Text

Amends 47 & 39 to Licenses DPR-77 & DPR-79,respectively, Changing Tech Specs to Extend Surveillance Frequencies & out-of-svc Times for Reactor Trip Sys
	ML20203N159
Person / Time
Site:	Sequoyah
Issue date:	09/17/1986
From:	Youngblood B; Office of Nuclear Reactor Regulation
To:	;
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References
	NUDOCS 8609230173
	Download: ML20203N159 (24)
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-

'o UNITED STATES

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WASHINGTON, D. C. 20555

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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SEQUOYAH NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 47 License No. DPR-77 1.

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

A.

The application for amendment to the Sequoyah Nuclear Plant, Unit 1 (the facility) Facility Operating License No. DPR-77 filed by the Tennessee Valley Authority (licensee), dated May 23, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Connission's regulations as set forth in 10 CFR Chapter I; B.

The facility will operate in confonnity with the license, as amended, the provisions of the Act, and the rules and regulations of the Connission; C.

There is reasonable assurance (1) 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 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 hereby amended by page changes to the Appendix A i

Technical Specifications as indicated in the attachment to this license amendnent, and paragraph 2.C.(2) of Facility Operating License No. DPR-77 is hereby amended to read as follows:

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8609230173 860917 PDR ADOCK 05000327 P

PDR

. (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 47 are hereby incorporated into 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.

FOR THE NUCLEAR REGULATORY C0tWISSION 6

B. J. Youngblood, Director PWR Project Directorate #4 Division of PWR Licensing-A Attachment" Appendix A Technical Specification Changes Date of Issuance:

September 17, 1986 l

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ATTACHMENT TO LICENSE AMENDMENT NO. 47 FACILITY OPERATING LICENSE NO. DPR-77 DOCKET NO. 50-327 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.

Amended Pages 3/4 3-5 3/4 3-6 3/4 3-7 3/4 3-8 3/4 3-34 3/4 3-35 3/4 3-36 3/4 3-37a 3/4 3-38 1

1

TABLE 3.3-1 (Continued)

TABLE NOTATION With the reactor trip system breakers in the closed position'and 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.

"High voltage to detector may ae de-energized above the P-6 (Block of Source.

Range Reactor Trip) setpoint.

ACTION STATEMENTS ACTION 1 -

With the number of channels OPERABLE one less than required by e

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 and/or open the reactor trip breakers.

ACTION 2 -

With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and 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, 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 l

for surveillance testing per Specification 4.3.1.1.1.

t c.

Either, THERMAL POWER is restricted to less than or equal to 75% of RATED THERMAL and the Power Range, Neutron Flux I

high trip 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 is monitored at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , d.

The QUADRANT POWER TILT RATIO, as indicated by the remaining three detectors is verified consistent with the normalized symmetric power distribution obtained by using the movable l

incore detectors in the four pairs of symmetric thimble l

locations at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when THERMAL POWER is i

greater than 75% of RATED THERMAL POWER.

i i

SEQUOYAH - UNIT 1 3/4 3-5 Amendment No. 47

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 0PERABLE 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.

d.

Above 10% of RATED THERMAL POWER, the provisions of Specification 3.0.3 are not applicable.

ACTION 4 -

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 Ran e Reactor Trip) setpoint, restore the inoperable channel to PERABLE 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 channels OPERABLE 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 i

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 one less than the Total j

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, 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 4.3.1.1.1.

ACTION 7 -

With the number of OPERABLE channels one less than the Total l

Number of Channels, STARTUP an./or POWER OPERATION may proceed until performance of the neyt required CHANNEL FUNCTIONAL TEST i

provided the inoperable ch,annel is placed in the tripped condition l

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

l 3

SEQUOYAH - UNIT 1 3/4 3-6 Amendment No. 47 1

TABLE 3.3-1 (Continued)

ACTION 8 -

With less than the Minimum Number of Channels OPERABLE, declare the interlock inoperable and verify that all affected channels of the functions listed below are OPERABLE or apply the appro-priate ACTION statement (s) for these functions.

Functions to be evaluated are:

a.

