Text

Amends 129 & 116 to Licenses DPR-77 & DPR-79,respectively, Revising Tech Spec Table 3.3-3, ESF Actuation Sys Instrumentation, & Table 3.3-4, ESF Actuation Sys Instrumentation Trip Setpoint & Table 4.3-2
	ML19332E503
Person / Time
Site:	Sequoyah
Issue date:	11/28/1989
From:	Black S; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML19332E504	List: ML19332E503; ML19332E505;
References
	NUDOCS 8912070303
	Download: ML19332E503 (23)
	v • d • e

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%'1 UNITED STATES A

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NUCLEAR REGULATORY COMMISSION WAsHwoTow, p. c. noses k.....

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TENNESSEE VALLEY AUTHORITY:

-DOCKET NO. 50-327

-SEQUOYAH NUCLEAR' PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE-s l

c m,w Amendment Norr

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License No.

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1.

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

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The application for amendment by Tennessee Vall$y Authority (

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A.

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licensee) dated May 25, 1989, complies with the standards'and.-

l 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 Connission; l

C.

There is reasonable assurance-(1) that the activities authorized by L

this amendment can be conducted without endangering the health and i

safety of the public, and (ii) that such activities will be

- conducted in compliance with the Commission's regulations; 0.#

is amendment will not be inimical to the common "F

ty or to the health and safety of the public; and

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is amendment is in accordance with 10 CFR Part 51 s.

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's regulations and all applicable requirements have s

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8912070303 891128 PDR ADOCK 05000327

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2 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. OPR-77 is hereby amended to read as follows:

(2) Technical Specifications The Technical. Specifications contained in Appendices A and B, as-revised through Amendment No.129, 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.

~

'FOR THE NUCLEAR REGULATORY COMMISSION I

\\"

g SuzanneBlack., Assistant ( ) ire r-p j

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for Projects-y TVA Projects Division Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical l

Specifications l'

l:

Date of Issuance: November 28, 1989

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m ATTACHMENT-TO LICENSE AMENDMENT-NO.129

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1:-

FACILITY OPERATING LICENSE NO. DPR-77

~

DOCKET NO. 50-327 l Revise the Appendix A Technical Specifications-by removing the pages r

I identified below and inserting the enclosed pages. The revised pages are_ identified by the~ captioned amendment number and contain marginal

. lines indicating. the area of change. Overleaf pages* are provided to

' maintain document completeness.

REMOVE INSERT 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 3-23' 3/4 3-23 l;,

3/4 3-24 3/4 3-24*

'~

-3/4 3-27 3/4 3-27 3/4 3-27a 3/4 3-27a 3/4 3-37 3/4 3-37 o

3/4 3-37a 3/4 3-37a o

1-i 31 i,

6 e

t

.--d,-

~

_m TABLE 3.3-3 (Continued) rn -$

ENGINEERED SAFETY FEATURE-ACTUATION SYSTEM INSTRUMENTATION

,5 MINIMUM-

^

c=

-TOTAL NO.

CHANNELS-

~ CHANNELS-

' APPLICABLE =

FUNCTIONAL' UNIT OF CHANNELS TO' TRIP OPERABLE-MODES

. ACTION 5.

TURBINE TRIP &

FEEDWATER ISOLATION a.

Steam Generator 3/ loop 2/ loop-in-2/ loop in 11, 2,'3 116* -

Water Level--

any oper-each oper-High-High ating loop'

ating-loop b.

Automatic Actuation 2

1 2

1,2,3

. 23 Logic 6.

AUXILIARY FEEDWATER U

a.

Manual fnitiation 2

1 2

1,2,3 24 b.

Automatic Actuation 2

1 2

1, 2, 3-23 Logic c.-

Main Sta. Gen. Water Level-Low-Low a

~ Start Motor

.i.

{

Driven Pumps 3/sta. gen.

2/sta. gen.

1, 2, 3 16*

g

.any sta_ gen.

