Text

Amends 168 & 158 to Licenses DPR-77 & DPR-79,respectively, Incorporating Various Changes to TS Re Containment Gas & Radiation Monitor Sys,Containment Purge Air Radiation Sys & Switches Associated W/Manual Trip of Containment Spray Sys
	ML20045F371
Person / Time
Site:	Sequoyah
Issue date:	06/25/1993
From:	Hebdon F; Office of Nuclear Reactor Regulation
To:	;
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ML20045F372	List: ML20045F371; ML20045F377;
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!i-V4 UNITED STATES

?

2.E NUCLEAR REGULATORY COMMISSION i

o, WASHINGTON, D.C. 20586 f

y/

j TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SE000YAH NUCLEAR PLANT. UNIT 1

{

AMENDMENT TO FACILITY OPERATING LICENSE i

r l

Amendment No. ~168 j

-License No. DPR-77 I

1.

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

A.

The application for. amendment by Tennessee Valley Authority (the licensee) dated August 27, 1991, and supplemented by letter dated November 6,1992, 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; l

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; j

D.

The issuance of this amendment will not be inimical to the common l

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.

)

t i

I P

i l

y 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. DPR-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.168, 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, to be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION Frederick J. Hebdon, Director Project Directorate 11-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

l Changes to the Technical Specifications Date of Issuance: June 25, 1993 h

l t

a

ATTACHMENT TO LICENSE AMENDMENT NO.168 FACILITY OPERATING LICENSE NO. DPR-77 DOCKET NO. 50-327 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 amendment number and contain marginal lines indicating the area of change.

REMOVE INSERT 3/4 3-16 3/4 3-16 3/4 3-17 3/4 3-17 3/4 3-22 3/4 3-22 3/4 3-26 3/4 3-26 3/4 3-32 3/4 3-32 3/4 3-35 3/4 3-35 3/4 3-36 3/4 3-36 3/4 3-40 3/4 3-40 3/4 3-41 3/4 3-41 3/4 3-42 3/4 3-42 B3/4 9-3 B3/4 9-3 l

1 i

i

TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION E

MINIMUM i

TOTAL NO.

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

Steam Line Pressure-3/ steam line 2/ steam line 2/ steam line 1,2,3 17*

Low in any steam line 2.

CONTAINMENT SPRAY a.

Manual 2

1**

2 1,2,3,4 20 b.

Automatic Actuation 2

1 2

1,2,3,4 15 Logic R

c.

Containment Pressure--

4 2

3 1,2,3 18 High-High P'

M 3.

CONTAINMENT ISOLATION a.

Phase "A" Isolation 1)

Manual 2

1 2

1,2,3,4 20 2)

From Safety Injection 2

1 2

1., 2, 3, 4 15 F

Automatic Actuation

,{

Logic 2a

.E k

- Two switches must be operated simultaneously for actuation.

g 2s Tn m

~.... ~.... -

TABLE 3.3-3 (Continued) y ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION 3lE x

i MINIMUM c-TOTAL NO.

CHANNELS CHANNELS APPLICABLE

}

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION w

b.

Phase "B" Isolation 1)

Manual 2

1**

2 1,2,3,4 20 l

2)

Automatic 2

1 2

1,2,3,4 15 Actuation logic 3)

Containment 4

2 3

1,2,3 18 Pressure-High-High R'

c.

Containment Ventilation Isolation t',

1)

Manual 2

1 2

1,2,3,4 19*

l 2)

Automatic Isolation 2

1 2

1,2,3,4 15 Logic 3)

Containment Purge 2

1 1

1,2,3,4 19*

Air Exhaust Monitor Radioactivity-High g

- Two switches must be operated simultaneously for actuation.

E ar s

m

TABLE 3.3-3 (Continued)

TABLE NOTATION

Trip function may be bypassed in this MODE below P-11 (Pressurizer ggPressure Block of Safety Injection) setpoint.

Trip function automatically blocked above P-11 and may be blocked below gggwhen Safety Injection on Steam Line Pressure-Low is not blocked.