Source Range Reactor Trip b.

Reactor Trip Low Reactor Coolant Loop Flow (2 loops)

Undervoltage Underfrequency Pressurizer Low Pressure Pressurizer High Level

/

c.

Reactor Trip Low Reactor Coolant Loop Flow (1 loop) d.

Reactor Trip Intermediate Range Low Power Range Source Range e.

Reactor Trip Turbine Trip ACTION 9 Deleted ACTION 10 -

Deleted ACTION 11 -

Deleted ACTION 12 -

With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, be in at least HOT STANOBY 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 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months for surveillance testing per Specification 4.3.1.1.1 provided the other channel is OPERABLE.

l D

e SEQUOYAH - UNIT 1 3/4 3-7 Amendment No. 47

TABLE 3.3-1 (Continued) i ACTION 13 -

With the number of OPERABLE channels one less than the Total Number of Channels and wi+h the THERMAL POWER level above the P-7 (Block of Low Power Reactor Trips) setpoint, place the inoperable channel in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , l

operation may continue until performance of the next required CHANNEL FUNCTIONAL TEST.

ACTION 14 -

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

l l

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s 1

SEQUOYAH - UNIT 1 3/4 3-8 Amendment No. 47

s TABLE 4.3-2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION Q

SURVEILLANCE REQUIREMENTS s

CHANNEL MODES IN WHICH 5

CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED

]

1.

SAFETY INJECTION AND FEEDWATER ISOLATION a.

Manual Initiation N.A.

N.A.

R 1,2,3,4 b.

Automatic Actuation Logic N.A.

N.A.

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

c.

Containment Pressure-High S

R Q

1,2,3 d.

Pressurizer Pressure--Low S

R Q

1,2,3 J,

'e.

Differential Pressure S

R Q

1,2,3

Batween Steam Lines--High f.

Steam Flow in Two Steam S

R Q

1,2,3 Lines--High Coincident with T,yg--Low-Low or Steam Line Pressure--Low 2.

CONTAINMENT SPRAY

~

a.

Manual Initiation N.A.

N.A.

R 1,2,3,4 b.

Automatic Actuation Logic N.A.

N.A.

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

y c.

Containment Pressure--High-High S R

Q 1,2,3

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s TABLE 4.3-2 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION Q

SURVEILLANCE REQUIREMENTS E

[

CHANNEL MODES IN WHICH 5

CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED 3.

CONTAINMENT ISOLATION a.

Phase "A" Isolation i

1) Manual N.A.

N.A.

R 1,2,3,4

2) From Safety Injection N.A.

N.A.

M(1) 1, 2, 3, 4 Automatic Actuation Logic i

q b.

Phase "B" Isolation

[

1) Manual N.A.

N.A.

R 1,2,3,4 8

i

2,) Automatic Actuation N.A.

N.A.

M(1) 1, 2, 3, 4

]

Logic

3) Containment Pressure--

S R

Q 1,2,3 High-High c.

Containment Ventilation Isolation

1) Manual N. A.

N.A.

R 1,2,3,4

2) Automatic Isolation Logic N.A.

N.A.

M(1) 1, 2, 3, 4 g-

3) Containment Gas Monitor S

R M

1,2,3,4 g

Radioactivity-High k

n E

1

s TABLE 4.3-2 (Continued) 4 y,

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION 1

Q SURVEILLANCE REQUIREMENTS i

E h

CHANNEL MODES IN WHICH z

CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE Z

FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED

4) Containment Purge Air S

R M

1,2,3,4 Exhaust Monitor Radio-activity-High

5) Containment Particulate S

R M

1,2,3,4 Activity-High 4.

STEAM LINE ISOLATION l

q a.

Manual N.A.

N.A.

R 1,2,3 i

+

l

..'b.

Automatic Actuation Logic N.A.

N.A.

M(1) 1,2,3 w

1 w*

i c.

Cbntainment Pressure--

S R

Q 1,2,3 l

High-High d.

Steam Flow in Two Steam S

R Q

1,2,3 Lines--High Coincident with T,yg--Low-Low or Steam Line Pressure--Low 5.

