block of Source Range Reactor Trip) setpoint, but below 5% of RATED THERMAL POWER, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above 5% of RATED THERMAL POWER.

c.

Above 5% of RATED THERMAL POWER, POWER OPERATION may continue.

ACTION 4 - With the number of OPERABLE channels one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

a.

Below the P-6 (Block of Source Range Reactor Trip) setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 setpoint.

b.

Above the P-6 (Block of Source Range Reactor Trip) setpoint, operation may continue.

ACTION 5 - With the number of OPERABLE channels one less than required by the Minimum Channels OPERABLE requirement, verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 or 3.1.1.2, as applicable, within I hour and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

ACTION 6 - 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 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 7 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

1 a.

The inoperable channel is placed in the tripped condition l

within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and b.

The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of other channels per Specification 4.3.1.1.

FARLEY-UNIT 1 3/4 3-7 AMENDMENT NO. EE.106

TABLE 3.3-1 (Continued)-

ACTION 8 - With the interlock inoperable to the extent that a reactor trip which should not be blocked in the current MODE is blocked, declare the trip function inoperable and follow the ACTION statements of Table 3.3-1 for the affected channel (s).

Interlock Affected Channels on Table 3.3-1 1.

P-6 a.

Source Range, Neutron Flux Startup Shutdown 2.

P-7 a.

Low Reactor Coolant Loop Flow (2 loops) b.

Undervoltage - Reactor Coolant Pumps c.

Underfrequency - Reactor Coolant Pumps d.

Pressurizer Low Pressure e.

Pressurizer High Level 3.

P-8 a.

Low Reactor Coolant Loop ' Flow (1 loop) 4.

P-9 a.

Turbine Trip 5.

P-10 a.

Intermediate Range, Neutron Flux b.

Power Range, Neutron Flux - Low Setpoint c.

Source Range, Neutron Flux Startup Shutdown d.

P-7 (Item 2 above) 6.

P-13 a.

P-7 (Item 2 above)

ACTION 9 - With a channel associated with an operating loop inoperable, restore the inoperable channel to OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months l

or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel associated with an operating loop may be bypassed for up to 4 l

hours for surveillance testing per Specification 4.3.1.1.

ACTION 10 - With one channel inoperable, restore the inoperable channel to OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or reduce THERMAL POWER to below l

the P-8 (Low Reactor Coolant Pump Flow and Reactor Coolant Pump Breaker Position) setpoint within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . Operation below the P-8 (Low Reactor Coolant Pump Flow and Reactor Coolant Pump Breaker Position) setpoint may continue pursuant to ACTION 11.

FARLEY-UNIT 1 3/4 3-8 AMENDMENT N0. E,106

TABLE 3.3-1 (Continued)

. ACTION 11 - With less than the Minimum Number of Channels OPERABLE, operation may continue provided the inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

l ACTION 12 - With the number of OPERABLE channels one less than required by the Minimum Channels OPERABLE 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 be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 13 - With the number of OPERABLE channels one less than required by the Minimum Channels OPERABLE 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 System breakers within the next hour.

ACTION 14 - With one of the diverse trip features (undervoltage or shunt trip attachment) inoperable, the breaker may be considered OPERABLE provided that the diverse trip feature is restored to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , or declare the breaker inoperable and apply ACTION 1.

The breaker shall not be bypassed while one of the diverse trip features is inoperable except for the time required for performing maintenance to restore the breaker to OPERABLE status.

ACTION 15 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or be in at least HOT STANDBY within the next 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 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.1.1, provided the other channel is OPERABLE.

FARLEY-UNIT 1 3/4 3-9 AMENDMENT NO. 26,E/,106-

^

TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REOUIREMENTS CHANNEL h0 DES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE m

3'; FUNCTIONAL UNIT CHECK CALIBRATION TEST REOUIRED R

f

1. Manual Reactor Trip N.A.

N.A.

R(ll),

1, 2 S/U(1)(12) 3*, 4*, 5*

EQ

2. Power Range, Neutron Flux A.

High S

D(2), M(3)

Q 1, 2 l

and Q(6)

B.

Low S

D(2),M(3)

S/U(10) 2 and Q(6)

3. Power Range, Neutron Flux, High N.A.

R(6)

Q 1, 2 l

Positive Rate

4. Power Range, Neutron Flux, High N.A R(6)

Q 1, 2 l

g Negative Rate Y

5. Intermediate Range, Neutron S

R(6)

S/U(10)

'1, 2 and l

C Flux

6. Source Range, Neutron Flux S(7)

R(6)

Q and S/U(10) 2, 3, 4, l

5, and *

7. Overtemperature AT S

R Q

1, 2

8. Overpower A T S

R Q

1, 2 5

9. Pressurizer Pressure--Low S

R Q

l M5

10. Pressurizer Pressure--High S

R Q

1, 2

11. Pressurizer Water Level--High S

R Q

1 g

12. A.

Loss of Flow - Single Loop S

R Q

1 E;

B.

Loss of Flow - Two Loops S

R N.A.

I

m TABLE 4.3-l'(Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUfREMENTS 4

CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL-SURVEILLANCE j FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED' A

< 13. Steam Generator Water Level--

S R

Q 1, 2 l

1 Low-Low C

% 14. Steam /Feedwater Flow Mismatch S

R Q

1, 2 l

and Low Steam Generator Water

~

Level

15. - Undervoltage - Reactor Coolant N.A.

R Q

l l

Pumps

16. Underfrequency - Reactor N.A.

R Q

l l

Coolant Pumps

17. Turbine Trip A.

Low Auto Stop 011 Pressure N.A.

R S/U(9)(10)

N.A.

g B.

Turbine Throttle Valve N.A.

R S/U(9)(10)

N.A.

Closure 18.. Safety Injection Input from ESF N.A.

N.A.

R(4) 1, 2 l_

l

19. Reactor Coolant Pump Breaker N.A.

N.A.

R 1

i Position Trip

20. Reactor Trip System Interlocks N.A.

R S/U(8) 1

21. Reactor Trip Breaker.

N.A.

