Text

Amends 138 & 130 to Licenses NPF-2 & NPF-8,respectively, Changing TSs to Change Applicable Modes for Source Range Nuclear Instrumentation (TS 3/4.3.1, Reactor Trip Sys Instrumentation)
	ML20154L273
Person / Time
Site:	Farley
Issue date:	10/15/1998
From:	Berkow H; NRC (Affiliation Not Assigned)
To:	;
Shared Package
ML20154L278	List: ML20154L273; ML20154L287;
References
	NUDOCS 9810190199
	Download: ML20154L273 (16)
	v • d • e

_

M Eco p

t UNITED STATES g

j NUCLEAR REGULATORY COMMISSION p

2 WASHINGTON, D.C. 20066 0001 j

$9.....

SOUTHERN NUCLEAR OPERATING COMPANY. INC.

ALABAMA POWER COMPANY DOCKET NO. 50-348 JOSEPH M. FARLEY NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.138 License No. NPF-2 l

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

A. The application for amendment by Southern Nuclear Operating Company, Inc.

(Southem Nuclear), dated May 27,1997, 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:

9810190199 981015 PDR ADOCK 05000348 P

PDR 3

6 2

(2) Technical Soecificatio'ns The Technical Specifications contained in Appendices A and B, as revised through Amendment No.138, are hereby incorporated in the license. Southern Nuclear 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 e bert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications l

i Date of issuance: October 15, 1998 i

1 t

4

ATTACHMENT TO LICENSE AMENDMENT NO.138 TO FACILITY OPERATING LICENSE NO. NPF-2 i

DOCKET NO. 50-348 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.

i Remove Insert i

3/4 3-2 3/4 3-2 3/4 3-6 3/4 3-6 3/4 3-14 3/4 3-14 3/4 5-3 3/4 5-3 3/4 5-7 3/4 5-7

)

l l

1 i

i

TABLE 3.3-1 i

REACTOR TRIP SYSTEM INSTRUMENTATION l

MINIMUM

~ TOTAL NO.

CHANNELS CHANNELS APPLICABLE i

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION N

1.

Manual Reactor Trip 2

1 2

1, 2

12 3*,

4*,

5*

13 2.

Power Range,. Neutron Flux A.

High 4

2 3

1, 2

24 B.

Low 4

2 3

2 2#

3.

Power Range, Neutron Flux, 4

2 3

1, 2

2#

High Positive Rate 4.

Power Range, Neutron Flux, 4

2 3

1, 2

2#

High Negative Rate 3

5.

Intennediate Range, Neutron 2

1 2

1, 2, and

35###

Flux O

I 6.

Source Range, Neutron Flux A.

Startup 2

1 2

2##, and

4 B.

Shutdown 2

0 1###

3***,

4 and 5 5

l 7.

Overtemperature AT L

Three Loop Operation 3

2 2

1, 2

7#

Two Loop Operation 3

1**

2 1,

2 9

8.

Overpower AT Three Loop Operation 3

2 2

1, 2

7#

l Two Loop Operation 3

1**

2 1,

2 9

f 9.

Pressurizer Pressure-Low 3

2 2

1 7#

10.

Pressurizer Pressure--High 3

2 2

1, 2

75 2?

+

C m

-..__-..-.._.__-__,-,..--..._-_a.

=..

1 l

TABLE 3.3-1 (Continued)

TABLE NOTATION With the reactor trip system breakers in the closed position, the i

control rod drive system capable of rod withdrawal, and fuel in l

the reactor vessel.

I L

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

f Below the P-6 (Block of Source Range Reactor Trip) setpoint.

l 1Nie provisions of Specification 3.0.4 are not. applicable.

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

Indication only.

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 ,

b. The Minimum Channels OPERABLE requirement is met; however, the inoperable chann'l may be bypassed for up to e

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of the other channels per Specification 4.3.1.1.

j

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 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.

i 1

i l'

i i

FARLEY-UNIT 1 3/4 3-6 AMENDMENT NO.138 j

l

TABLE 4.3-1 (Continued)

TABLE NOTATION With the reactor trip system breakers closed and the control rod drive system capable of rod Witt drawal.

(1)

If not performed in previous 7 days.

