Text

Amends 67 & 59 to Licenses NPF-2 & NPF-8,respectively, Revising Tech Specs Re Operation & Surveillance Requirements for Reactor Trip Breakers,Including Automatic Shunt Trip Feature Mods
	ML20215N233
Person / Time
Site:	Farley
Issue date:	10/24/1986
From:	Rubenstein L; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20215N234	List: ML20215N233; ML20215N240;
References
	TAC-55354, TAC-55355, NUDOCS 8611050077
	Download: ML20215N233 (26)
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_

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UNITED STATES NUCLEAR REGULATORY COMMISSION g

WASHINGTON, D. C. 20066 t

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\\...../

ALABAMA POWER COMPANY DOCKET NO. 50-348 JOSEPH M. FARLEY NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 67 License No. NPF-2 4

1.

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

A.

The application for amendment by Alabama Power Company (the licensee) dated December 16, 1985, supplemented August 1, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, as amended, the provisions of the Act, and the 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 of 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 amenoment, and paragraph 2.C.(2) of Facility Operating License No. NPF-2 is hereby amended to read as follows:

J c16110SOO77 861024 PDR ADOCK 05000348 P

PDR

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 67. are hereby incorporated in the license. The licensee 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 receipt of this amendment.

FOR THE NUCLEAR REGULATORY COMISSION h

k n"+

Lester S. Rubenstein, Director PWR Project Directorate #7 Division of PWR Licensing-A Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

October 24, 1986 t

j, 1

ATTACHMENT TO LICENSE AMENDMENT NO. 67 TO FACILITY OPERATING LICENSE NO. NPF-2 DOCKET NO. 50-348 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated. The revised pages are identi'ted i

by amendment number and contain vertical lines indicating the area of chanoe, The corresponding overleaf pages are also provided to maintain document completeness.

j Remove Pages Insert Pages 3/4 3-2 3/4 3-2 1

3/4 3-5 3/4 3-5 3/4 3-9 3/4 3-9 3/4 3-12 3/4 3-12 3/4 3-13 3/4 3-13 l

3/4 3-14 3/4 3-14 m

1 i

i

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

.__m

3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION i

3.3.1 As a minimum, the reactor trip system instrumentation channels and interlocks of Table 3.3-1 shall be OPERABLE with RESPONSE TIMES as shown in Table 3.3-2.

4 APPLICABILITY: As shown in Table 3.3-1.

ACTION:

As shown in Table 3.3-1.

.l SURVEILLANCE REQUIREMENTS 4.3.1.1 Each reactor trip system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MODES and at the frequencies shown in Table 4.3-1.

4.3.1.2 The logic for the interlocks shall be demonstrated OPERABLE prior to each reactor startup unless performed during the preceding 92 days. The total interlock function shall be demonstrated OPERABLE at least once per 18 months, 4.3.1.3 The REAC10R TRIP SYSTEM RESPONSE TIME of each reactor trip function shall be demonstrated to be within its limit at least once per 18 months.

Each test shall include at least one logic train such that both logic trains are tested at least once per 36 months and one channel per function such that

.all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip function as

.shown in the " Total No. of Channels" column of Table 3.3-1.

\\

FARLEY-UNIT 1 3/4 3-1 AMENDMENT NO. 26

-c

p TABLE 3.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION

?

EE U

HINIMUM TOTAL NO.

CHANNELS CHANNELS

-APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPLRABLE 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#

H.

Lme 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 s

[

5.

Intermediate Range, Neutron 2

1 2

1, 2, and

3####

Fl ux 4

6.

Source Range, Neutron Flux A.

Startup 2

1 2

2##, and

4 B.

Shutdown 2

0 1###

3, 4 and 5 S

7.

Overtemperature A T 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#

Two Loop Operation 3

1**

2 1, 2 9

g 9.

Pressurizer Pressure-Low 3

2 2

1 7#

10. Pressurizer Pressure--High 3

2 2

1, 2 7#

=

5 5:

1 m

TABLE 3.3-1 (Continued) s2 l

p2 REACTOR TRIP SYSTEM INSTRUMENTATION E2 c:

35

-e MINIMUM TOTAL. NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 2

1 2

1, 2 1, 14 3*, 4*, 5*

13 l

21'.

' Reactor Trip Breakers 2

1 2

1. 2 I

22.

