Text

Amends 182 & 174 to Licenses DPR-77 & DPR-79,respectively, Revising Setpoints & Time Delays for Auxiliary Feedwater Loss of Power & 6.9 Kv Shutdown Board loss-of-voltage & degraded-voltage Instrumentation
	ML20069E593
Person / Time
Site:	Sequoyah
Issue date:	05/24/1994
From:	Hebdon F; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20069E594	List: ML20069E593; ML20069E599;
References
	NUDOCS 9406070279
	Download: ML20069E593 (32)
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E UNITED STATES l'"'

^f NUCLEAR REGULATORY COMMISSION

,f' WASHINGTON, D.C. 20555-0001 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SE0V0YAH NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENS_E Amendment No. 182 License No. DPR-77 l.

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

A.

The application for amendment by Tennessee Valley Authority (the j

licensee) dated October 1,1993, and supplemented by letter dated 1

March 29, 1994, 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 1

defense and security or to the health and safety of the public; and l

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.

9406070279 940524-PDR ADOCK 05000327 i

P PDR l

'. 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 Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.182, 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 upon completion of the related plant modifications during the Unit 2 Cycle 6 refueling outage.

FOR THE NUCLEAR REGULATORY COMMISSION b(LL5 A-t n.

{y Frederick J. Hebdon, Director Project Directorate II-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation f

Attachment:

Changes to the Technical Specifications Date of Issuance:

tiay 24, 1994

ATTACHMENT TO LICENSE AMENDMENT NO.182 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 INSEBI 3/4 3-20 3/4 3-20 3/4 3-21 3/4 3-21 3/4 3-22 3/4 3-22 3/4 3-23 3/4 3-23 3/4 3-23a 3/4 3-23a 3/4 3-27a 3/4 3-27a 3/4 3-27b 3/4 3-27b 3/4 3-32 3/4 3-32 3/4 3-33a 3/4 3-33a 3/4 3-37 3/4 3-37 3/4 3-37a 3/4 3-37a 3/4 3-38 3/4 3 B3/4 7-2a B3/4 7-2a

~

TABLE 3.3-3 (Continued) o ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION 5

MINIMUM TOTAL NO.

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

e.

Loss of Power Start 1.

Voltage Sensors 3/ shutdown 2/ shutdown 3/ shutdown 1, 2, 3 35 board **

board **

2.

Load Shed Timer 2/ shutdown 1/ shutdown 2/ shutdown 1, 2, 3 35 board **

board **

f.

Trip of Main Feedwater Pumps Start Motor-Driven R

Pumps and Turbine

[

Driven Pump 1/ pump 1/ pump 1/ pump 1, 2 20*

i E

g.

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

h.

Auxiliary Feedwater Suction Transfer Time Delays 1.

Motor-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*

2a

.F O

C

.=

5w

- Unit 1 Shutdown Boards Only

TABLE 3.3-3 (Continued)

M ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION E

S MINIMUM g

TOTAL NO.

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

7. LOSS OF POWER w

a.

6.9 kv Shutdown Board

--Loss of Voltage 1.

Voltage Sensors 3/ shutdown 2/ shutdown 3/ shutdown 1, 2, 3, 4, 34 board board board 5####, 6####

2.

Diesel Generator 2/ shutdown 1/ shutdown 2/ shutdown 1, 2, 3, 4 34 Start and Load board baard board 5####, 6####

Shed Timer R

b.

6.9 kv Shutdown Board Degraded Voltage Y$

1.

Voltage Sensors 3/ shutdown 2/ shutdown 3/ shutdown 1, 2, 3, 4 34 board board board 5####, 6####

2.

Diesel Generator 2/ shutdown 1/ shutdown 2/ shutdown 1, 2, 3, 4 34 Start and Load board board board 5####, 6####

R Shed Timer 5

?+

3.

SI/ Degraded 2/ shutdown 1/ shutdown 2/ shutdown 1, 2, 3, 4 34 Voltage Logic board board board 2

P Enable Timer 8.

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INTERLOCKS a.

Pressurizer Pressure -

3 2

2 1,2,3 22a

~

P-ll/Not P-ll a

b.

Deleted 8

~

c.

Steam Generator 3/ loop 2/ loop 3/ loop 1, 2 22c y

Level P-14 any loop

TABLE 3.3-3 (Continued)

TABLE NOTATION

\\

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

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

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

1. 1. 1. When Associated Diesel Generator is required to be OPERABLE By LCO 3.8.1.2, "AC Sources-Shutdown." The Provisions of Specification 3.0.4 are not applicable.

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 H0T 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 test-ing 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 placed in the tripped condition a.

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

The Minimum Channels OPERABLE requirements is met; howeler, 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 inoper-able channel is placed in the bypassed condition and the Minimum Channels OPERABLE requirement is met; 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 4.3.2.1.1.