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

The provisions of Specification 3.0.4 are not applicable.

ACTION STATEMENTS ACTION 15 -

With the number of OPERABLE Channels one less than the Total Number of Channels, be in at least HOT STANDBY within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ; however, one channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.2.1.1 provided the other channel is OPERABLE.

ACTION 16 -

Deleted.

ACTION 17 -

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 place'd in the tripped a.

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

b.

The Minimum Channels OPERABLE requirements is met; however, the inoperable channel may be bypassed for l

up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of other channels per Specification 4.3.2.1.1.

ACTION 18 -

With the number of OPERABLE Channels one less than the Total Number of Channels, operation may proceed provided the inoperable channel is placed in the bypassed condition and the Minimum Channels OPERABLE requirement is met; one addi-tional channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for i

surveillance testing per Specification 4.3.2.1.1.

ACTION 19 -

With less than the Minimum Channels OPERABLE, operation may continue provided the containment purge supply and exhaust l

valves are maintained closed.

ACTION 20 -

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 the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SEQUOYAH - UNIT 1 3/4 3-22 Amendment No. /f73'/AU,168 i

_ TABLE 3.3-4 (Continued) 2 y

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS h

FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES i

c-3.

Containment Purge Air Exhaust

-3

-3 Monitor Radioactivity-High

-<8.5 x 10 pCi/cc

-<8.5 x 10 pCi/cc 4.

STEAM LINE ISOLATION a.

Manual Not Applicable Not Applicable b.

Automatic Actuation Logic Not Applicable Not Applicable c.

Containment Pressure--High-High 5 81 psig 12.9 psig 2

d.

Steam Line Pressure--Low

>600 psig steam line

>592.2 psig steam line pressure (Note 1) pressure (Note 1)

,s*

e.

Negative Steam Line Pressure

$100.0 psi (Note 2)

<107.8 psi (Note 2)

"4 Rate--High

~

m 5.

TURBINE TRIP AND FEEDWATER ISOLATION a.

Steam

.erator Water level--

<81% of narrow range

<81.7% of narrow range High-liign Instrument span each Instrument span each steam generator steam generator b.

Automatic Actuation Logic N. A.

N.A.

R ar O

!E m

TABLE 3.3-5 (Continued) i ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 10.

Station Blackout i

a.

Auxiliary Feedwater Pumps 1 60(11) 11.

Trip of Main Feedwater Pumps a.

Auxiliary Feedwater Pumps 1 60(11) i 12.

Loss of Power a.

6.9 kv Shutdown Board - Degraded

< 10(10) i Voltage or Loss of

~

Voltage 13.

RWST Level-Low Coincident with Containment Sump Level-High and Safety Injection a.

Automatic Switchover to

~

Containment Sump i 250 14.

Containment Purge Air Exhaust Radioactivity - High a.

Containment Ventilation Isolation i 10(6) i h

SEQUOYAH - UNIT 1 3/4 3-32 Amendment No. 2S/,/ R, 168

TABLE 4.3-2 (Continued) mE8 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION s

SURVEILLANCE REQUIREMENTS 1

CHANNEL MODES FOR WHICH E

CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE IS Z

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 w1

2) Automatic Actuation Logic N.A.

N.A.

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

g,

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 Purge Air S

R H

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

ar m

r

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

TABLE 4.3-2 (Continued) m h

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION Q

SURVEILLANCE REQUIREMENTS E

CHANNEL MODES FOR WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE IS C

FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED

[

4.

STEAM LINE ISOLATION a.

Manual N.A.

N.A.

R 1,2,3 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 Line Pressure--Low 5

R Q

1,2,3 e.

Negative Steam Line Pressure S

R Q

3 Rate--High 0

5.

TURBINE TRIP AND FEEDWATER ISOLATION a.

Steam Generator Water S

R Q

1,2,3 Level--High-High g

b.

Automatic Actuation Logic N.A.

N.A.

M(1) 1, 2, 3 6.