M(5)(14)(15),

1, 2, S/U(1)(14)(15) 3*,

4*, 5*

3 22. Automatic Trip Logic N.A.

N.A.

M(5) 1,, 2, E

3*,

4*, 5*-

5 E' 23._ Reactor' Trip Bypass Breaker N.A.

N.A.

(13), R(11) 1, 2, 3*,

4*, 5*

3 C

e,-

i

,,=

m

. M ~ '. e

TABLE 3.3-3 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION E

MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE si FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION C

1.

SAFETY INJECTION, TURBINE TRIP AND FEE 0 WATER ISOLATION a.

Manual Initiation 2

1 2

1,2,3,4 18 b.

Automatic Actuation 2

1 2

1,2,3,4 13 Logic c.

Containment 3

2 2

1,2,3 19*

Pressure--High jd d.

Pressurizer 3

2 2

1, 2, 3#

19*

Pressure--Low w

e.

Differential 1, 2, 3 Pressure Between Steam Lines--High Three Loops 3/ steam line 2/ steam line 2/ steam line 19*

l Operating twice and 1/3 steam lines

1. 1. steam 2/ operating 15 Two Loops

_3/ operating 2

/

Operating steam line line twice steam line gj in either

@j operating gj steam line

'i 5

L

TABLE 3.3-3 (Continued) jj ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION E

-c 4:

MINIMUM 5

TOTAL NO.

CHANNELS CHANNELS APPLICABLE

-[

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION f.

Steam Line Pressure--Low 1, 2, 388 Three Loops 1 pressure /

1 pressure 1 pressure 19*

l Operating loop any 2 loops any 2 loops Two Loops 1 pressure /

1### pressure 1 pressure 15 Operating loop in any oper-any operating ating loop loop 2.

CONTAINMENT SPRAY w

a.

Manual 2

1 2

1,2,3,4 18 2

b.

Automatic Actuation 2

1 2

1, 2, 3, 4 13 to' Logic c.

Containment Pressure--

4 2

3 1,2,3 16 High-High-High 3E 5xb 5

~,-.

G

a TABLE 3.3-3 (Continuedl ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION g; -

g MINIMUM

. TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION E

1_

4.

' STEAM LINE ISCLATION a.

Manual 1/ steam line 1/ steam line 1/ operating 1,

2**, 3**

22 steam line b.

Automatic 2

1 2

1, 2**, 3**

21 Actuation Logic c.

. Containment Pressure--

3 2

2 1,

2**, 3**

19*

l High-High d.

Steam Flow in Two 1,

2**, 3**

2d.

Steam Lines--High s

ja Three Loops 2/ steam line 1/ steam line 1/ steam line 19*

l Operating any 2 steam lines

1. 1. any 1/ operating 15 Two Loops 2/ operating l

/

Operating steam line operating steam line steam line COINCIDENT WITH

-Tavg--Low-Low 1,

2**, 3**

. l[

Three Loops 1 Tavg/ loop 1 Tavg any.

1 Tavg any 19*

l Operating 2 loops 2 loops se 5E 5;.

[l Two Loops 1 Tavg/oper-18## Tavg 1 Tav in any_

15 c)

Operating ating loop in any oper-operakingloop ating loop

. in L

Ia El

TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEAi'JRE ACTUATION SYSTEM INSTRUMENTATION g;

MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO 1 RIP OPERABLE MODES ACTION C

e.

Steam Line Pressure--

1, 2**, 388,**

low Three loops 1 pressure /

1 pressure 1 pressure 19*

l Operating loop any 2 loops any 2 loops Two Loops 1 pressure /

1888 pressure 1 pressure 15 Operating operating in any oper-any operating loop ating loop loop 5.

TURBINE TRIP &

FEEDWATER ISOLATION w

32 a.

Steam Generator 3/ loop 2/ loop in 2/ loop in 1, 2 19*

l y>

Water Level--

any oper-each oper-g>

High-High ating loop ating loop I

m 5

L s

TABLE 3.3-3 (Continued) 32 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION ie

[2 MINIMUM J:

TOTAL NO.

CRANNELS CHANNELS APPLICABLE g

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 6.

AUXILIARY FEEDWATER a.

Automatic Actuation logic 2

1 2

1,2,3 21 b.

Stm. Gen. Water Level--Low-Low i.

Start Motor-Driven Pumps 3/stm. gen.

2/stm. gen.

1, 2, 3 19*

l any stm. gen.

w ii.

Start Turbine-lt Driven Pumps 3/stm. gen.

2/stm. gen.

1, 2,,

3 19*

l any 2 stm. gen.

4 u2 m

c.

Undervoltage-RCP Start Turbine-Driven Pump 3-2/ bus 2

2 1

19 l

d.

S.I.

Start Motor-Driven Pumps See 1 above (all S.I. initiating functions and requirements) e.

Trip of Main Feedwater Pumps 3E Start Motor-Driven Pumps

'2/pum')

1/ pump 1/ pump 1

23*

E2 5

E

.s m

TABLE 3.3-3 (Continued) g ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION Q

MINIMUM J-TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 7.

LOSS OF POWER

~

a.

4 kv Bus 3/ Bus 2/ Bus 2/ Bus 1, 2, 3, 4 24*

l Loss of Voltage b.

Grid Degraded Voltage 3/ Bus 2/ Bus 2/ Bus 1, 2, 3, 4 24*

l 8.

ENGINEERED-SAFETY FEATURE ACTUATION SYSTEM INTERLOCKS a.

Pressurizer Pressure, 3

2 2

1,2,3 20 P-ll wi b.

Low-Low Tavg, P-12 3

2 2

1,2,3 20 c.

Steam Generator (See 5.a above)

Level, P-14 d.

Reactor Trip, P-4 2

1 2

1, 2, 3 13 3E hs 5

E; e

TABLE 3.3-3 (Continued)

TABLE NOTATION

Trip function may be bypassed in this MODE below the P-ll (Pressurizer Pressure Block of Safety Injection) setpoint.