TURBINE TRIP AND FEEDWATER ISOLATION

[

a.

Steam Generator Water S

R Q

1,2,3 l

Level--High-High

=

6.

AUXILIARY FEEDWATER y

a.

Manual N.A.

N.A.

R 1, 2, 3 0

b.

Automatic Actuation Logic N.A.

N.A.

M(1) 1, 2, 3 4

s l

TABLE 4.3-2 (Continted) v,

)

{!

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS o

i E

l

[

CHANNEL MODES IN WHICH z

CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE El FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED 8.

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INTERLOCKS a.

Pressurizer Pressure, N.A.

R(2)

N.A.

1,2,3 P-11 b.

T,yg, P-12 N.A.

R(2)

N.A.

1,2,3 c.

Steam Generator N.A.

R(2)

N.A.

1, 2 l

3:

Level, P-14 i

l Y

9' AUTOMATIC SWITCHOVER TO j

y CONTAI,NMENT SUMP a.

RSWT Level - Low S

R M

1,2,3,4

)

COINCIDENT WITH i

Containment Sump Level - High S

R M

1,2,3,4 AND l

Safety Injection (See 1 above for all Safety Injection Surveillance Requirements) l l

w I

I g

i I

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TABLE 4.3-2 (Continued)

TABLE NOTATION (1) Each train or logic channel shall be tested at least every 62 days on a STAGGERED TEST BASIS.

(2) The total interlock function shall be demonstrated OPERABLE during CHANNEL CALIBRATION testing of each channel affected by interlock operation.

/

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SEQUOYAH - UNIT 1 3/4 3-38 Amendment No.47 l

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UNITED STATES

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NUCLEAR REGULATORY COMMISSION 5

j WASHINGTON, D. C. 20555 i

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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SEQL'OYAH NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 39 License No. DPR-79 1.

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

A.

The application for amendment to the Sequoyah Nuclear Plant, Unit 2 (the facility) Facility Operating License No. DPR-79 filed by the Tennessee Valley Authority (licensee), dated May 23, 1986 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations as set forth in 10 CFR Chapter I; B.

The facility will operate in confonnity with the license, as amended, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (1) 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 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 hereby amended by page changes to the Appendix A Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-79 is hereby amended to read as follows:

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. (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 39 are hereby incorporated into 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.

FOR THE NUCLEAR REGULATORY COMMISSION

'\\9 B. J. Youngblood, Director PWR Project Directorate #4 Division of PWR Licensing-A Attachment Appendix A Technical Specification Changes Date of Issuance:

September 17, 1986 PWRM/hWR-A PWR.

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ATTACHMENT TO LICENSE AMENDMENT NO. 39 FACIL'ITY OPERATING LICENSE NO. DPR-79 DOCKET NO. 50-328 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vert,1 cal lines indicating the areas of change.

Amended Page 3/4 3-5 3/4 3-6 3/4 3-7 3/4 3-8 3/4 3-34 3/4 3-35 3/4 3-36 4

s-3/4 3-37a 3/4 3-39 i

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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.

"High voltage to detector may be de-energized above the P-6 (Block of Source Range Reactor Trip) setpoint.

ACTION STATEMENTS i

ACTION 1 - 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 H0T STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and/or open the reactor trip breakers.

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:

i 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 .

I b.

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

for surveillance testing per Specification 4.3.1.1.1.

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 l

QUADRANT POWER TILT RATIO is monitored at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

d.

The QUADRANT p0WER TILT RATIO, as indicated by the remaining three detectors, is verified consistent with the normalized symmetric power distribution obtained by using the movable incore detectors in the four pairs of symmetric thimble locations at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when THERMAL POWER is greater than 75% of RATED THERMAL POWER.

SEQUOYAH - UNIT 2 3/4 3-5 Amendment No. 39 f

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TABLE 3.3-1 TContinued)

/

3

.i ACTION 3 - With the' number of channels OPERABLE ohe less than required by

,j~

f the Minimum Channels OPERABLE requirement and with the THERMAL 4

O*

~

POWER level:

.e

~

i

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s';

Below the P-6 (Block ofiSource. Range Reactor Trip) setpoint, j

i 6

)a restoretheinoperablechannel;toOPERABLEstatuspriorto N

.O~

increasing THERMAL POWER above the P-6 Setpoint.

i

,i i

s:

)

b.