Automatic Trip Logic 3*, 4*, 5*

13 i

OJ

+

I 1

j

-99 5

f TABLE 3.3-1 (Continued)

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

6 The provisions of Specification 3.0.4 are not applicable.

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

000 Indication only.

00##

The provisions of Specification 3.0.3 are not applicable if THERMAL POWER level > 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 EDT 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 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , b.

The Minimum Channels 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,the other channels per Specification 4.3.1.1.

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

c.

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 NO. 61

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 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

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 46 hours5.324074e-4 days 0.0128 hours 7.60582e-5 weeks 1.7503e-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 i

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.

f 1

J I

h i

e AMENDMENT NO. 26, 6:

FARLEY - UNIT.1 3/4 3-9

.m w,-.,----

e.,-,----w

--m..-.-,--.---wy-

,-_,-----.-.--y,.-

.,-------.,------w.---.----._y,--

., -.,,, - ~,,.

l TABLE 3.3-2 5

i REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES Q

e Z

FUNCTIONAL UNIT RESPONSE TIME 1.

Manual Reactor Trip Not Applicable 2.

Power Range, Neutron Flux a.

High 5 0.5 seconds

b.

Low Not Applicable 3.

Power Range, Neutron Flux, High Positive Rate Not Applicable 4.

Power Range, Neutron Flux, High Negative Rate 1 0.5 seconds *

{

5.

Intermediate Range, Neutron Flux Not Applicable Y

6.

Source Range, Neutron Flux Not Applicable o

7.

Overtemperature AT 1 4.0 seconds

8.

Overpower AT Not Applicable 9.

Pressurizer Pressure--Low 1 2.0 seconds 10.

Pressurizer Pressure--High 1 2.0 seconds 9

11.

Pressurizer Water Level--High E

Not Applicable 9

-4 5

Neutron detectors are exempt from response time testing.

Response time of the neutron flux signal portion m*

of the channel shall be measured from detector output or input of first electronic component in channel.

b

l I

TABLE 3.3-2 (Continued)

{

REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES 1

e j

]

FUNCTIONAL UNIT RESPONSE TIME 12.

A.

Loss of Flow - Single Loop l

(Above P-8) i 1.0 seconds f

B.

Loss of Flow - Two Loops (Above P-7 and below P-8) 1 1.0 seconds 13.

Steam Generator Water Level--Low-Low i 2.0 seconds 14.

Steam /Feedwater Flow Nismatch and Low Steam Generator Water Level Not Applicable j

15.

Undervoltage-Reactor Coolant Pumps i 1.2 seconds i

s

16. Underfrequency-Reactor Coolant Pumps 1 0.6 seconds U

17. Turbine Trip J

A.

Low Auto Stop 011 Pressure Not Applicable B.

Turbine Throttle Valve Closure Not Applicable

]

18.

Safety Injection Inpu.t from ESF Not Applicable l

l 19.

Reactor Coolant Pump Breaker Position Trip Not Applicable 20.

Reactor Trip System Interlocks Not Applicable j

21.

Reactor Trip Breakers Not Applicable i

22. Automatic Trip Logic Not Applicable E

i 4

TABLE 4.3-1

{

REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREttENTS E

CHANNEL MODES IN WHICH O

CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CAllBRATION TEST REQUIRED 1.

Manual Reactor Trip N.A.

N.A.

R(11),

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

4*, 5*

2.

Power Range, Neutron Flux A.

High S

D(2),M(3)

M 1, 2 and Q(6) 8.

Low S

0(2),M(3)

S/U(10) 2 and Q(6) 3.

Power Range, Neutron Flux, High N.A.

R(6)

M 1, 2 w2 Positive Rate 4

Power Range, Neutron Flux, N.A.

R(6)

M 1, 2 High Negative Rate 5.

Intermediate Range, Neutron S

R(6)

S/U(1) 1, 2 and Flux 6.

Source Range, Neutron Flux S(7)

R(6)

M and S/U(1) 2, 3, 4, 5, and

7.

OvertemperaturehT S

R M

1, 2 Overpower b T S

R M

1, 2 8.

I 2

9.

Pressurizer Pressure-tow S

R M

1 4

E

10. Pressurizer Pressure--High S

R M

1, 2 45

11. Pressurizer Water Level--High 5

R M

1 12.

A.

Loss of Flow - Single Loop S

R M

1 3

B.

Loss of Flow - Two Loops S

R N.A.