1. Trip function may be bypassed in this MODE below P-12 (T Block of avg Safety Injection) setpoint.

1. 1. The channel (s) associated with the protective functions derived from the out of service Reactor Coolant Loop shall be placed in the tripped mode.

The provisions of Specification 3.0.4 are not applicable.

Not applicable if main steam isolation valves are closed.

ACTION STATEMENTS ACTION 13 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ; however, one channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.2.1 provided the other channel is OPERABLE.

ACTION 14 - Deleted.

l ACTION With a channel associated with an operating loop inoperable, restore the inoperable channel to OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months l

or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel associated with an operating loop may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.2.1.

l ACTION 16 - With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed provided the inoperable channel is placed in the bypassed condition and the Minimum Channels OPERABLE requirement is met; one additional channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification l

4.3.2.1.

ACTION 17 - With less than the Minimum Channels OPERABLE, operation may continue provided the containment purge and exhaust valves are maintained closed.

ACTION 18 - With the number of OPERABLE Channels one less than the Minimum Channels OPERABLE 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 be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

FARLEY-UNIT 1 3/4 3-23 AMENDMENT N0. 4,106.

3 3

TABLE 3.3-3 (Continued)

ACTION 19 - With the number of OPERABLE Channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied;

a. The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and l

b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for l

surveillance testing of other channels per Specification 4.3.2.1.

ACTION 20 - With the interlock inoperable to the extent that a safeguards function which should not be blocked in the current MODE is blocked, declare the safeguard function (s) inoperable and follow the appropriate ACTION statement (s) of Table 3.3-3 for the affected function (s).

Interlock Affected Channels on Table 3.3-3 1.

P-ll a.

Pressurizer Pressure--Low 2.

P-12 a.

Steam Line Pressure--Low b.

Steam flow in Two Steam Lines High Coincident with T

--LOW-LOW avg ACTION 21 - With the number of OPERABLE Channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least H0T SHUTDOWN within the following 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 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing providej the other channel is OPERABLE.

ACTION 22 - With the number of OPERABLE Channels one less than the Total Number of Channels 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 be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 23 - With the number of OPERABLE Channels one less than the Minimum Number of Channels, operation may proceed until performance of the next required CHANNEL FUNCTIONAL TEST.

ACTION 24 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a.

The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and b.

The Minimum Channel OPERABLE requirement is met; however, the inoperable 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 of other channels per Specification 4.3.2.1.

FARLEY-UNIT 1 3/4 3-24 AMENDMENT NO. 33,106

TABLE 4.3-2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION

~

SURVEILLANCE REOUIREMENTS 5

ie CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE EE FUNCTIONAL UNIT CHECK CALIBRATION TEST REOUIRED w

1.

SAFETY INJECTION, TURBINE TRIP AND FEEDWATER ISOLATION a.

Manual Initiation N.A.

N.A.

R(1) 1, 2, 3, 4 l

b.

Automatic Actuation Logic N.A.

N.A.

M(2) 1, 2, 3, 4 c.

Containment Pressure--High S

R Q

1, 2, 3 l

d.

Pressurizer Pressure--Low S

R Q

1, 2, 3 l

e.

Differential Pressure S

R Q

1, 2, 3 l

[

Between Steam Lines--High w

f.

Steam Line Pressure--Low S

R Q

1,2,3 l

2.

CONTAINMENT SPRAY a.

Manual Initiation N.A.

N.A.

R(1) 1, 2, 3, 4 l

b.

Automatic Actuation Logic N.A.

N.A.

M(2) 1, 2, 3, 4 c.

Containment Pressure--

S R

Q 1, 2, 3 l

l High-High-High E9 5

L

4 TABLE 4.3-2 (Continued) h ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS g

g MODES IN WHICH q

CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK.

CALIBRATION TEST REQUIRED 3.

CONTAINMENT ISOLATION a.

Phase "A" Isolation

1) Manual N.A.

N.A.

R(1) 1, 2, 3, 4 l

2) From Safety Injection N.A N.A.

M(2) 1, 2, 3, 4 Automatic Actuation Logic b.

Phase "B" Isolation g

{

1) Manual N.A.

N.A.

R(1) 1, 2, 3, 4 l

^

2) Automatic Actuation N.A.

N.A.

M(2) 1, 2, 3, 4 Logic

3) Containment Pressure--

S R

Q 1,2,3 l

High-High-High c.

Purge and Exhaust Isolation

1) Manual N.A.

N.A.

R(1) 1, 2, 3, 4 l

1

2) Automatic Actuation Logic N.A.

N.A.

M(2) 1, 2, 3, 4 E

5 L.

e TABLE 4.3-2 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS A

CHANNEL MODES IN WHICH E

CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE Z

FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED 4.

STEAM LINE ISOLATION a.

Manual N.A.

N.A.

R(1) 1, 2, 3 l

b.

Automatic Actuation Logic N.A.

N.A.

M(2) 1, 2, 3 c.

Containment Pressure--

S R

Q 1, 2, 3 l

High-High d.

Steam Flow in Two Steam S

R Q

1, 2, 3 l

R Lines--High Coincident with

[

T

--l0W-l0" avg b

e.

Steam Line Pressure--Low S

R Q

1, 2, 3 l

5.

TURBINE TRIP AND FEEDWATER ISOLATION a.

Steam Generator Water S

R Q

1, 2, 3 l

Level--High-High E9 E

E 5

L.

O-

TABLE 4.3-2 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS g-ie0 CHANNEL MODES IN WHICH E

CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE Z

FUNCTIONAL UNIT CHECK CALIBRATION TEST REOUIRED

~

6.

AUXILIARY FEEDWATER a.

Automatic Actuation Logic N.A.

N.A.

M(2)(6) 1, 2, 3 b.

Steam Generator Water S

R Q

1,2,3 l

Level--Low-Low c.

Undervoltage - RCP N.A.

R Q

1 l

d.

S.I.

See 1 above (all SI surveillance requirements) e.

Trip of Main Feedwater N.A.

N.A.

S/U(5) 1 Pumps a

7.

LOSS OF POWER a.