(2)

- Heat balance only, above 15% of RATED THERMAL POWER. Adjust l

channel if absolute difference is greater than 2 percent.

(3)

Compare incore to excore axial flux difference every 31 EFPD.

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

(4)

- Manual ESF functional input check every 18 months.

l (5)

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

(6)

- Neutron detectors may be excluded from CHANNEL CALIBRATION.

(7)

Below the P-6 (Block of Source Range Reactor Trip) setpoint.

U on reaching P-6 from MODE 2 the CHANNEL CHECK must be p

performed within I hour.

Logic only, if not performed in previous 92 days.

(8)

(9)

- CHANNEL FUNCTIONAL TEST will consist of verifying that each channel indicates a turbine trip prior to latching the turbine and indicates no turbine trip prior to P-9.

If not performed in the previous 31 days.

(10)

(11)

Independently verify OPERABILITY of the undervoltage and shunt trip circuitry for the Manual Reactor Trip Function.

(12)

Verify reactor trip breaker and reactor trip bypass breaker open upon actuation of each Main Control Board handswitch.

(13)

Local manual shunt trip prior to placing breaker in service.

Local manual undervoltage trip prior to placing breaker in service.

Undervoltage trip via Reactor Protection System.

(14)

(15) - Local manual shunt trip.

I I

FARLEY-UNIT 1 3/4 3-14 AMENDMENT NO.138

EMERGENCY CORE COOLING SYSTEMS 3/4.5.2 ECCS SUBSYSTEMS - T3yg > 350*F LIMITING CONDITION FOR OPERATION 3.5.2 Two independent Emergency Core Cooling System (ECCS) subsystems shall be OPERABLE with each subsystem comprised of:

a.

One OPERABLE centrifugal charging pump, L

b.

One OPERABLE residual heat removal heat exchanger, c.

One OPERABLE residual heat removal pump, and d.

An OPERABLE flow path capable of taking suction from the refueling water storage tank on a safety injection signal and transferring suction to the containment sump during the recirculation phase of operation.*

l APPLICABILITY: MODES 1, 2 and 3.

ACTION:

]

a.

With one ECCS subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be ira 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 HOT l

l SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

1 I

b.

In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to specification 6.9.2 within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date.

The current value of the usage factor for each affected safety injection nozzle shall be provided in this special Report whenever its value exceeds 0.70.

1 l

l j'

Upon entry into Mode 3 from Mode 4, the breaker or disconnect device to the valve operators for MOVs 8706A and 8706B may be locked open 1

for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to allow for repositioning from Mode 4 requirements.

FARLEY-UNIT 1 3/4 5-3 AMENDMENT NO.138 j

4 5

i

. =.

, =.

EMERGENCY CORE COOLING SYSTEMS 3/4.5.3 ECCS SUBSYSTEMS - Tavg < 350*F i

LIMITING CONDITION FOR OPERATION l

3.5.3 As a minimum, one ECCS subsystem comprised of the following shall be OPERABLE:

a.

One OPERABLE centrifugal charging pump, b.

One OPERABLE residual heat removal heat exchanger, c.

One OPERABLE residual heat removal pump, and d.

An OPERABLE flow path capable of taking suction from the refueling water storage tank upon being manually realigned I

and transferring suction to the containment sump during the recirculation phase of operation.*

l APPLICABILITY: MODE 4.

1 ACTION:

1 With no ECCS subsystem OPERABLE because of the inoperability a.

of either the centrifug'al charging pump or the flow path from the refueling water storage tank, restore at least one ECCS subsystem to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in COLD SHUTDOWN within the next 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months if at least one RHR loop is OPERABLE.

b.

With no ECCS subsystem OPERABLE because of the inoperability of either the residual heat removal heat exchanger or residual heat removal pump, restore at least one ECCS subsystem _to OPERABLE status or maintain the Reactor Coolant System T vg less than 350*F by use of alternate heat removal a

methods.

c.

In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the. total accumulated actuation cycles to date. The current value of the usage factor for each affected safety injection nozzle shall be provided in this Special Report whenever its value exceeds 0.70.

Upon entry into Mode 4 from Mode 3, the breaker or disconnect device to the valve operators for MOVs 8706A and 8706B may be closed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to allow for repositioning from Mode 3 requirements.