AUXILIARY FEEDWATER a.

Manual N. A.

N.A.

R 1,2,3 f

b.

Automatic Actuation Logic N.A.

N.A.

M(1) 1, 2, 3 k=0i

.~

(D

enE TABLE 3.3-6 8

RADIATION MONITORING INSTRUMENTATION I

MINIMUM CHANNELS APPLICABLE ALARM / TRIP MEASUREMENT E

INSTRUMENT OPERABLE MODES SETPOINT RANGE ACTION 1.

AREA MONITOR w

2

~I 4

a.

Fuel Storage Pool Area 1

1 00 mR/hr 10

- 10 mR/hr 26' 2.

PROCESS MONITORS

-3 7

a.

Containment Purge Air 1

1, 2, 3, 4 & 6 18.5 x 10 pCi/cc 10 - 10 cpm 28 b.

Containment E

i.

Gaseous Activity Y

7 l

RCS Leakage Detection 1

1, 2, 3 & 4 N/A 10 - 10 cpm 27 ii.

Particulate Activity 7

RCS Leakage Detection 1

1, 2, 3 & 4 N/A 10 - 10 cpm 27 N

7

,g c.

Control Room Isolation 1

ALL MODES

< 400 cpm **

10 - 10 cpm 29 5

ee 5

With fuel in the storage pool or building k

- Equivalent to 1.0 x 10 -5 pCi/cc.

.s 9

CD s

TABLE 3.3-6 (Continued)

ACTION STATEMENTS

-ACTION 26 -

With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirement, perform area surveys of i

the monitored area with portable monitoring instrumentation at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 27 -

With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.6.1.

ACTION 28 -

With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specifications 3.9.9 (MODE 6) and 3.3.2.1 (MODES 1, 2, 3 and 4).

ACTION 29 -

With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirement, within I hour initiate and maintain operation of the control room emergency ventilation system in the recirculation mode of operation.

i SEQUOYAH - UNIT 1 3/4 3-41

, Amendment No.,04K/lMut 168

M TABLE 4.3-3 jj RADIATION HONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES FOR WHICH e

CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE IS gg INSTRUMENT CHECK CALIBRATION TEST REQUIRED El 1.

AREA MONITOR w

a.

Fuel Storage Pool Area S

R H

2.

PROCESS MONITORS a.

Containment Purge Air Exhaust 5

R H

1, 2, 3, 4 & 6 b.

Containment w

3; i.

Gaseous Activity l

cp RCS Leakage Detection S

R H

1, 2, 3, & 4 u

ii.

Particulate Activity RCS Leakage Detection S

R H

1, 2, 3 & 4 c.

Control Room Isolation S

R H

ALL MODES E

.if O

i:

((

"With fuel in the storage pool or building.

m w-

,%-a g

m 9

gi-

<+

es..

g y

,-ye

,gg--

y ig-y+

y er 1

,---y

y->w

+

mw

REFUELING OPERATIONS 1

l BASES 3/4 9.9 CONTAINMENT VENTILATION SYSTEM The OPERABILITY of this system ensures that the containment ventilation isolation penetrations will be automatically isolated upon detection of high radiation levels during containment purging operations.

The OPERABILITY of this system is required to restrict the release of radioactive material from the containment atmosphere to the environment.

3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL AND SPENT FUEL PIT The restrictions on minimum water level ensure that sufficient water depth is available to remove 99% of the assumed 10% iodine gap activity released from the rupture of an irradiated fuel assembly. The minimum water depth is consistent with the assumptions of the accident analysis.

3/4.9.12 AUXILIARY BUILDING GAS TREATMENT SYSTEM The limitations on the auxiliary building gas treatment system ensure that all radioactive material released from an irradiated fuel assembly will be filtered through the HEPA filters and charcoal adsorber prior to discharge Cumulative operation of the system with the heater on for to the atmosphere.

10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months over a 31 day period is sufficient to reduce tite buildup of moisture The OPERABILITY of this system and the on the adsorbers and HEPA filters.

resulting iodine removal capacity are consistent with the assumptions of the accident analyses.