Above the P-6!(Block of Source Range Reactor Trip) setpoint, x.

t but below 5% of RATED THERMAL POWER,' restore the inoperable b

channel to OPERABLE status prior to increasing THERMAL POWER aoove 5% of RATED THERMAL PfMER.

t 1

o c.

Above 5% of RATED THERMAL POWER, ' POWER OPERATION may 9

4 A

continue.

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i

.t 7

y d.

Above 10% of RATED. THERMAL POWER, the provisions of t.

Specificatic'n 3.0.'3 are not applictble.

,s i

JCTMH 4 - With the number of OPERA 3LE channels ens'less than required by 1

the Minimum Channels OPERABLE requirement.and with the THERMAL e

F0WER level:

4

-l

,t

,E~

3 b'

a.

Below the P-6 (Block of-Scurce Range Reactor Trip) setpoint, q

restore the inoperable channel to.0PERABLE. status prior to i

increasingTHERMALPOWERabovethqF-6Setpoint.

A s

s4 b.

Above the P-6 (Block of Source Range Reactor Trip) setpoint,

~

operatiori may continue.

a

' ACTION 5 - With the number of OPERABLE channels o.w,less than required by

,s\\-

the Minimum Channels OPERABLE requiremeht, verify compliance 4

with the SHUTDOWN MARGIN requirements af Specification 3.1.1.1

.o i

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 3

J 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

t T

ACTION 6 - With the nteber of OPERABLE channe?s one less than the Total i

t Number of Channels, STARTUP'and/or PCWER OPERATION may proceed i

provided tt.e 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 a

w.

I

- b.

The Minimum Channels OPERABLE requirement is met; however, M

i 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 l

g for surveillance testing per Specification 4.3.1.1.1.

ACTION 7 - With the number of OPERABLE channels one less than the Total 1

Number of Channels, STARTUP and/or POWER OPERATION may proceed until performance 1of tha next required CHANNEL FUNCTIONAL TEST provided the inoperable channel is placed in the tripped condition within;5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .

l 1

i

,SEQUOYAH.- UNIT E 3/4 3-6 Amendment No. 39 e

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TABLE 3.3-1 (Continued) i i

ACTION 8 - With less than the Minimum Number of Channels OPERABLE, declare the interlock inoperable and verify that all affected channels of the functions listed below are OPERABLE or apply the appro-priate ACTION statement (s) for those functions.

Functions to be evaluated are:

a.

Source Range Reactor Trip.

b.

Reactor Trip Low Reactor Coolant Loop Flow (2 loops)

Undervoltage Underfrequency Turbine Trip Pressurizer Low Pressure Pressurizer High Level c.

Reactor Trip Low Reactor Coolant Loop Flow (1 loop) d.

Reactor Trip Intermediate Range Low Power Range Source Range ACTION 9 - Deleted ACTION 10 - Deleted ACTION 11 - Deleted ACTION 12 - With the number of OPERABLE channels one less than required by the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to I hour for surveillance testing per Specification 4.3.1.1.1 provided the other channel is OPERABLE.

1 SEQUOYAH - UNIT 2 3/4 3-7 Amendment No. 39 I

TABLE 3.3-1 (Continued)

ACTION 13 - With the number of OPERABLE channels one less than the Total Number of Channels and with the THERMAL POWER level above the P-7 (enable reactor trips) setpoint, place the inoperable channel in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , operation may continue l

until performance of the next required CHANNEL FUNCTIONAL TEST.

ACTION 14 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SEQUOYAH - UNIT 2 3/4 3-8 Amendment No. 39

s TABLE 4.3-2 mE ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION k

SURVEILLANCE REQUIREMENTS CHANNEL MODES FOR WHICH 3

CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE IS FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED m

1.

SAFETY INJECTION AND FEEDWATER ISOLATION a.