4.16 kv Emergency Bus N.A.

R(3)

M(4) 1, 2, 3, 4 Undervoltage (Loss of Voltage) b.

4.16 kv Emergency Bus N.A.

R(3)

M(4) 1, 2, 3, 4 Undervoltage (Degraded g

Voltage) 5 8.

ENGINEERED SAFETY FEATURE N.A.

R N.A.

N.A.

l l

ACTUATION SYSTEM INTERLOCKS a

b i

h m

i

TABLE 4.3-2 (Continued)

TABLE NOTATION (1)

Manual actuation switches shall be tested at least once per 18 months during shutdown.

l (2)

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

(3)

Channel calibration shall exclude actuation of the final trip actuation relay.*

(4)

Functional testing shall consist of verification of relay operation upon removal of input voltage and operation of 2-out-of-3 logic excluding the final trip actuation relay.*

(5)

If not performed in the previous 92 days.

(6)

Excluding automatic actuation logic for trip of main feedwater pumps.

Actuation of the final trip actuation relay shall be included in response time testing.

FARLEY UNIT 1 3/4 3-37 AMENDMENT N0. 76,106

1/4.3 INSTRUMENTATION

~

BASES 3/4.3.1 and 3/4.3.2 REACTOR TRIP SYSTEM and ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION The OPERABILITY of the Reactor Trip and Engineered Safety Feature Actuation System instrumentation and interlocks ensures that 1) the associated Engineered Safety Feature Actuation action and/or reactor trip will be initiated when the parameter monitored by each channel or combination thereof reaches its setpoint,

2) the specified coincidence logic and sufficient redundancy is maintained to permit a channel to be out of service for testing or maintenance consistent with maintaining an appropriate level of reliability of the Reactor Trip System and Engineered Safety Feature Actuation System instrumentation and, 3) sufficient system functional capability is available for protective and ESF purposes from diverse parameters.

The OPERABILITY of these systems is required to provide the overall reliability, redundancy and diversity assumed available in the facility design for the protection and mitigation of accident and transient conditions.

The integrated operation of each of these systems is consistent with the assumptions used in the accident analyses. The surveillance requirements specified for these systems ensure that the overall system functional capa-bility is maintained comparable to the original design standards.

The periodic surveillance tests performed at the minimum frequencies are sufficient to demonstrate this cap bil ity.

Specified surveillance intervals and surveillance and maintenance outage times have been determined in accordance with WCAP-10271, " Evaluation of Surveillance Frequencies and Out of Service Times for the Reactor Protection Instrumentation System," and supplements to that report as approved by the NRC and documented in the SERs and SSER (letters to J. J. Sheppard from Cecil 0.

Thomas dated February 21, 1985; Roger A. Newton from Charles E. Rossi dated February 22, 1989; and Gerard T. Goering from Charles E. Rossi dated April 30, 1990).

The Engineered Safety Feature Actuation System interlocks perform the l

functions indicated below on increasing the required parameter, consistent with the setpoints listed in Table 3.3-4:

P-11 Defeats the manual block of safety injection actuation on low pressurizer pressure.

P-12 Defeats the manual block of safety injection actuation on low steam line pressure.

P-14 Trip of all feedwater pumps, turbine trip, closure of feedwater isolation valves and inhibits feedwater control valve modulation.

On decreasing the required parameter the opposite function is performed at reset setpoints, with the exception of P-12 as noted below:

P-12 Allows manual block of safety injection actuation on low steam line pressure. Causes steam line isolation on high steam. flow. Affects steam dump blocks (i.e.,

prevents premature block of the noted function).

FARLEY-UNIT 1 B 3/4 3-1 AMENDMENT N0.2E,106 a

f o nao UNITED STATES

o

~

1 NUCLEAR REGULATORY COMMISSION f

,E WASHINGTON, D. C. 20555 SOUTHERN NUCLEAR OPERATING COMPANY. INC.

DOCKET NO. 50-364 JOSEPH M. FARLEY NVCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 99 License No. NPF-8 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Southern Nuclear Operating Company, Inc., dated October 14, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The _ issuance of this license amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 ef the Comission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications, as indicated in the attachment to this license amendment; and paragraph 2.C.(2) of Facility Operating License No. NPF-8 is hereby amended to read as follows:

. (2)

Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 99, are hereby incorporated in the license. Southern Nuclear Operating Company, Inc., shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

[

William H. Bateman, Director Project Directorate 11-1 Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: May 16, 1994

&TTACHMENT TO LICENSE AMENDMENT NO. 99 TO FACILITY OPERATING LICENSE NO. NPF-8 DOCKET NO. 50-364 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are' indicated by marginal lines.

Remove Paaes Insert Paaes 3/4 3-4 3/4 3-4 3/4 3-5 3/4 3-5 3/4 3-6 3/4 3-6 3/4 3-7 3/4 3-7 3/4 3-8 3/4 3-8 3/4 3-9 3/4 3-9 3/4 3-12 3/4 3-12 3/4 3-13 3/4 3-13 3/4 3-16 3/4 3-16 3/4 3-17 3/4 3-17 3/4 3-19 3/4 3-19 3/4 3-20 3/4 3-20 3/4 3-21 3/4 3-21 3/4 3-22 3/4 3-22 3/4 3-23 3/4 3-23 3/4 3-24 3/4 3-24 3/4 3-33 3/4 3-33 3/4 3-34 3/4 3-34 3/4 3-35 3/4 3-35 3/4 3-36 3/4 3-36 3/4 3-37 3/4 3-37 B3/4 3-1 B3/4 3-1 l

i i

j l

TABLE 3.3-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION E

MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION Z

17.

Turbine Trip co A.

Low Auto Stop 011 Pressure 3

2 2

1 7#

B.

Turbine Throttle Valve 4

4 1

1 68 l

Closure

18. Safety Injection Input from ESF 2

1 2

1, 2 15 l

19. Reactor Coolant Pump Breaker Position Trip A.

Above P-8 1/ breaker 1

1/ breaker 1

10 B.

Above P-7 1/ breaker 2

1/ breaker 1

118 el per oper-ating loop 20.