ANSI N510-1975 will be used as a procedural guide for surveillance testing.

i B 3/4 9-3 Amendment No.

73'4', 168 SEQUOYAH - UNIT 1

$ra atogo 3\\

UNITED STATES 5 MA!

E NUCLEAR REGULATORY COMMISSION

&^ lf f o

WASHINGTON, D.C. 20556

%..r.s J

..+

TENNESSEE VALLEY AUTHORITY DOCKET N0. 50-328 SE000YAH NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.158 License No. DPR-79 i

1.

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

A.

The application for amendment by Tennessee Valley Authority (the licensee) dated August 27, 1991, and supplemented by letter dated November 6,1992, 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 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 l

been satisfied.

9 9

~

- r 1

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. DPR-79 is hereby amended to read as follows:

i (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.158, 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, to be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION wNL b

r~

s Frederick J. Heben, Director Project Directorate II-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: June 25,1993 i

ATTACHMENT TO LICENSE AMENDMENT NO.158 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 amendment number and contain marginal lines indicating the area of change.

REMOVE INSERT 3/4 3-17 3/4 3-17 3/4 3-19 3/4 3-19 3/4 3-22 3/4 3-22 3/4 3-26 3/4 3-26 3/4 3-32 3/4 3-32 3/4 3-35 3/4 3-35 3/4 3-36 3/4 3-36 3/4 3-41 3/4 3-41 3/4 3-42 3/4 3-42 3/4 3-43 3/4 3-43 B3/4 9-3 B3/4 9-3 P

O P

TABLE 3.3-3 (Continued) m ENGINEERED SAFETY FEAfURE ACTUATION SYSTEM INSTRUMENTATION 5

i MINIMUM e

TOTAL NO.

CHANNELS CllANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 3.

CONTAINMENT ISOLATION b.

Phase "B" Isolation 1)

Manual 2

1**

2 1,2,3,4 20 2)

Automatic 2

1 2

1,2,3,4 15 Actuation Logic 3)

Containment 4

2 3

1,2,3 18 Pressure-High-High c.

Containment Ventilation 3

Isolation

~n 1)

Manual 2

1 2

1,2,3,4 19*

[

2)

Automatic Isolation 2

1 2

1,2,3,4 15 Logic 3)

Containment Purge 2

1 1

1,2,3,4 19*

Air Exhaust !onitor Radioactivity-High g

- Two switches must be operated simultaneously for actuation.

1 ae F.

e m

m

~

TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION 5

x 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 1, 2, 3 17*

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 D

a.

Manual Initiation 2

1 2

1,2,3 24 Y

b.

Automatic Actuation 2

1 2

1,2,3 23 U

Logic c.

Main Steam Generator

'Jater Level--Low-Low N

i.

Start Motor-

=y Driven Pumps E

a.

Steam Gen.

3/Stm. Gen.

2/Stm. Gen.

1, 2, 3 36*

Water level--

in any in each Low-Low operating operating (Adverse)

Stm. Gen.

h b.

Steam Gen.

3/Stm. Gen.

2/Stm. Gen.

1,2,3 36*

Water level--

in any in each Low-Low operating operating (EAM)

Stm. Gen.

$g c.

RCS Loop AT 4(1/ loop) 2 3

1,2,3 37*

l CD

,.. ~,

I 1

i i

~

TABLE 3.3-3 (Continued)

TABLE NOTATION

rip function may be bypassed in this MODE below P-11 (Pressurizer T

ggPressure Block of Safety Injection) setpoint.

Trip function automatically blocked above P-11 and may be blocked below t

gggP-11 when Safety Injection on Steam Line Pressure-Low is not blocked.

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

The provisions of Specification 3.0.4 are not applicable.

ACTION STATEMENTS ACTION 15 -

With the number of OPERABLE Channels one less than the Total i

Number of Channels, be in HOT STANDBY within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ; however, one channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.2.1.1 provided the other channel is OPERABLE.