Manual Initiation N.A.

N.A.

R 1,2,3,4 b.

Automatic Actuation Logic N.A.

N.A.

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

Containment Pressure-High S

R q

1,2,3 d.

Pressurizer Pressure--Low S

R g

1,2,3

[

i.

Differential Pressure S

R g

1,2,3

Between Steam Lines--High f.

Steam Flow in Two Steam S

R q

1,2,3 Lines--High Coincident with T,yg--Low-Low or Steam Line Pressure--Low 2.

CONTAINMENT SPRAY

[

a.

Manual Initiation N.A.

N.A.

R 1,2,3,4 f

b.

Automatic Actuation Logic N.A.

N.A.

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

[

c.

Containment Pressure--High-High S R

Q 1,2,3 5

9

s TABLE 4.3-2 (Continued)

E ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION j

SURVEILLANCE REQUIREMENTS b

CHANNEL MODES FOR WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE IS i

g FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED

[

3.

CONTAINMENT ISOLATION a.

Phase "A" Isolation

1) Manual N.A.

N.A.

R 1,2,3,4

2) From Safety Injection N.A.

N.A.

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

Phase "B" Isolation

1) Manual N.A.

N.A.

R 1,2,3,4 5

2) Automatic Actuation Logic N.A.

N.A.

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

~

J.

.3) Containment Pressure--

S R

Q 1,2,3 High-High c.

Containment Ventilation Isolation

1) Manual N.A.

N.A.

R 1,2,3,4

2) Automatic Isolation Logic N.A.

N.A.

M(1) 1, 2, 3, 4

3) Containment Gas Monitor S

R M

1,2,3,4 Radioactivity-High E

I n

E

TABLE 4.3-2 (Continued) u, E

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION

[o SURVEILLANCE REQUIREMENTS 2

7 CHANNEL MODES FOR WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE IS FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED w

4) Containment Purge Air S

R M

1,2,3,4 m

Exhaust Monitor Radio-activity-High

5) Containment Particulate S

R M

1,2,3,4 Activity-High 4.

STEAM LINE ISOLATION a.

Manual N.A.

N.A.

R 1,2,3

,s

[

b.

Automatic Actuation Logic N.A.

N.A.

M(1) 1, 2, 3

c.

Containment Pressure--

S R

Q 1,2,3 High-High d.

Steam Flo'in Two Steam S

R Q

1,2,3 Lines--High Coincident with T

-- Lo -Low or Steam Line PN9surew-Low 5.

TURBINETRIPANDFEdDWATER ISOLATION g

[

a.

Steain Generator Water S

R Q

1,2,3 g

Level--High-High

<+

=

6.

AUXILIARY FEEDWATER P

a.

Manual N.A.

N.A.

R 1,2,3 g

b.

Automatic Actuation Logic N. A.

N.A.

M(1) 1, 2, 3

s TABLE 4.3-2 (Continued) wE ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION k

SURVEILLANCE REQUIREMENTS E

[

CHANNEL MODES FOR WHICH z

CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE IS H

FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED ro 8.

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INTERLOCKS a.

Pressurizer Pressure, N.A.

R (2)

N.A.

1,2,3 P-11 b.

T,yg, P-12 N.A R (2)

N.A.

1,2,3 c.

Steam Generator N.A.

R (2)

N.A.

1, 2 mg Level, P-14 w

U 9.

AUTOMATIC SWITCHOVER TO CONTAINMENT SUMP a.

RSWT Level - Low S

R M

1,2,3,4 COINCIDENT WITH Containment Sump Level - High S

R M

1,2,3,4 AND Safety Injection (See 1 above for all Safety Injection Surveillance Requirements) y i

e l

TABLE 4.3-2 (Continued)

TABLE NOTATION (1) Each train or logic channel shall be tested at least every 62 days on a STAGGERED TEST BASIS.

(2) The total interlock function shall be demonstrated OPERABLE during CHANNEL CALIBRATION testing of each channel affected by interlock operation.

SEQUOYAH - UNIT 2 3/4 3-39 Amendment No. 39

-

ML20203N159

Text

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