Reactor Trip System Interlocks A.

Intermediate Range Neutron Flux, P-6 2

1 2

2, and*

8 B.

Low Power Reactor Trips Block, P-7 P-10 Input 4

2 3

1 8

P-13 Input 2

1 2

1 8

C.

Power Range Neutron g

Flux, P-8 4

2 3

1 8

b D.

Power Range Neutron y

Flux, P-10 (Input to P-7) 4 2

3 1, 2 8

l E.

Turbine Impulse Chamber 2

Pressure, P-13 2

1 2

1 8

l E

F.

Power Range Neutron Flux, P-9 4

2 3

1 8

m

TABLE 3.3-1 (Continued) 9 E2 REACTOR TRIP SYSTEM INSTRUMENTATION 9

C 25 MINIMUM

-d TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 21.

Reactor Trip Breakers 2

1 2

1, 2 1, 14 3*,

4*, 5*

13

22. Automatic Trip Logic 2

1 2

1, 2 15 l

3*,

4*, 5*

13 w

y, u,

5 5

5 la r

m m m..

a

a TAGLE 3.3-1 (Continued)

TABLE NOTATION With the reactor trip system breakers in the closed position, the control rod drive system capable of rod withdrawal, and fuel in the reactor vessel.

The channel (s) associated with the protective functions derived from the out of service Reactor Coolant Loop-shall be placed in the tripped condition.

5 The provisions of Specification 3.0.4 are not applicable.

1. High voltage to detector may be de-energized above P-6.

1. 1. Indication only.

1. 1. 1. The provisions of Specification 3.0.3 are not applicable if THERMAL POWER level 2: 10% of RATED THERMAL POWER.

ACTION STATEMENTS ACTION 1 - With tiie number of OPERABLE channels one less than required by the Minimum Channels OPERABLE requirement, be in 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.

ACTION e - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a.

The inoperable channel is placed in the tripped condition within j

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , l

1 b.

The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for l

surveillance testing of the other channels per Specification 4.3.1.1.

1 c.

Either, THERMAL POWER is restricted to less than or equal to 75%

of RATED THERMAL POWER and the Power Range Neutron Flux trip setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER within 4 hour:;; or, the QUADRANT POWER TILT RATIO from.the remaining 3 detectors is monitored at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months per i

Specification 4.2.4.2.

FARLEY-UNIT 2 3/4 3-6 AMENDMENT N0. E2,99

TABLE 3.3-1 (Continued)

ACTION 3 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

a.

Below the P-6 (Block of Source Range Reactor Trip) setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER.above the P-6 setpoint.

b.

Above the P-6 (Block of Source Range Reactor Trip) setpoint, but below 5% of RATED THERMAL POWER, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above 5% of RATED THERMAL POWER.

c.

Above 5% of RATED THERMAL POWER, POWER OPERATION may continue.

ACTION 4 - With the number of OPERABLE channels one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

a.

Below the P-6 (Block of Source Range Reactor Trip) setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 setpoint.

b.

Above the P-6 (Block of Source Range Reactor Trip) setpoint, operation may continue.

ACTION 5 - With the number of OPERABLE channels one less than required by the Minimum Channels OPERABLE requirement, verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 or 3.1.1.2, as applicable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

ACTION 6 - 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 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 7 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

l a.

The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and b.

The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of other channels per Specification 4.3.1.1.

FARLEY-UNIJ 2 3/4 3-7 AMENDMENT N0. 99

I TABLE 3.3-1 (Continued)

ACTION 8 - With the interlock inoperable to the extent that a reactor trip which should not be blocked in the current MODE is blocked, declare the trip function inoperable and follow the ACTION statements of Table 3.3-1 for the affected channel (s).

Interlock Affected Channels on Table 3.3-1 1.

P-6 a.

Source Range, Neutron Flux Startup Shutdown 2.

P-7 a.

Low Reactor Coolant Loop Flow (2 loops) b.

Undervoltage - Reactor Coolant Pumps c.

Underfrequency - Reactor Coolant Pumps d.

Pressurizer Low Pressure e.

Pressurizer High Level 3.

P-8 a.

Low Reactor Coolant Loop Flow (1 loop) 4.

P-9 a.

Turbine Trip j

5.

P-10 a.

Intermediate Range, Neutron Flux b.

Power Range, Neutron Flux - Low Setpoint j

c.

Source Range, Neutron Flux Startup Shutdown d.

P-7 (Item 2 above) 6.

P-13 a.

P-7 (Item 2 above)

ACTION 9 - With a channel associated with an operating loop inoperable, restore the inoperable channel to OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months l

or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel associated with an operating loop may be bypassed for up to 4 l

hours for surveillance testing per Specification 4.3.1.1.

ACTION 10 - With one channel inoperable, restore the inoperable channel to OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or reduce THERMAL POWER to below l

the P-8 (Low Reactor Coolant Pump Flow and Reactor Coolant Pump Breaker Position) setpoint within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

Operation below the P-8 (Low Reactor Coolant Pump Flow and Reactor Coolant Pump Breaker Position) setpoint may continue pursuant to ACTION 11.

FARLEY-UNIT 2 3/4 3-8 AMENDMENT NO. 99

.o" TABLE 3.3-1 (Continued)

ACTION 11 - With less than the Minimum Number of Channels OPERABLE, operation may continue provided the inoperable channel'is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

l ACTION 12 - With the number of OPERABLE channels one less than required by the Minimum Channels OPERABLE requirement, restore the innperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , or be in HOT STANDBY within the next-6 hours.

ACTION 13 - With the number of OPERABLE channels one less than required by the Minimum Channels OPERABLE 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 System breakers within the next hour.

ACTION 14 - With one of the diverse trip features (undervoltage or shunt trip attachment) inoperable, the breaker may be considered OPERABLE provided that the diverse trip feature is restored to OPERABLE status within 4B hours, or declare the breaker inoperable and apply ACTION 1.