1 0

92 TABLE 4.3-1 (Continued) 7-E?

REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS C

CHANNEL MODES IN WHICH

[-[d CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED 13.

Steam Generator Water Level--

S R

M 1, 2 Low-Low 14.

Steam /Feedwater Flow Mismatch S

R H

1, 2 and Low Steam Generator Water

-Level IS. Undervoltage - Reactor Coolant N.A.

R H

1 Pumps 16 Underfrequency - Reactor N.A.

R M

1 Ad Coolant Pumps i'

17. Turbine Trip EI A.

Low Auto Stop Oil Pressure N.A.

N.A.

S/U(9)(1)

N.A.

B.

Turbine Throttle Valve N.A.

N.A.

S/U(9)(1)

N.A.

Closure

18. Safety Injection Input from ESF N.A.

N.A.

M(4) 1, 2

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, SE S/U(1)(14)(15) 3*, 4*, 5*

9 EE

22. Automatic Trip Logic N.A.

N.A.

M(5) 1, 2, 9

3*, 4*, 5*

-4 EE

23. Reactor Trip Bypass Breaker N.A.

N.A.

(13),R(ll) 1, 2, 3*, 4 *, 5*

e

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) - 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.

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

4 (6) - Neutron detectors may be excluded from CHANNEL CALIBRATION.

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

(8) - Logic only, if not performed in previous 92 days.

(9) - CHA%EL 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.

(11) - Independently verify 0PERABILITY of the undervoltage and shunt trip circuitry for the Manual Reactor Trip Function.

(12) - Verify reactor trip breaker and reactor trip bypass breaker open l

upon actuation of each Main Control Board handswitch.

(13) - Local manual snunt trip prior to placing breaker in service.

Local manual undervoltage trip prior to placing breaker in service.

10) - Undervoltage trip via Reactor Protection System.

' 6) - Local manual shunt trip.

FARLEY - UNIT 1 3/4 3-14 AMENDMENT NO.26,M,67, 67

f[ a uc,)o u

UNITED STATES.

'g NUCLEAR REGULATORY COMMISSION e

o g

E WASHINGTON, D. C. 20555 g

,o ALARAMA' POWER COMPANY DOCKET NO. 50-364 JOSEPH M. FARLEY NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 59 License No. NPF-8 1.

The Nuclear Regulatory Comission (the Comissioni has found that:

A.

The application for amendment by Alabama Power Company (the licensee) dated December 16, 1985, supplemented August 1, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; 9.

The facility will ope ate in conformity with the application, as amended, the provisions of the Act, and the 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 of the Comission's regulations and all applicable requirements have been satisfied.

9 Accordiaglv, 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 Specifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No. 59, are hereby incorporated in the license. The licensee 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 receipt of this amendment.

FOR THE NUCLEAR REGULATORY COMMISSION f.3 Lester S.

ubenstein, Director PWR Pro.fect Directorate #2 Division of PWR Licensing-A Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: October 24, 1986

j ATTACHMENT TO LICENSE AMENDMENT NO. 59 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 as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.

i The corresponding overleaf pages are also provided to maintain document completeness.

Remove Pages Insert Pages 3/4 3-2 3/4 3-2 3/4 3-5 3/4 3-5 3/4 3-9 3/4 3-9 3/4 3-12 3/4 3-12 i

3/4 3-13 3/4 3-13 3/4 3-14 3/4 3-14 i

l

3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1 As a minimum, the reactor trip system instrumentation channels and.

interlocks of Table 3.3-1 shall be OPERABLE with RESPONSE TIMES as shown in Table 3.3-2.

APPLICABILITY:

As shown in Table 3.3-1.

ACTION:

As shown in Table 3.3-1.

SURVEILLANCE REQUIREMENTS 4.3.1.1 Each reactor trip system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MODES and at the frequencies shown in Table 4.3-1.

4.3.1.2 The logic for the interlocks shall be demonstrated OPERABLE prior to each reactor startup unless performed during the preceding 92 days.

The total interlock function shall be demonstrated OPERABLE at least once per 18 months.

4.3.1.3 The REACTOR TRIP SYSTEM RESPONSE TIME of each reactor trip function shall be demonstrated to be within its limit at least once per 18 months.

Each test shall include at least one logic train such that both logic trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once e*;ery N times 18 months where N is the total number of redundant channels in a specific reactor trip function as shown in the " Total No. of Channels" column of Table 3.3-1.

i 1

FARLEY-UNIT 2 3/4 3-1

TABLE 3.3-1 g

REACTOR TRIP SYSTEM INSTRUMENTATION E

MINIMUM Z

TOTAL NO.