9 ii.

Start Turbine-

[

Driven Pump 3/sta. gen.

2/sta. gen.

2/sta. gen 1, 2,.3 16*

,o any 2 sta. gen.

O d.

S.I.

Start Motor-Driven i

O Pumps and Turbine t

.- w.,

~

Driven Pump See 1 above (all S.I. initiating functions and requirements) i 1

--,.1

... ~ -. '

' ~

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. TABLE 3.3-3 { Continued)

"c ENGINEERED SAFETY FEATURE ACTUATION SYSTEN INSTRUMENTATION S

i 1

x MIN'IMUN

' e TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES' LACTION-

- 7.

LOSS OF POWER

~ ]

a.

6.9 kv Shutdown Board

--Loss of Voltage 1.

Start Diesel-2/ shutdown

'1'1oss of 2/ shutdown 1,-2, 3, 4

'20*

Generators board voltage on board

'any shutdown board

,s*

2.

Load Shedding 2/ shutdown 1/ shutdown 2/ shutdown 1, 2, 3, 4 20*

T board board board-l3 b.

6.9 kv Shutdown Board Degraded Voltage 1.

Voltage Sensors 3/ shutdown 2/ shutdown 2/ shutdown 1, 2, 3, 4 20*

board board board 2.

Diesel Generator 2/ shutdown 1/ shutdown 1/ shutdown 1,2,3,4 20*

Start and Load board board board Sladding Timer 3.-

SI/ Degraded 2/ shutdown 1/ shutdown 1/ shutdown 1, 2, 3, 4 20*-

F

' Voltage Enable board board board s

Timer

- NOTE: This technical specification is to be implemented during the startup following the 2nd refueling outage or following completion of the modification, whichever is earlier.

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__.__-__.________-__.____-_____=-_,a

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u TABLE 3.3-3 (Continued)

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-ENGINEERED SAFETY FEATURE ACTDATION SYSTEM INSTRUE NTATION' E

MINIMDI

~

TOTAL NO.

CHANNELS CHANNELS APPLICABLE-c FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE' pW0ES ACTION 5

e.

Station Blackout' Start Motor-Driven

~ ~ ~

Pump associated 2/ shutdown' 1/ shutdown 2/ shutdown with the shutdown board boced board 1, 2, 3 20 board and Turbine Driven Pump f.

Trip of Main Feedwater Pumps Start Motor-Driven R

Pumps and Turbine Driven Pump 1/ pump 1/ pump 1/ pump 1, 2 20*

w h

g.

Auxiliar~y Feedwater Suction Pressure-Low 3/ pump 2/ pump 3/ pump 1, 2, 3 21*

h.

Auxiliary Feedwater Suction Transfer Time

- Delays 1.

Notor-Driven Pump 1/ pump 1/ pump 1/ pump 1, 2, 3 21*

2.. Turbine-Driven Pump 2/ pump 1/ pump 2/ pump 1, 2, 3 21*

k a

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Q TABLE 3.3-3 (Continued) 1 A.'. TION 21 -

With less than the Minimum Number of Channels OPERABLE, declare i

the associated auxiliary feedwater pump inoperable, and comply with the ACTION requirements of Specification 3.7.1.2.

l l

ACTION 22 -

With less than the Minimum Number of Channels OPERABLE, declare the interlock inoperable and verify that all affected channels of l

the functions listed below are OPERABLE or apply the appropriate ACTION statement (s) for those functions.

Functions to be evaluated are:

T i

a.

SafetyIn,jection

~

c Pressurizer Pressure b.

SafetyInjection l

High Steam Line Flow Steam Line Isolation High Steam Line Flow i

Steam Dump c.

Turbine Trip i

Steam Generator Level High-High l

Feedwater Isolation Steam Generator Level High-High I

ACTION 23 -

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

Number of Channels, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months i

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 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1.