The breaker shall not be bypassed while one of the diverse trip features is inoperable except for the time required for performing maintenance to restore the breaker to OPERABLE status.

ACTION 15 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to i

OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or be in at least HOT STANDBY j

within the next 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 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.1.1, provided the other channel is OPERABLE.

1 i

~1 FARLEY-UNIT 2 3/4 3-9 AMENDMENT NO. E9,99

TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATICN SURVEILLANCE REOUIREMENTS CHANNEL MODES IN WHICH t

CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE

->y FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED t

1. Manual Reactor Trip N.A.

N.A.

R(11),

1, 2 l

S/U(1)(12) 3*, 4*, 5*

E I

Z

2. Power Range, Neutron Flux t

~

A.

High S

D(2), M(3)

Q 1, 2 l

and Q(6)

B.

Low S

D(2), M(3)

S/U(10) 2 and Q(6)

3. Power Range, Neutron Flux, High N.A.

R(6)

Q 1, 2 l

Positive Rate

4. Power Range, Neutron Flux, High N.A R(6)

Q 1, 2 l

t Negative Rate a

i'

5. Intermediate Range, Neutron S

R(6)

</U(10)

'1, 2 and l

C Flux

6. Source Range, Neutron Flux S(7)

R(6)

Q and S/U(10) 2, 3, 4, l

5, and *

7. Overtemperature AT S

R Q

1, 2

8. Cverpower AT S

R Q

1, 2

!:2 M

S R

Q l

s

9. Pressurizer Pressure--Low 5

10. Pressurizer Pressure--High S

R Q

1, 2 h

11. Pressurizer Water Level--High S

R Q

l

12. A.

Loss of Flow - Single Loop S

R Q

l h_

B.

Loss of Flow - Two Loops S

R N.A.

1

~

TABLE 4.3-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE S

FUNCTIONAL UNIT CHECK CALIBRATION TEST

_ REQUIRED m

7 13. Steam Generator Water level--

S R

Q 1, 2 l

Low-Low cz Z

14. Steam /Feedwater Flow Mismatch S

R Q

1, 2 l

and low Steam Generator Water N

level

15. Undervoltage - Reactor Coolant N.A.

R Q

l l

Pumps

16. Underfrequency - Reactor N.A.

R Q

l l

Coolant Pumps

17. Turbine Trip A.

Low Auto Stop 011 Pressure N.A.

R S/U(9)(10)

N.A.

B.

Turbine Throttle Valve N.A.

R S/U(9)(10)

N.A.

Closure m,

U

18. Safety Injection Input from ESF N.A.

N.A.

R(4) 1, 2 l

19. Reactor Coolant Pump Breaker N.A.

N.A.

R 1

Position Trip

20. Reactor Trip System Interlocks N.A.

R S/U(8) 1'

21. Reactor Trip _ Breaker N.A.

N.A.

M(5)(14)(15),

1, 2, S/U(1)(14)(15) 3*,

4*, 5*

4g

22. Automatic Trip Logic N.A.

N.A.

M(5) 1, 2, 3*,

4*,.5*

a45

23. Reactor Trip Bypass Breaker N.A.

N.A.

(13), R(11) 1, 2, g

3*, 4*, 5*

e

i.

TABLE 3.3-3 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION i2 2

MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE si FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

[

1.

SAFETY INJECTION, TURBINE TRIP AND FEEDWATER ISOLATION a.

Manual Initiation 2

1 2

1, 2, 3, 4 18 b.

Automatic Actuation 2

1 2

1,2,3,4 13 Logic c.

Containment 3

2 2

1, 2, 3 19*

Pressure--High if d.

Pressurizer 3

2 2

I, 2, 3#

19*

Pressure--Low

-w h;

e.

Differential 1, 2, 3 Pressure Between Steam Lines--High Three Loops 3/ steam line 2/ steam line 2/ steam line 19*

l Operating twice and 1/3 steam lines 888 steam 2/ operating 15 Two Loops 3/ operating 2

/

Operating steam line line twice steam line h

in either

@g operating Eg steam line 5

5 i8 q

TABLE 3.3-3 (Continued) 9 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION F

'2 J-MINIMUM 5

TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION f.

Steam Line Pressure--Low 1, 2, 3##

Three Loops 1 pressure /

1 pressure 1 pressure 19*

l l

Operating loop any 2 loops any 2 loops Two Loops I pressure /

1### pressure I pressure 15 Operating loop in any oper-any operating ating loop loop 2.

CONTAINMENT SPRAY a,

Manual 2

1 2

1,2,3,4 18 w

b.

Automatic Actuation 2

1 2

1,2,3,4 13 w'

Logic c.

Containment Pressure--

4 2

3 1, 2, 3 16 High-High-High E

5 2

5

TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION f;

MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION Eq 4.

STEAM LINE ISOLATION m

a.

Manual 1/ steam line 1/ steam line 1/ operating 1,

2**, 3**

22 steam line b.

Automatic 2

1 2

1, 2**, 3**

21 Actuation Logic c.

Containment Pressure--

3 2

2 1,

2**, 3**

19*

l High-High d.

Steam Flow in Two 1, 2* *, 3 *

R Steam Lines--High a

y Three Loops 2/ steam line 1/ steam line 1/ steam line 19*

l g

Operating any 2 steam lines 8ff any 1/ operating 15 Two Loops 2/ operating 1

/

Operating steam line operating steaia line steam line COIWCIDENT WITH Tavg--Low-Low 1,

2**, 3**

k Three Loops 1 Tavg/ loop 1 Tavg any 1 Tavg any 19*

l g

Operating 2 loops 2 loops x

9

[

Two Loops 1 Tavg/oper-l### Tavg 1 Tav in any 15

,o

' Operating ating loop-in any oper-operakingloop ating loop m_

TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION E

p; MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION E

q e.

Steam Line Pressure--

1, 2**, 3##,**

low n3 Three Loops 1 pressure /

1 pressure 1 pressure 19*

l Operating loop any 2 loops any 2 loops Two Loops 1 pressure /

18## pressure 1 pressure 15 Operating operating in any oper-any operating loop ating loop loop 5.