CHANNELS CHANNELS APPLICABLE -

no 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.

Hi gh 4

2 3

1, 2 2#

B.

Low 4

2 3

2 2#

3.

Power Range, Neutron Hux, 4

2 3

1, 2 2#

High Positive Rate 4

2 3

1, 2 2#

4.

Power Range, Neutron Flux,.

High Negative Rate

,s

[

5.

Intermediate Range, Neutron 2

1 2

1, 2, and *'

3####

4 Flux 6.

Source Range, Neutron Flux A.

Startup 2

1 2

2##, and

4 B.

Shutdown 2

0 l###

3, 4 and 5 5

7.

Overtemperature A T 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#

Two Loop Operation 3

1**

2 1, 2 9

g 9.

Pressurizer Pressure-Low 3

2 2

1 7#

10.

Pressurizer Pressure--High 3

2 2

1, 2 7#

=

^

s P

TABLE 3.3-1 (Continued) m?

'E REACTOR TRIP SYSTEM INSTRUNENTATION Q

MINIMUM

~

TOTAL NO.

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

17. Turbine Trip A.

Low Auto Stop 011 Pressure 3

2 2

1 B.

Turbine Throttle Valve 4

4 4

1 7

Closure 18.

Safety Injection Input from ESF 2

1 2

1, 2 1

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

11 per oper-R ating loop T

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 4

2 3

1 8

Flux, P-8 D.

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

3 1, 2 8

E.

Turbine Impulse Chamber Pressure, P-13 2

1 2

1 8

F.

Power Range Neutron 4

2 3

1 8

Flux, P-9

f g

TABLE 3.3-1 (Continued),

i REACTOR TRIP SYSTEM INSTRUMENTATION Q

-i MINIMUM N

TOTAL NO.

CHANNELS CHANNELS APPLICARLE FUNCTIONAL UNIT OF CilANNELS 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 1

3*,4*,5*

13 v.

a9 5

IS

-g_

i i

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 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

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.

FARLEY - UNIT 2 3/4 3-9 AMENDMENT NO. 59

~

e TABLE 3.3-2 E

REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES p

?.

RESPONSE TIME E

FUNCTIONAL UNIT ro 1.

Manual Reactor Trip Not Applicable 2.

Power Range, Neutron Flux

< 0.5 seconds

a.

High Not Appiicable b.

Low 3.

Power Range, Neutron Flux, High Positive Rate-Not Applicable 4.

Power Range, Neutron Flux, High Negative Rate 1 0.5 seconds

5.

Intermediate Range, Neutron Flux Not Applicable w

6.

Source Range, Neutron Flux Not Applicable 7.

Overtemperature AT

$ 4.0 seconds

8.

Overpower AT Not Applicable 9.

Pressurizer Pressure--Low i 2.0 seconds 10.

Pressurizer Pressure--High 1 2.0 seconds 11.

Pressurizer Water ievel--High Not Appiicable

' Neutron detectors are exempt from response time testing.

Response time of the neutron flux signal portion of ' the channel shall be measured f rom detector nut put or input of f irst. elect ronic component in channel.

I l

TABLE 3.3-2 (Centinuzd)

Y p2 REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES O

s-RESPONSE TIME j

FUNCTIONAL UNIT b2 12.

A.

Loss of Flow - Single Loop (Above P-8) 1 1.0 seconds B.

Loss of Flow - Two Loops (Above P-7 and below P-8) i 1.0 seconds 13.

Steam Generator Water Level--Low-Low 1 2.0 seconds 14.

Steam /Feedwater Flow Mismatch and Low Steam Generator Water Level Not Applicable 15.

Undervoltage-Reactor Coolant Pumps 1 1.2 seconds 16.

Underfrequency-Reactor Coolant Pumps 5 0.6 seconds ka 17.

Turbine Trip

?>

A.

Low Auto Stop Oil Pressure Not Applicable B.

Turbine Throttle Valve Closure Not Applicable 18.

Safety Injection Input from ESF Not Applicable 19.

Reactor Coolant Pump Breaker Position Trip Not Applicable 20.

Reactor Trip System Interlocks Not Applicable 21.

Reactor Trip Breakers Not Applicable 22.