ACTION 24 -

With the number of OPERABLE channels one less than the Total

!; umber 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 at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 25 -

With the niaber of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE l

status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the associated valve inoperable 1

-and take the ACTION required by Specification 3.7.1.5.

l 1

l-l i

SEQUOYAH - UNIT 1 3/4 3-23 Amendment No. 12, 63, 129 s

TABLE 3.3-4 m

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS 5

x e

FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES C5 1.

SAFETY INJECTION, TURBINE TRIP AND

[

FEEDWATER ISOLATION a.

Manual Initiation Not Applicable Not Applicable b.

Automatic Actuation Logic-Not Applicable Not Applicable c.

Containment Pressure--High 1 1.54 psig i 1.7 psig d.

Pressurizer Pressure--Low

> 1870 psig 1 1860 psig Y

e.

Differential Pressure

< 112 psi

[

Between Steam Lines--High

-< 100 psi S

f.

Steam F1'ow in Two Steam Lines--

< A function defined as

< A function defined as High Coincident with T

--Low-Low Tollows: A ap correspond-Tollows: / op corresponding avg or Steam Lme Pressure--tow ing to 40% of full steam to 44% of full steam flow flow between 0% and 20%

between 0% and 20% load and load and then a op then a op increasing increasing linearly to a linearly to a op correspond-ap corresponding to 110%

ing to 111.5% of full steam of full steam flow at flow at full load full load

~

T,,g 1 540*F T,,9 2 538'F

> 600 psig steam line 1 80 psig steam line 5

_pressure pressure a

TARLE 3.3-4 (Continued) m j

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS 5lE x

FUNCTIONAL UNIT TRIP SETPOINT ALLOWA8LE VALUES C*

6.

AUXILIARY FEEDWATER a.

Manual Not Applicable Not Applicable b.

Automatic Actuation Logic Not Applicable Not Applicable c.

Main Steam Generator Water Level-low-low

> 18% of narrow range

> 17% of narrow range Instrument span each Instrument span each steam generator steam generator

{

d.

S.I.

See 1 above (all SI Setpoints)

T e.

Station Blackout 0 volts with a 5.0 second 0 volts with a 5.0 1 1.0 second O

time delay time delay f.

Trip of Main Feedwater N.A.

N.A.

Pumps

g. - Auxiliary Feedwater Suction

> 2 psig (motor driven pump) > 1 psig (motor driven pump)

Pressure-Low

> 13.9 psig (turbine driven

> 12 psig (turbine driven Pump) pump)

$I h.

Auxiliary Feedwater Suction 4 seconds (motor driven 4 seconds 1 0.4 seconds E

Trinsfer Time Delays pump)

(motor driven pump)

~

5.5 seconds (turbine driven 5.5 seconds 1 0.55 seconds E

pump)

(turbine driven pump)

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Q TABLE 3.3-4 (Continued) w mS ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS S!

FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES

7.

LOSS OF POWER c-zZ a.

6.9 kv Shutdown Board Undervoltage Loss of Voltage 1.

Start of Diesel Generators a.

Nominal Voltage Setpoint 4860 volts 4860 volts +97.2 volts b.

Relay Response Time for 0 volts with a 1.5 second 0 volts witii a 1.5 +0.5 Loss of Voltage time delay sec d time delay -

2.

Load Shedding a.

Nominal Voltage Setpoint 4860 volts 4860 volts 97.2 volts b.

Relay Response Time for 0 volts with a 5.0 second 0 volts witii s 5.0 +1.0 R

Loss of Voltage time delay second time delay b.

6.9 kv Shutdown Board-Degraded w4 Voltage.

1.

Voltage Sensors 6560 volts 6560 volts + 33 volts 2.

Diesel Generator Start and l

Load Shed Timer 300 seconds 300 seconds + 30 seconds 3.

SI/ Degraded Voltage Logic Enable Timer 10 seconds 10 seconds + 0.5 seconds 8.