ACTION 19 -

With less than the Minimum Channels OPERABLE, operation may continue provided the containment purge supply and exhaust 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. 63, 141, 168, 182 l

TABLE 3.3-3 (Continued)

ACTION 21 -

With less than the Minimum Number of Channels OPERABLE, declare the associated auxiliary feedwater pump inoperable, 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 appro-priate ACTION statement (s) for those functions.

Functions to be evaluated are:

a.

Safety Injection Pressurizer Pressure Steam Line Pressure Negative Steam Line Pressure Rate l

b.

Deleted c.

Turbine Trip 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 et 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 chaanel to OPERABLE status within 48 hcurs 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 H0T 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 inoper-able and take the ACTION required by Specification 3.7.1.5.

ACTION 34 -

a.

With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to CPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or enter applicable Limiting Condition (s) For Operation and Action (s) for the associated diesel generator set made inoperable by the channel.

b.

With the number of OPERABLE channels less than the Total Number of Channels by more than one, restore all but one channel to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or enter applicable Limiting Condition (s) for Operation and Action (s) for the associated diesel generator set made inoperable by the channels.

SEQUOYAH - UNIT 1 3/4 3-23 Amendment No. 12, 63, 129, 141, 160, 182

TABLE 3.3-3 (Continued)

ACTION 35 -

a.

With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or enter applicable Limiting Condition (s) For Operation and Action (s) for the associated auxiliary feedwater pump made inoperable by the channel, b.

With the number of OPERABLE channels less than the Total Number of Channels by more than one, restore all but one channel to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or enter appli-cable Limiting Condition (s) For Operation and Action (s) for the associated auxiliary feedwater pump made inoperable by the channel.

ACTION 36 -

With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed 1

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.

Fcr the affected protection set, the Trip Time Delay for one affected steam generator (T is adjusted to match the Trip Time Delay for multiple aff)ected steam generators (T,)

within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

c.

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

ACTION 37 -

With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided that within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , for the affected protection set, i

the Trip Time Delays (T, justed)to 0% RTP. threshold power level for zer and T seconds time delay is ad ACTION 38 -

With the number of OPERABLE channels one less than the Total Number of Channels, STARTVP and/or POWER OPERATION may proceed provided that within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , for the affected protection set, i

the Steam Generator Water Level - Low-Low (EAM) channels trip setpoint is adjusted to the same value as Steam Generator Water Level - Low-Low (Adverse).

i SEQUOYAH - UNIT 1 3/4 3-23a Amendment No. 141, 160, 182

TABLE 3.3-4 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES

[

ii.

RCS Loop aT Equivalent to z

Power > 50% RTP w

Coincident with Steam 215.0% of narrow range 214.4% of narrow Generator Water Level--

instrument span range instrument span Low-Low (Adverse) and Containment Pressure (EAM)

$0.5 psig 50.6 psig or Steam Generator Water 210.7% of narrow range 210.1% of narrow range Level--Low-Low (EAM) instrument span instrument span d.

S.I.

See 1 above (all SI Setpoints)

~g e.

Loss of Power Start iy 1.

Voltage Sensors 25520 volts 25472 volts 2.

Load Shed Timer 1.25 seconds 1.25 0.09 seconds f.

Trip of Main Feedwater N.A.

N.A.

Pumps

,a E

g.

Auxiliary Feedwater Suction 2 2 psig (motor driven pump) 2 1 psig (motor driven pump)

E Pressure-Low 2 13.9 psig (turbine driven 2 12 psig (turbine driven pump) pump) h.

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

-(

5.5 seconds (turbine driven 5.5 seconds 0.55 seconds

~

pump)

(turbine driven pump)

-+

.h w

,s.

I 1

TABLE 3.3-4 (Continued) i ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS

{

FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES

[

7.

LOSS OF POWER z

~

a.

6.9 kv Shutdown Board Undervoltage Loss of Voltage 1.

Voltage Sensors 35520 volts 3 472 volts 5

2.

Diesel Generator Start and Load Shed Timer 1.25 seconds 1.25 +0.09 seconds b.

6.9 kv Shutdown Board-Degraded Voltage w2 1.

Voltage Sensors 6456 volts 36403.5 volts (dropout) m4 56626.5 volts (reset) i E

i

2.. Diesel Generator Start and Load Shed Timer 5300-seconds

$321 seconds t

3.

SI/ Degraded Voltage Logic

]

p Enable Timer

-10 seconds 10 seconds + 0.75 seconds ao E

8.

ENGINEERED SAFETY FEATURE 5

ACTUATION SYSTEM INTERLOCKS r

-i z

a.

Pressurizer Pressure g

1.

Not P-11, Automatic Unblock 5 1970 psig 5 1975.2 psig I

of Safety Injection on g

Increasing Pressure e

2.