FARLEY-UNIT 1 3/4 5-7 AMENDMENT NO. 138

i RREfoq g

S UNITED STATES t

g j

NUCLEAR REGULATORY COMMISSION e

f WASHINGTON, D.C. 20066 0001

'+9.....,d I

SOUTHERN NUCLEAR OPERATING COMPANY. INC.

ALABAMA POWER COMPANY DOCKET NO. 50-364 l

JOSEPH M. FARLEY NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 130 License No. NPF-8

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

A. The application for amendment by Southern Nuclear Operating Company, Inc.

(Southern Nuclear), dated May 27,1997, 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 4

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 OperatinD License No. NPF-8 is hereby amended to read as follows:

l l

.. _. -. - - - -. ~. _.. -.. -..

r l

l (2) Technical Soecificatio'ns l

The Technical Specifications contained in Appendices A and B, as revised throegh Amerdment No.130, are hereby incorporated in the license. Southern Nuclear shall ope: ate the facility in accordance with the Technical Specifications.

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

FOR THE NUCLEAR REGULATORY COMMISSION rt N. Berko, Director roject Directorate 11-2 r

Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation

Attachment:

l Changes to the Technical Specifications

~l Date of issuance: October 15, 1998 l

I t

I

\\

i ATTACHMENT TO LICENSE AMENDMENT NO.130 l

l 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 marginallines.

Remove Insert 3/4 3-2 3/4 3-2 3/4 3-6 3/4 3-6 1

3/4 3-14 3/4 3-14 3/4 5-3 3/4 5-3 3/4 5-7 3/4 5-7 t

L I

I

TABLE 3.3

REACTOR TRIP SYSTEM INSTRUMENTATION

_g.

MINIMUM

'Q.

TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT _

OF CHANNELS TO TRIP OPERABLE.

MODES ACTION 1.

Manual Reactor Trip 2

1 2

1, 2 12 3*,

4*,

5*

13 2.

Power Range, Neutron Flux A.

High 4

2 3

1, 2

2#

B.

Low 4

2 3

2 24 3.

Power Range, Neutron Flux, 4

2 3

1, 2 25 High Positive Rate 4.

Power Range Neutron Flux.

4 2

3 1,

2 2#

High Negative Rate w.1 5.

Intermediate Range, Neutron 2

1 2

1, 2 and

3####

w 4

Flux 6.

Source Range, Neutron Flux A.

Startup 2

1 2

2##, and

4 B.

Shutdown 2

0 199#

3***,

4 and 5 5

l 7.

Overtemperature AT Three Loop Operation 3

2 2

1, 2

7#

Two Loop Operation 3

1**

2 1,

2 9

8.

Overpower AT Three Loop Operation 3

2 2

1, 2 7#

I 9.

Two Loop Operation 3

1**

2 1,

2 9

Pressurizer Pressure-Low 3

2 2

1 7#

10.

Pressurizer Pressure--High 3

2 2

1, 2 7#

g O

a

1 TABLE 3.3-1 (Continued)

TABLE NOTATION

With the reactor trip system breakers in the closed position, the l

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.

1

- - Below the P-6 (Block of Source Range Reactor Trip) setpoint.

l 1

J

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.

J 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:

'The inoperable channel is placed in the tripped condition a.

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

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 the other channels per Specification 4.3.1.1.

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 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.

l FARLEY-UNIT 2 3/4 3-6 AMENDMENT NO. 130 4

I i

TABLE 4.3-1 (Continued)

TABLE NOTATION With the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal.

(1)

If not performed in previous 7 days.

(2)

Heat balance only, above 15% of RATED THERMAL POWER. Adjust channel if absolute difference is greater than 2 percent.

3 (3)

Compare'incore to excore axial flux difference every 31 EFPD.

Rscalibrate if the absolute difference is greater than or equal to 3 percent.

Manual ESF functional input check every 18 months.

l (4)

(5)

Each train or logic channel shall be tested at least every i

62 days on a STAGGERED TEST BASIS.

(6)

Neutron detectors may be excluded from CHANNEL CALIBRATION.

1 (7)

Below the P-6 (Block of Source Range Reactor Trip) setpoint.