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INTERLOCKS a.

Prdssurizer Pressure g

Manua'l Block of Safety Injection P-11 1 1970 psig i 1980 psig 5

R

NOTE:

This technical specification is to be implemented at the startup following the 2nd refueling g

outage or following completion of the modification, whichever is earlier.

yi

..--. ~..

~,.

TABLE 4.3-2 (Continued) m j.

-ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREN NTS E

c CHANNEL MDDES IN WHICH 5

e-CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED

~

c.

Main Steam Generator Water S

R Q

1, 2, 3 Level-Low-Low d.

S.I.

See 1 above (all SI surveillance requirements) e.

Station Blackout N.A.

R N.A.

1,2,3 f.

Trip of Main Feedwater N.A.

N.A.

R 1, 2

{

Pumps Y

g.

Auxiliary Feedwater Suction N.A.

R M

1, 2, 3 Pressure-Low n.

Auxiliary Feedwater Suction N.A.

R M.A.

1, 2, 3 Transfer Time Delays i

7.

LOSS OF POWER a.

6.9 kv Shutdown Board -

Loss-of Voltage

1. ' Start Diesel Generators S

R M

1,2,3,4 F

2.

' Load Shedding S

R N.A.

1, 2, 3, 4

$a R

E F

NOTE:

This technical specification to be implemented at the startup following the 2nd refueling outage or following completion of the modification, whichever is earlier.

y

......u

-,,. ~.. ~

TABLE 4.3-2 (Continued) y j

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREE NTS E

. CHANNEL MODES IN WHICH c-CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED

b.

6.9 kv Shutdown Board -

Degraded Voltage 1.

Voltage sensors S

R N

1,2,3,4 2.

Diesel Generators N.A.

R N.A.

1, 2, 3, 4 l

Start and Load l

Shedding Timer 3.

SI/ Degraded Voltage N.A.

R N.A.

1,2,3,4 R*

Logic Timer Y

8.

ENGINEERED SAFETY FEATURE t,j ACTUATION SYSTEM INTERLOCKS i

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 Level, P-14 9.

AUTO $ATICSWITCH0VERTO

{

CONTAIMMENT SUNP 4

t, a.

RSWT Level - Low S

R M

1,2,3,4 COINCIDENT WITH 1

g Containment Sump Level - High 5

R M

1, 2, 3, 4 AND Safety Injection

.(See 1 above for all Safety Injection Surveillance Requirements) b.

Automatic Actuation Logic N.A.

N. A,._,,

M(1) 1, 2, 3, 4

NOTE: This technical specification to be implemented at the startup following the 2nd refueling outage or following completion of the modification, whichever is earlier.

..... = - -

g UNITED STATis

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NUCLEAR REGULATORY COMMISSION 5.

wAsmwarow o.c. sones

e essee c

TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SEQUOYAH NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment Ne's hl* *^

]

^

Liconse No.;.WR49k ;-

l The Nuclear Regulatory Connission (the Commission) has found that:[

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1.

A.

The application for amendment by Tennessee Valley Authority kY I

licensee)datedMay 25, 1989, 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 confomity with the application, the l

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 Consission's regulations; E

~

is amendment will not be inimical to the common t

ity or to the health and safety of the public; and O

p, v;pf E.')

is amendment is in accordance with 10 CFR Part 51

'f

's regulations and all applicable requirements have tieft v'

y 4

s l

l s

!l 2-2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment l

and paragraph 2.C.(2) of Facility Operating License No. OPR-79 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B as revised through Amendment No.116, 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.

FOR THE NUCLEAR REGULATORY COP 9t!SSION b

h

['

Suzanne ack, Assist rector

)

for Projects o

TVA Projects Division I

Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Spect fications i

- Date of Issuance: November 28, 1989 P

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e S

5 0

I

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E n, ATTACHMENT TO LICENSE AMENDMENT NO. 116 FACILITY OPERATING LICENSE NO. DPR-79 DOCKET NO. 50-328 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned smendment number and contain marginal lines indicating the area of change.