TURBINE TRIP &

FEEDWATER ISOLATION a.

Steam Generator 3/ loop 2/ loop in 2/ loop in 1, 2 19*

l id Water Level--

any oper-each oper-E; High-High ating loop ating loop 999 5

h

TABLE 3.3-3 (Continued) 32 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION E

E2 MINIMUM E:

TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 6.

AUXILIARY FEEDWATER a.

Automatic Actuation Logic 2

1 2

1, 2, 3 21 b.

Stm. Gen. Water Level--Low-Low

i. Start Motor-Driven Pumps 3/stm. gen.

2/stm. gen.

1, 2, 3 19*

l any stm. gen.

11. Start Turbine-w 12 Driven Pumps 3/stm. gen.

2/stm. gen.

1,,2, 3

19*

l 3,

any 2 stm. gen.

ro c.

Undervoltage-RCP Start Turbine-Driven Pump 3-2/ bus 2

2 1

19 l

d.

S.I.

Start Motor-Driven Pumps See 1 above (all S.I. initiating functions and requirements) e.

Trip of Main Feedwater Pumps 3E Start Motor-9 Driven Pumps 2/ pump 1/ pump 1/ pump 1

23*

E E

5 i

TABLE 3.3-3 (Continued) 32 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION P

C2 MINIMUM E:

TOTAL NO.

CHANNELS CHANNELS APPLICABLE

{}

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ___

ACTION 7.

LOSS OF POWER a.

4 kv Bus 3/ Bus 2/ Bus 2/ Bus 1, 2, 3, 4 24*

l Loss of Voltage b.

Grid Degraded Voltage 3/8us 2/ Bus 2/ Bus 1, 2, 3, 4 24*

l j

8.

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INTERLOCKS a.

Pressurizer Pressure, 3

2 2

1, 2, 3 20 P-11 m1 b.

Low-Low Tavg, P-12 3

2 2

1, 2, 3 20 "3

c.

Steam Generator (See 5.a above)

Level, P-14 d.

Reactor Trip, P-4 2

1 2

1, 2, 3 13 i

d 5

x$

5

TABLE 3.3-3 (Continued)

TABLE NOTATION

Trip function may be bypassed in this MODE below the P-Il (Pressurizer Pressure Block of Safety Injection) setpoint.

1. Trip function may be bypassed in this MODE below P-12 (T Block of avg Safety Injection) setpoint.

1. 1. The channel (s) associated with the protective functions derived from the out of service Reactor Coolant Loop shall be placed in the tripped mode.

The provisions of Specification 3.0.4 are not applicable.

Not applicable if main steam isolation valves are closed.

ACTION STATEMENTS ACTION 13 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or be in H0T STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ; however, one channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.2.1 provided the other channel is OPERABLE.

ACTION 14 - Deleted.

l ACTION 15 - With a channel associated with an operating loop inoperable, restore the inoperable channel to OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months l

or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel associated with an operating loop may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.2.1.

l ACTION 16 - With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed provided the inoperable channel is placed in the bypassed condition and the Minimum Channels OPERABLE requirement is met; one additional channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification l

4.3.2.1.

ACTION 17 - With less than the Minimum Channels OPERABLE, operation may continue provided the containment purge and exhaust valves are maintained closed.

ACTION 18 - With the number of OPERABLE Channels one less than the Minimum Channels OPERABLE 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 be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

FARLEY-UNIT 2 3/4 3-23 AMENDMENT N0. U,99

T' TABLE 3.3-3 (Continued)

ACTION 19 - With the number of OPERABLE Channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and l

b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for l

surveillance testing of other channels per Specification 4.3.2.1.

ACTION 20 - With the interlock inoperable to the extent that a safeguards function which should not be blocked in the current MODE is blocked, declare the safeguard function (s) inoperable and follow the appropriate ACTION statement (s) of Table 3.3-3 for the affected function (s).

Interlock Affected Channels on Table 3.3-3 1.

P-ll a.

Pressurizer Pressure--Low 2.

P-12 a.

Steam Line Pressure--Low b.

Steam Flow in Two Steam Lines High Coincident with T

--LOW-LOW avg ACTION 21 - With the number of OPERABLE Channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or be in at least HOT-STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 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 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing provided the other channel is OPERABLE.

ACTION 22 - With the number of OPERABLE Channels one less than the Total Number of Channels 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 be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 23 - With the number of OPERABLE Channels one less than the Minimum Number of Channels, operation may proceed until performance of the next required CHANNEL FUNCTIONAL TEST.

ACTION 24 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

)

a.

The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and b.

The Minimum Channel 0PERABLE requirement is met; however, the inoperable 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 of other channels per Specification 4.3.2.1.

FARLEY-UNIT 2 3/4 3-24 AMENDMENT NO. N,99

~.

TABLE 4.3-2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REOUIREMENTS 5

~'

CHANNEL liODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE E

FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED

~

1.

SAFETY INJECTION, TURBINE TRIP AND FEEDWATER ISOLATION a.

Manual Initiation N.A.

N.A.

R(1) 1, 2, 3, 4 l

b.

Automatic Actuation Logic N.A.

N.A.

M(2) 1, 2, 3, 4 c.

Containment Pressure--High S

R Q

1, 2, 3 l

d.

Pressurizer Pressure--Low S

R Q

1, 2, 3 l

e.

Differential Pressure S

R Q

1, 2, 3 l

Between Steam Lines--High f.

Steam Line Pressure--Low S

R Q

1, 2, 3 l

2.

CONTAINMENT SPRAY a.

Manual Initiation N.A.

N.A.

R(1) 1, 2, 3, 4 l

b.

Automatic Actuation Logic N.A.

N.A.

M(2) 1, 2, 3, 4 c.

Containment Pressure--

S R

Q 1, 2, 3 l

g, c,

High-High-High 6

'i 5

TABLE 4.3-2 (Continued)

A ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION g

SURVEILLANCE REQUIREMENTS E

MODES IN WHICH Q

CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED m

3.