Upon reaching P-6 from MODE 2 the CHANNEL CHECK must be performed within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

(8)

Logic only, if not performed in previous 92 days.

(9)

CHANNEL FUNCTIONAL TEST will consist of verifying that each channel indicates a turbine trip prior to latching the turbine and indicates no turbine trip prior to P-9.

(10)

If not performed in the previous 31 days.

)

l l

(11)

Independently verify OPERABILITY of the undervoltage and shunt trip circuitry for the Manual Reactor Trip Function.

(12)

Verify reactor trip breaker and reactor trip bypass breaker l

open upon actuation of each Main Control Board handswitch.

l (13)

Local manual shunt trip prior to placing breaker in service.

i Local manual undervoltage trip prior to placing breaker in service.

l l

(14)

Undervoltage trip via Reactor Protection System.

l (15)

Local manual shunt trip.

4 i

FARLEY-UNIT 2 3/4 3-14 AMENDMENT NO.130

. - _ - -. ~.. -. -... -.

. _... ~.

+

EMERGENCY CORE COOLING SYSTEMS 3/4.5.2 ECCS SUBSYSTEMS - T yg > 350'F LIMITING CONDITION FOR OPERATION 3.5.2 Two independent Emergency Core Cooling System (ECCS) subsystems shall be OPERABLE with each subsystem comprised of:

a.

One OPERABLE centrifugal charging pump, b.

One OPERABLE residual heat removal heat exchanger, c.

One OPERABLE residual heat removal pump, and i

d.

An OPERABLE flow path capable of taking suction from the refueling water storage tank on a safety injection signal and transferring suction to the containment sump during the recirculation phase of operation.*

l APPLICABILITY:

MODES 1, 2 and 3.

ACTION:

a.

With one ECCS subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

In the event the ECCS is actuated and injects water into the Reactor Coolant Ssstem, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date. The current value of the usage factor for each affected safety injection nozzle shall be provided in this Special Report whenever its value exceeds 0.70.

1 i

I Upon entry into Mode 3 from Mode 4, the breaker or disconnect device to the valve operators for MOVs 8706A and 8706B may be locked open for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to allow for repositioning from Mode 4 requirements.

FARLEY-UNIT 2 3/4 3-3 AMENDMENT NO. 130 l

__.m

~

EMERGENCY CORE COOLING SYSTEMS 3/4.5.3 ECCS SUBSYSTEMS - Tavg < 3 50'_F LIMITING CONDITION FOR OPERATION 3.5.3 As a minimum, one ECCS subsystem comprised of the following shall be OPERABLE:

a.

One OPERABLE centrifugal charging pump, b.

One OPERABLE residual heat removal heat exchanger, c.

One OPERABLE residual heat removal pump, and d.

An OPERABLE flow path capable of taking suction from the refueling water storage tank upon being manually realigned and transferring suction to the containment sump during the recirculation phase of operation.*

l APPLICABILITY:

MODE 4.

ACTION:

a.

With no ECCS subsystem OPERABLE because of the inoperability of either the centrifugal charging pump or the flow path from the refueling water storage tank, restore at least one ECCS subsystem to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in COLD SHUTDOWN within the next 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months if at least one RHR loop is OPERABLE.

l b.

With no ECCS subsystem OPERABLE because of the inoperability of either the residual heat removal heat exchanger or.

l residual heat removal pump, restore at least one ECCS subsystem to OPERABLE status or maintain the Reactor Coolant System T vg less than 350'F by use of alternate heat remova:

a methods.

c.

In the event the ECCS is actuated and injects water into the j.

Reactor Coolant System, a Special Report shall be prepared l

and submitted to the Commission pursuant to specification l

6.9.2 within 90 days describing the circumstances of the actuation and the, total accumulated actuation cycles to date. The current value of the usage factor for each affected safety injection nozzle shall be provided in this Special Report whenever its value exceeds 0.70.

Upon entry into Mode 4 from Mode 3, the breaker or disconnect device to the valve operators for MOVs 8706A and 8706B may be closed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to allow for repositioning from Mode 3 requirements.

FARLEY-UNIT 2 3/4 5-7 AMENDMENT NO. 130

ML20154L273

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