Overleaf pages* are provided to maintain document completeness.

REMOVE INSERT 3/4 3-19 3/4 3-19 3/4 3-20 3/4 3-20 3/4 3-23 3/4 3-23 3/4 3-24 3/4 3-24*

3/43-27 3/4 3-27 3/4 3-27a 3/4 3-27a 3/4 3-37 3/4 3-37 3/4 3-38 3/4 3-38 u

1 1

1 l

4 e

i 4

i O

a TABLE 3.3-3 (Continued)

N y

ENGINEERED SAFETY FEATURE ACTUATION SYSTEN INSTRUE NTATION E

NININUN c-.

TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS.

.TO TRIP' OPERABLE NODES ACTION-N COINCIDENT WITH EITHER T

--Low-Low 1, 2, 3 avg Four Loops 1 T,yg/ loop 2 T '9 any 1T any 16*-

100$

310$E Operating OR, COINCIDENT WITH Steam Line Pressure-1,2,3 Low R

Four Loops 1 pressure /

2 pressures 1 pressure 16*

Y Operating loop any loops any 3 loops e

5.

TURBINE TRIP &

FEEDWATER ISOLATION a.

Steam Generator 3/1oop 2/ loop in 2/ loop in 1,-2, 3 16*

Water Level--

any oper-each oper-High-High ating loop ating loop b.

Automatic Actuation 2

1 2

1,2,3 23

~

Logic e

6.

AUXILIARY FEEDWATER a.

Manual Initiation 2

1 2

1,2,3 24 z?

b.

Automatic Actuation 2

1 2

1,2,3 23 w

Logic w

,E

=

o,

TABLE 3.3-3 (Continued)

. v, E

ENGINEERED-SAFETY FEATURE ACTUATION SYSTEM INSTRtMENTATION h

MINIfRM i

E TOTAL ND.

CHANNELS CHANNELS APPLICABLE

~

FUNCTIONAL UNIT.

OF CHANNELS TO TRIP OPERABLE DEBES

-ACTION-E c;

Main Sta. Gen. Water Z

Level-Low-Low I..

i.

Start Motor Driven Pumps 3/sta. gen.

2/sta. gen.

-2/sta. gen.

1, 2, 3 16*'

any sta gen.

1 ii. Start Turbine-Driven Pump 3/sta. gen.

2/sta. gen.

2/sta. gen 1, 2, 3 16*

any 2 sta. gen.

d.

S.I.

Start Motor-Driven i

Pumps and Turbine l

Driven Pump See 1 above (all S.I. initiating functions and requirements) w e.

Station Blackout 1

Start Motor-Driven Pump associated 2/ shutdown 1/ shutdown 2/ shutdown w

4 with the shutdown board board board 1, 2, 3 20 board and Turbine Driven Pump f.

Trip of Main Feedwater Pumps j

Start Motor-Driven

. Pumps and Turbine l

- Driv.en Pump 1/ pump 1/ pump 1/ pump 1, 2 20*

i g.

Auxiliary Feedwater j

k Suction Pressure-Low 3/ pump 2/ pump 3/ pump 1,2,3 21*

8 m

j g

h.

Auxiliary Feedwater j

Suction Transfer 3

Time Delays F

1.

Motor-Driven

)

Pump 1/ pump 1/ pump 1/ pump 1, 2,.3 21*

3 (3

2.

Turbine-Driven j

Pump 2/ pump 1/ pump.

2/ pump 1,2,3 21*

a i

l 4

1-'

.)

L TABLE 3.3-3 (Continued)

~ ACTION 21 -

With less than the Minimum Number of Channels OPERABLE, I

declare the associated auxiliary feedwa wr pump inoperable, 1

and comply with the ACTION requirements of Specification 3.7.1.2.