Automatic Trip logic Not Applicable I

4 4

)

g TAllLE 4.3-1 i

Q REACTOR TRIP SYSTEM INSTRl!MFNTATION StlRVEILLANCE REQUIREMENTS h

CHANNEL MODES IN WillCil CilANNEl.

CllANNLI.

FilNCT IONAL S11RVE ILL ANCI:

m FilNCTIONAL llNIT CllLCK CAllHRAil0N ILST ltEQUIRED 1.

Manual Reactor Trip N.A.

N.A.

R(ll),

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

4*,

5+

2.

Power Range, Neutron Flux A.- liigh S

1)(2), M(3)

M 1, 2 anel Q(f )

H.

Low S

D(2),M(3)

S/U(10) 2 and O(6) 3.

Power Range, Neutron Flux,liigh N.A.

R(6)

M 1, 2 wg Positive Rate

[

4 Power Range, Neutron Flux, N.A.

R(6)

M 1, 2 liigh Negative Rate N

S.

Intermediate Range, Neutron S

R(6)

S/ll(l) 1, 2 anel Flux 6.

Source Range, Neutron Flux S(/)

R(b)

!! and S/U(1) 2, 3, 4, 5, anel

1.

OvertemperaturehT S

R M

1, 2 H.

Overpower b T S

R H

1, 2 5

gl 9

Pressurizer Pressure-Low S

R H

I A

g.

10.

Pressurizer Pressure--liigh S

R-M 1, 2 5

11.

Pressurizer Water I.evel--Ilieth S

R M

1 y

17.

A.

l.oss of Flow - SiniJie 1.oop N

R ft 1

[

11 I o<.s o f I l ow - Iwo Ioops S

R N.A.

1

TAHLE 4.3-1 (Continued) i "n

E REACTOR TRIP SYSTEM INSTRUMENTATION SURVLILLANCE REQUIREMENTS E

CllANNEL MODES IN WHICli U

CilANNEL CllANNEL FUNCTIONAL SURVEILLANCE CllECK CALIBRATION.

TEST REQUIRED ro FilNCTIONAL UNIT

13. Steam Generator Water Level--

S R

H 1, 2 Low-Low 14.

Steam /Feedwater Flow Mismatch S

R M

1, 2 and low Steam Generator Water Level IS. Undervoltage - Reactor Coolant N.A.

R H

I Pumps

~

N.A.

R M

1 16.

Underfrequency - Reactor Coolant Pumps y

A.

Low Auto Stop Oil Pressure N.A.

N.A.

S/U(9)(1)

N.A.

17. Turbine Trip O

H.

Turbine Throttle Valve N.A.

N.A.

S/U(9)(1)

N.A.

Closure

18. Safety injection input from ESF N.A.

N.A.

M(4) 1, 2

19. Reactor Coolant Pump Breaker N.A.

N.A.

R 1

Position Trip 20.

Reactor Trip System Interlocks N.A.

R S/tf(H) 1 N.A.

N.A.

M(5)(14)(IS),

I, 2

21. Reactor Trip Breaker S/U(1)(14)(IS) 3*, 4*, S*

N

22. Automatic Trip logic N.A.

N.A.

M(S)

I, 2, 3*, 4*, S*

23. Reactor Trip Bypass Hreaker H.A.

N.A.

(13),R(ll)

I, 2 5

3*,'4*, 5*

2F

TABLE 4.3-1 (Continued)

TABLE NOTATION

- With the reactor trip system breakers closed and the control rod drive system capable of rod witndrawal.

(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)

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.

(5) - Each train or logic cnannel shall be testec at least every 62 days on a STAGGERED TEST BASIS.

(t) - heutron detectors may be excluaed fron CHANNEL CALIHRATIUN, (7) - Below the P-6 (Block of Source Range Reactor Trip) setpoint.

(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 turoine and indicates no turbine trip prior to P-9.

(10) - If not performed in the previous 31 days.

(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.

(14) - Undervoltage trip via Reactor Protection System.

(lo) - Local manual shunt trip.

W l

FARLEY - UNIT 2 3/4 3-14 AMENDMENT NO. 37, n 5'.-

e

v t e Letter Sequence Other
TAC:55354, (Open) TAC:55355, (Open)
Initiation Request Acceptance... Supplement Administration Questions Answers Results Approval Other: ML20138P110, ML20204H272, ML20215N233
MONTHYEAR1986-10-24 [Table View]

ML20215N233

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