CONTAINMENT ISOLATION a.

Phase "A" Isolation

1) Manual N.A.

N.A.

R(1) 1, 2, 3, 4 l

2) From Safety Injection N.A N.A.

M(2) 1, 2, 3, 4 Automatic Actuation Logic b.

Phase "B" Isolation g

1) Manual N.A.

N.A.

R(1) 1, 2, 3, 4 l

2) Automatic Actuation N.A.

N.A.

M(2) 1, 2, 3, 4 Logic

3) Containment Pressure--

S R

Q 1, 2, 3 l

High-High-High c.

Purge and Exhaust Isolation

1) Manual N.A.

N.A.

R(1) 1, 2, 3, 4 l

E

2) Automatic Actuation Logic N.A.

N.A.

M(2) 1, 2, 3, 4 9

5 V

~.

TABLE 4.3-2 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION gg SURVEILLANCE REQUIREMENTS

?O CHANNEL MODES IN WHICH EE CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE El FUNCTIONAL UNIT CHECK CALIBRATION TEST REOUIRED m

4.

STEAM LINE ISOLATION a.

Manual N.A.

N.A.

R(1) 1, 2, 3 l

b.

Automatic-Actuation Logic N.A.

N.A.

M(2) 1, 2, 3 c.

Containment Pressure--

S R

Q I, 2, 3 l

High-High d.

Steam Flow in Two Steam S

R Q

1, 2, 3 l

lf Lines--High Coincident with

((

T,yg--Low-Low I

e.

Steam Line Pressure--Low S

R Q

1, 2, 3 l

5.

' TURBINE TRIP AND FEEDWATER ISOLATION a.

Steam Generator Water S

R Q

1, 2, 3 I

Level--High-High N

E

%?

E 5

~

TABLE 4.3-2 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS

)

iB

'2 CHANNEL MODES IN WHICH Ei CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE 1

FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED fV 6.

AUXILIARY FEEDWATER a.

Automatic Actuation Logic J.A.

N.A.

M(2)(6) 1, 2, 3 b.

Steam Generator Water S

R Q

1, 2, 3 l

Level--Low-Low c.

Undervoltage - RCP N.A.

R Q

l l

d.

S.I.

See 1 above (all SI surveillance requirements) s*

e._

Trip of Main Feedwater N.A.

N.A.

S/U(5)

,1

}'

Pumps a

7.

LOSS OF POWER a.

4.16 kv Emergency Bus N.A.

R(3)

M(4) 1, 2, 3, 4 Undervoltage (Loss of Voltage) r b.

4.16 kv Emergency Bus N.A.

R(3)

M(4) 1, 2, 3, 4 Undervoltage (Degraded 2,

Voltage) iR Ei 8.

ENGINEERED SAFETY FEATURE N.A.

R N.A.

N.A.

l 55 ACTUATION SYSTEM INTERLOCKS 5

5 i8

~.

TABLE 4.3-2 (Continued)

TABLE NOTATION (1)

Manual actuation switches shall be tested at least once per 18 months during shutdown.

l (2)

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

(3)

Channel calibration shall exclude actuation of the final trip actuation relay.*

(4)

Functional testing shall consist of verification of relay operation upon removal of input voltage and operation of 2-out-of-3 logic excluding the final trip actuation relay.*

(5)

If not performed in the previous 92 days.

(6)

Excluding automatic actuation logic for trip of main feedwater pumps.

Actuation of the final trip actuation relay shall be included in response time testing.

FARLEY - UNIT 2

'3/4 3-37 AMENDMENT NO. D,99

,=

3/4.3 INSTRUMENTATION BASES 3/4.3.1 and 3/4.3.2 REACTOR TRIP SYSTEM and ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION The OPERABILITY of the Reactor Trip and Engineered Safety Feature Actuation System instrumentation and interlocks ensures that 1) the associated Engineered Safety Feature Actuation action and/or reactor trip will be initiated when the parameter monitored by each channel or combination thereof reaches its setpoint,

2) the specified coincidence logic and sufficient redundancy is maintained to permit a channel to be out of service for testing or maintenance consistent with maintaining an appropriate level of reliability of the Reactor Trip System and Engineered Safety Feature Actuation System instrumentation and, 3) sufficient system functional capability is available for protective and ESF purposes from diverse parameters.

The OPERABILITY of these systems is required to provide the overall reliability, redundancy and diversity assumed available in the facility design for the protection and mitigation of accident and transient conditions.

The integrated operation of each of these systems is consistent with the assumptions used in the accident analyses. The surveillance requirements specified for these systems ensure that the overall system functional capa-bility is maintained comparable to the original design standards.

The periodic surveillance tests performed at the minimum frequencies are sufficient to demonstrate this capability. Specified surveillance intervals and surveillance and maintenance outage times have been determined in accordance with WCAP-10271, Evaluation of Surveillance Frequencies and Out of Service Times for the Reactor Protection Instrumentation System," and supplements to that report as approved by the NRC and documented in the SERs and SSER (letters to J. J. Sheppard from Cecil 0.

Thomas dated February 21, 1985; Roger A. Newton from Charles E. Rossi dated February 22, 1989; and Gerard T. Goering from Charles E. Ro:.si dated April 30, 1990).

The Engineered Safety Feature Actuation System interlocks perform the l

functions indicated below on increasing the required parameter, consistent with the setpoints listed in Table 3.3-4:

P-11 Defeats the manual block of safety injection actuation on low pressurizer pressure.

P-12 Defeats the manual block of safety injection actuation on low steam l

line pressure, P-14 Trip of all feedwater pumps, turbine trip, closure of feedwater isolation valves and inhibits feedwater control valve modulation.

On decreasing the required parameter the opposite function is performed at reset setpoints, with the exception of P-12 as noted below:

P-12 Allows manual block of safety injection actuation on low steam line pressure. Causes steam line isolation on high steam flow. Affects steam dump blocks (i.e., prevents premature block of the noted function).

FARLEY-UNIT 2 B 3/4 3-1 AMENDMENT NO. 99

_

ML20069A075

Text

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