ACTION 16 -

Deleted.

ACTION 17 -

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 requirements is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of other channels per Specification 4.3.2.1.1.

ACTION 18 -

With the number of OPERABLE Channels one less than the Total Number of Channels, operation may proceed provided the inoperable channel is placed in the bypassed condition and the Minimum Channels OPERABLE requirement is met; one addi-tional channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for 9

surveillance testing per Specification 4.3.2.1.1.

ACTION 19 -

With less than the Minimum Channels OPERABLE, operation may continue provided the containment purge supply and exhaust l

valves are maintained closed.

ACTION 20 -

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 the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

i SEQUOYAH - UNIT 2 3/4 3-22 Amendment No. 55yE2,158 1

l

TABLE 3.3-4 (Continued)

MS ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS

?

E FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES

-3

-3 3.

Containment Purge Air Exhaust

-(8.5 x 10 pCi/cc

-<8.5 x 10 pCi/cc Monitor Radioactivity-High N

4.

STEAM LINE ISOLATION a.

Manual Not Applicable Not Applicable b.

Automatic Actuation Logic Not Applicable Not Applicable c.

Containment Pressure--High-High 1 81 psig 12.9 psig 2

d.

Steam Line Pressure--Low 2600 psig steam line 1592.2 psig steam line pressure (Note 1) pressure (Note 1)

M e.

Negative Steam Line Pressure

$ 00.0 psi (Note 2) 1107.8 psi (Note 2) 1 y

Rate--High 5.

TURBINE TRIP AND FEEDWATER ISOLATION a.

Steam Generator Water level--

<81% of narrow range

<81.7% of narrow range High-High Instrument span each Instrument span each steam generator steam generator b.

Automatic Actuation Logic N.A.

N.A.

3 3

2e

[

9z#

c; m

TABLE 3.3-5 (Continued)

ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 10.

Station Blackout a.

Auxiliary Feedwater Pumps 1 60(11) 11.

Trip of Main Feedwater Pumps a.

Auxiliary Feedwater Pumps 1 60(11) 12.

Loss of Power a.

6.9 kv Shutdown Board - Degraded

< 10(10)

Voltage or Loss of Voltage 13.

RWST Level-Low Coincident with Containment Sump level-High and Safety Injection a.

Automatic Switchover to Containment Sump i 250 14.

Containment Purae Air Exhaust Radioactivity - High a.

Containment Ventilation Isolation 1 10(6) l i

SEQUOYAH - UNIT 2 3/4 3-32

, Amendment No. Ig//gg,158

TABLE 4.3-2 (Continued) v, E

Ej ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION g$

SURVEILLANCE REQUIREMENTS 1

CHANNEL MODES FOR WHICH gj CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE IS q

FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED 3.

CONTAINMENT ISOLATION a.

Phase "A" Isolation

1) Hanual 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 u,

s

[

2) Automatic Actuation Logic N.A.

N.A.

M(1) 1, 2, 3, 4

!N

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 Purge Air 5

R M

1,2,3,4 Exhaust Monitor Radio-p activity-High 2e mee

g; TABLE 4.3-2 (Continued) 13 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SE SURVEILLANCE REQUIREMENTS CHANNEL MODES FOR WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE IS E

FUNCTIONAL UNIT

_ CHECK CALIBRATION TEST REQUIRED ta no 4.

STEAM LINE ISOLATION l

a.

Manual N.A.

N.A.

R 1,2,3 b.

Automatic Actuation Logic N.A.

N.A.

M(1) 1, 2, 3 c.

Containment Pressure--

S R

Q 1,2,3 High-High r

t d.

Steam Line Pressure--Low S

R Q

1, 2, 3 h$

e.

Negative Steam Line Pressure S

R Q

3 Rate--High u,

h' 5.

TURBINE TRIP AND FEEDWATER 4

ISOLATION a.

Steam Generator Water S

R Q

1,2,3 Level--High-High g{

b.

Automatic Actuation Logic N.A.

N.A.

M(1) 1, 2, 3

R 6.