P-11, Enable Manual Block of g 1962 psig 3 1956.8 psig Safety Injection on Decreasing

~

Pressure 5

~

TABLE 3.3-5 (Continued)

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

Loss of Power Start l

a.

Auxiliary Feedwater Pumps s 60""

11.

Trio of Main Feedwater Pumps a.

Auxiliary Feedwater Pumps s 60""

12.

Loss of Power j

a.

6.9 kv Shutdown Board - Degraded 5 10"'

Voltage or loss of Voltage

13. E_WST Level-Low Coincident with Containment Sump Level-Hiah and Safety In.iec tion a.

Automatic Switchover to Containment Sump s 250 14.

Containment Purae Air Exhaust Radioactivity - Hiah a.

Containment Ventilation Isolation s 10")

%l SEQUOYAH - UNIT 1 3/4 3-32 Amendment No. 29, 77, 168, 182

INSTRUMENTATION TABLE 3.3-5 (Continued)

TABLE NOTATION (7) Diesel generator starting and sequence loading delays not included.

Offsite power available.

Response time limit includes opening and closing of valves to establish SI path and attainment of discharge pressure for centrifugal charging pumps.

(8) Diesel generator starting and sequence loading delays not included.

Response time limit includes operating time of valves.

(9) Diesel generator starting and sequence loading delays included.

Response

time limit includes operating time of valves.

(10) The response time for loss of voltage is measured from the time the load shedding and diesel generator start signal is generated from the loss of voltage timer until the time full voltage is restored by the diesel.

The response time for degraded voltage is measured from the time the load shedding signal is generated, either from the degraded voltage or the SI enable timer, to the time full voltage is restored by the diesel.

The response time of the timers is covered by the requirements on their setpoints.

(11) The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 for the turbine-driven Auxiliary Feedwater Pump.

(12) The following valves are exceptions to the response times shown in the Table and will have the values listed in seconds for the initiating signals and the function indicated:

Valves:

FCV-67-89, -90, -105, -106 Response times:

7.b, 75")/85")

Valve:

FCV-70-141 1

Response times:

7.b, 70"'/80"'

(13) Containment purge valves only. Containment radiation monitor valves have a response time of 6.5 seconds or less.

(14) Does not include Trip Time Delays.

Response times noted include the transmitters, Eagle-21 process protection cabinets, solid state protec-tion cabinets, and actuation devices (up to and including pumps).

This i

reflects the response times necessary for THERMAL POWER in excess of 50%

RTP.

SEQUOYAH - UNIT 1 3/4 3-33a Amendment No. 29, 77, 82, 55, 106, 141, 182 i

TABLE 4.3-2 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE RE0VIREMENTS M

iE CHANNEL MODES FOR WHICH SE CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE 5E FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED c:

c.

Main Steam Generator Water

[{

Level--Low-Low 1.

Steam Generator Wr.tcr S

R Q

1, 2, 3 Level--Low-Low (f.dverse) 2.

Steam Generator Water S

R Q

1, 2, 3 Level--Low-Low (EAM) 3.

RCS Loop AT S

R Q

1, 2, 3 4.

Containment Pressure S

R Q

1, 2, 3 (EAM) d.

S.I.

See 1 above (all SI surveillance requirements) w d,

e.

Loss of Power Start u

1.

Voltage Sensors N.A.

R M

1,2,3 2.

Load Shed Timer N.A.

R N.A.

1, 2, 3 f.

Trip of Main Feedwater N.A.

N.A.

R 1, 2 L"

Pumps a

El g.

Auxiliary Feedwater Suction N.A.

R M

1, 2, 3 j

Pressure-Low

[=

h.

Auxiliary Feedwater Suction N.A.

R N.A.

1,2,3

.o Transfer Time Delays jo 7.

LOSS OF POWER R'

a.

6.9 kv Shutdown Board -

2 Loss of Voltage lt 1.

Voltage Sensors N.A.

R M

1, 2, 3, 4, S#, 6#

2.

Diesel Generator Start N.A.

R N.A.

1, 2, 3, 4, 5#, 6#

go and Load Shed Timer

TABLE 4.3-2 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION E

SURVEILLANCE REQUIREMENTS 5

CHANNEL MODES FOR WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE E

FUNCTIONAL UNIT CHECK CALIBRATION TEST RE0UIRED b.

6.9 kv Shutdown Board -

Degraded Voltage 1.

Voltage sensors N.A.

R M

1, 2, 3, 4, 5#, 6#

2.

Diesel Generators N.A.

R N.A.

1, 2, 3, 4, 5#, 6#

Start and Load Shed Timer 3.

SI/ Degraded Voltage N.A.

R N.A.

1, 2, 3, 4 R

Logic Enable Timer a

i' 8.