ACTION 22 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 i

appropriate ACTION statement (s) for those functions.

Functions to be evaluated are:

a.

Safety Injection Pressurizer Pressure b.

Safety Injection High Steam Line Flow Steam Line Isolation High Steam Line Flow Steam Dump 1

c.

Turbine Trip e

Steam Generator Level High-High Feedwater Isolation Steam Generator Level High-High ACTION 23 -

With the number of OPERABLE channels one less than the Total Number of Channels, 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 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 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1.1.

ACTION 24 -

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

ACTION 25 -

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 declare the associated valve inoperable and take the ACTION required by Specification 3.7.1.5.

SEQUOYAH - UNIT 2 3/4 3-23 Amendment No. 55,116

TABLE-3.3-4

.g S

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS

.o

!E FUNCTIONAL UNIT TRIP SETPOINT

. ALLOWA8LE VALUES C5 1.

SAFETY INJECTION, TURBINE TRIP AND FEEDWATER ISOLATION a.

Manual Initiation Not Applicable Not Applicable b.

Ai,tomatic Actuation Logic Not Applicable Not Applicable c.

Containment Pressure--High 11.54 psig

$1.7 psig 4

d.

Pressurizer Pressure--Low 11870 psig 11860 psig e.

Differential Pressure

$100 psi 1112 psi Between Steam Lines--High R

f.

Ste*am Flow in Two Steam Lines--

<A function defined as

<A function defined as T

High Coincident with T"V9--Low-Low Tollows: A op correspond-Tollows: A op corresponding

's or Steam Line Pressure--Lw ing to 40% of full steam to 44% of full steam flow flow between 0% and 20%

between 0% and 20% load and load and then a Ap then a op increasing increasing linearly to a linearly to a op correspond-ap corresponding to 110%

ing to 111.5% of full steam

)

of full steam flow at flow at full load full load i

~

T,yg 1MO*F T,,9 1538'F 4

2

>600 psig steam line

>580 psig steam line pressure pressure Na W

1"n

. ~.,

6

.--a c-

-.a-v.-~,

s.,

w

.,_w

.g TABLE 3.3-4 (Continued) g ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUNENTATION TRIP slE

n FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES

,E_.

6.

AUXILIARY FEEDWATER m

a.

Manual Not Applicable,

Not Applicable b.

Automatic Actuation Logic Not Applicable Not Applicable I

c.

Main Steam Generator Water Level-low-low

>18% of narrow range

>17% of narrow range Instrument span each Instrument span each steam generator steam generator d.

S. I.

See 1 above (all SI Setpoints)

I e.

Station Blackout

0. volts with :: 5.0 second 0 volts with a 5.0 1 1.0 second w

time delay time delay k

f.

Trip of Main Feedwater N.A.

Pumps N. A.

g.

Auxiliary Feedwater Suction Pressure-Low

> 2 psig (motor driven pump)

> 1 psig (motor driven pum

> 13.9 psig (turbine driven

> 12 (turbine driven pump)p)

(pump) h.

Auxiliary Feedwater Suction Transfer Time Delays 4 seconds (motor driven pump) 4 seconds 0.4 seconds (motor driven pump) 2 E

~

5.5 seconds (turbine driven pump) 5.5 seconds i0.55 seconds 2

(turbine driven pump) a

~..

M

. s

,.~

. TABLE 3.3-4 (Continued).

,m j

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS s

. ~.

7 FUNCTIONAL UNIT

. TRIP SETPOINT ALLOWABLE VALUES E

7.

LOSS OF POWER

~~

6.9 kv Shutdown Board Undervoltage m

a.

Loss of Voltage 1.

Start of Diesel Generators a.

Nominal Voltage Setpoint 4860 volts 4860 volts 197.2. volts b.

~ Relay Response Time for 0 volts with a 1.5 second 0 volts with'a 1.5 10.5 Loss of Voltage time delay second time delay 2.