AUXILIARY FEEDWATER R

S a.

Manual N.A.

N.A.

R 1,2,3 k

b.

Automatic Actuation Logic N.A.

N.A.

M(1) 1, 2, 3 k

. ~~

00

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

wEg TABLE 3.3-6 g

RADIATION MONITORING IN5TRUMENTATION x

MINIMUM c:

CHANNELS APPLICABLE ALARM / TRIP MEASUREMENT INSTRUMENT OPERABLE MODES SETPOINT RANGE ACTION N

1.

AREA MONITOR

-1 4

a.

Fuel Storage Pool Area 1

1200 mR/hr 10

- 10 mR/hr 26' 2.

PROCESS MONITORS

-3 7

a.

Containment Purge Air 1

1, 2, 3, 4 & 6 18.5 x 10 pCi/cc 10 - 10 cpm 28 y

b.

Containment y

i.

Gaseous Activity 7

I RCS Leakage Detection 1

1, 2, 3 & 4 N/A 10 - 10 cpm 27 fi.

Particulate Activity 7

RCS Leakage Detection 1

1, 2, 3 & 4 N/A 10 - 10 cpm 27 g'

7 c.

Control Room Isolation 1

ALL MODES i 400 cpm **

10 - 10 cpm 29 E

2e g

^ With fuel in the storage pool or building h

- Equivalent to 1.0 x 10 pCi/cc.

-5

=

t.J1 CD

TABLE 3.3-6 (Continued)

ACTION STATEMENTS i

ACTION 26 -

With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirement, perform area surveys of the monitored area with portable monitoring instrumentation at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 27 -

With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.6.1.

ACTION 28 -

With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specifications 3.9.9 (MODE 6) and 3.3.2 (MODES 1, 2, 3 and 4).

ACTION 29 -

With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirement, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months initiate and maintain operation of the control room emergency ventilation system in the recirculation mode of operation.

t l

1 1

SEQUOYAH - UNIT 2 3/4 3-42 Amendment No. diff,158

TABLE 4.3-3 My RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES FOR WHICH i

CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE IS g

INSTRUMENT CHECK CALIBRATION TEST REQUIRE'.

Z 1.

AREA MONITOR N

a.

Fuel Storage Pool Area S

R M

2.

PROCESS MONITORS a.

Containment Purge Air Exhaust S

R H

1, 2, 3, 4 & 6 b.

Containment w1 i.

Gaseous Activity RCS Leakage Detection S

R M

1, 2, 3, & 4 ii.

Particulate Activity RCS Leakage Detection S

R M

1, 2, 3 & 4 c.

Control Room Isolation 5

R H

ALL MODES aa ae "With fuel in the storage pool or building.

CD

t REFUELING OPERATIONS BASES 3/4.9.9 CONTAINMENT VENTILATION SYSTEM The OPERABILITY of this system ensures that the containment ventilation isolation penetrations will be automatically isolated upon detection of high radiation levels during containment purging operations. The OPERABILITY of this system is required to restrict the release of radioactive material from the containment atmosphere to the environment.

3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL AND SPENT FUEL PIT The restrictions on minimum water level ensure that sufficient water depth is available to remove 99% of the assumed 10% iodine gap activity released from the rupture of an irradiated fuel assembly.

The minimum water depth is consistent with the assumptions of the accident analysis.

3/4.9.12 AUXLIARY BUILDING GAS TREATMENT SYSTEM The limitations en the auxiliary building gas treatment system ensure i

that all radioactive material released from an irradiated fuel assembly will be filtered through the HEPA filters and charcoal adsorber prior to discharge to the atmosphere.

Cumulative operation of the system with the heater on for 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months over a 31 day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters.

The OPERABILITY of this system and the resulting iodine removal capacity are consistent with the assumptions of the accident analyses.

ANSI N510-1975 will be used as a procedural guide for surveillance testing.

r P

i j

j i

i SEQUOYAH - UNIT 2 B 3/4 9-3 Amendment No./121,158

ML20045F371

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