Load Shedding a.

Nominal Voltage Setpoint 4860 volts 4860 volts 197.2 volts y

b.

Relay Response Time for 0 volts with a 5.0 second 0 volts with a 5.0 1.0 Loss of Voltage time delay second time delay T

2 0,

o b.

6.9 kv Shutdown Board-Degraded

.t Voltage 1.

Voltage Sensors 6560 volts 6560 volts i 33 volts 2.

Diesel Generator Start and Load Shed Timer 300 seconds 300 seconds i 30 seconds 3.

'SI/ Degraded Voltage Logic g

Enable Timer 10 seconds 10 seconds 1 0.5 seconds E

8.

ENGINEERED SAFETY FEATURE l

ACTUATION SYSTEM INTERLOCKS n

z a.

Pressurizer Pressure F

Manual Block of Safety Injection P-11 11970 psig 11980 psig.

NOTE: This technical specification is to be implementsd'5dring the startup following the 1st refueling

=

outage.

m

,.. -... ; ?

TABLE 4.3-2 (Continued) g f

' ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION y

SURVEILLANCE REQUIREE NTS CHANNEL MODES FOR WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE IS E

FUNCTIONAL UNIT CHECK

^ CALIBRATION TEST REQUIRED c.

Main Steam Generator Water S

'R

.Q 1,'2, 3 Level-Low-Low d.

S.I.

See 1 above (all SI surveillance requirements) e.

Station Blackout N.A.

R N.A.

1, 2, 3 f.

Trip of Main Feedwater N.A.

M.A.

R 1, 2 Pumps g.

Auxiliary Feedwater Suction N.A.

R M

1, 2, 3 Pressure-Low h.

Auxiliary

Feedwater Suction N.A.

R N.A.

1, 2, 3 Y

Transfer Time Delays w"

7.

LOSS OF POWER a.

6.9 kv Shutdown Board -

Loss'of Voltage 1.

Start Diesel Generators S

R

.N 1,2,3,4 2

Load Shedding 5

R N.A.

1,2,3,4 F

NOTE:

This te~chnical specification is to be implemented during the startup following the 1st refueling outage.

E e

5>

A

.g.

s

.u TABLE-4.3-2 (Continued)-

.m

+.

j ENGINEERED 5AFETY FEATURE ACTUATION SYSTEM INSTRUE NTATION SURVEILLANCE REQUIRtMERIS-

~

E e

CHANNEL MODES FOR WICH.

e CHANNEL CHANNEL FUNCTIONAL' SURVEILLANCE IS' y

FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED

b.

6.9 kw Shutdown Board -

Degraded Voltage 1.

Voltage sensors S

R M

1, 2, 3, 4 2.

Diesel Cenerators N.A.

R N.A.

1, 2, 3, 4 Start and Load Shedding Timer

.i 3.

SI/ Degraded Voltage M.A.

R N.A.

1, 2, 3, 4

{

Logic Timer i

T 8.

ENGINEERED SAFETY FEATURE M

ACTUATION SYSTEM INTERLOCKS a.

Pressurizer Pressure, N.A.

R(2)

N.A.

1, 2, 3 P-11

- i b._ T,,g, P-12 N.A Rf2)

N.A.

1, 2, 3 c.

Steam Generator N.A.

R(2)

N. A.

1, 2 L,evel, P-14 k

9.

AUTOMATIC SWITCHOVER TG y

CONTAIMENT SUNP 1

a.

RSWI Level - Low 5

R M

1, 2, 3, 4 COINCIDENT WITH E

Containment Sump Level - High 5

R M

1, 2, 3, 4 AND Safety Injection (See 1 above for all Safety Injection Surveillance Requirements) u, b.

Automatic Actuation Logic N.A.

N.A.

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

vi

-w

Note: This technical specification is to be implemented during the startup following the 1st refueling outage.

g

.

ML19332E503

Text

Attachment:

Attachment:

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