ENGINEERED SAFETY FEATURE "J

ACTUATION SYSTEM INTERLOCKS a.

Pressurizer Pressure, N.A.

R(2)

N.A.

1, 2, 3 P-11/Not P-11 Eg b.

Deleted 5g c.

Steam Generator N.A.

R(2)

N.A.

1, 2 Level, P-14 5

9.

AUTOMATIC SWITCH 0VER TO CONTAINMENT SUMP a.

RSWT Level - Low S

R Q

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

R Q

1,2,3,4

~

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

O

]

b.

Automatic Actuation Logic N.A.

N.A.

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

{3

'a

~

TABLE 4.3-2 (Continued)

~

TABLE NOTATION When associated diesel generator is required to be OPERABLE by LC0 3.8.1.2, "AC Sources - Shutdown."

(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 1 3/4 3-38 Amendment No. 47, 182

PLANT SYSTEMS BASES because of a main steam line or feedwater line break and a single failure of the B-train motor driven AFW pump.

The two redundant sources must be aligned such that 5. I steam generator source is open and operable and the No. 4 steam generator source is closed and operable.

For instances where one train of emergency raw cooling water (ERCW) is declared inoperable in accordance with technical specifications, the AFW turbine-driven pump is considered operable since it is supplied by both trains of ERCW.

Similarly, the AFW turbine-driven pump is considered operable when one train of the AFW loss of power start function is declared inoperable in accordance with technical specifications because both 6.9 kilovolt shutdown board logic trains supply this function.

This position is consistent with American National Standards Institute /ANS 58.9 requirements (i.e., postulation of the failure of the opposite train is not required while relying on the TS limiting condition for operation).

3/4.7.1.3 CONDENSATE STORAGE TANK The OPERABILITY of the condensate storage tank with the minimum water volume ensures that sufficient water is available to maintain the RCS at HOT l

STANOBY conditions for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months with steam discharge to the atmosphere concur-rent with total loss of off-site power.

The contained water volume limit includes an allowance for water not useatle because of tank discharge line location or other physical characteristics.

SEQUOYAH - UNIT 1 B 3/4 7-2a Amendment No. 115, 155, 182

%g s

s S

UNITED STATES 5"

4!

NUCLEAR REGULATORY COMMISSION

,/

WASHINGTON, D.C. 2055W1 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SE0VOYAH NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.174 License No. OPR-79 1.

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

A.

The application for amendment by Tennessee Valley Authority (the licensee) dated October 1, 1993, and supplemented by letter dated March 29, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissiun'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 been satisfied.

____._m._

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:

(2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.174, are hereby incorporated in the license.

The licensee shall operate the facilicy in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance, to be implemented upon completion of the related plant modifications during the Unit 2 Cycle 6 refueling outage.

FOR THE NUCLEAR REGULATORY COMMISSION (L uT N 7th7 g

Frederick J. Hebdon, 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: lby 24, 1994 n

~,,--~v

,c e

1 ATTACHMENT TO LICENSE AMENDMENT NO.174 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.

RWQyl INSERT 3/4 3-20 3/4 3-20 3/4 3-21 3/4 3-21 3/4 3-22 3/4 3-22 3/4 3-23 3/4 3-23 3/4 3-23a 3/4 3-23a 3/4 3-27a 3/4 3-27a 3/4 3-27b 3/4 3-27b 3/4 3-32 3/4 3-32 3/4 3-33a 3/4 3-33a 3/4 3-37 3/4 3-37 3/4 3-38 3/4 3-38 3/4 3-39 3/4 3-39 B3/4 7-2a B3/4 7-2a

TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION 5

MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE' FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES SCJIGN z

Z e.

Loss of Power Start m

1.

Voltage Sensors 3/ shutdown

'2/ shutdown 3/ shutdown 1, 2, 3 35 board **

board **

2.

Load Shed Timer 2/ shutdown 1/ shutdown 2/ shutdown 1, 2, 3 35 board **

board **

bcard**

f.

Trip of Main Feedwater Pumps Start Motor-Driven R

Pumps and Turbine

[

Driven Pump 1/ pump 1/ pump 1/ pump 1, 2 20*

t E

g.

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

h.

Auxiliary Feedwater Suction Transfer Time Delays 1.

Motor-Driven

[

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

h 2.

Turbine-Driven S

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

.E O

P c-

- Unit 2 Shutdown Boards Only

TABLE 3.3-3 (Continued)

Mjg ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION S?!!

MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION c:5

-d

7. LOSS OF POWER m

a.

6.9 kv Shutdown Board

--Loss of Voltage 1.

Voltage Sensors 3/ shutdown 2/ shutdown 3/ shutdown 1, 2, 3, 4, 34 board board board 5####, 6####

2.

Diesel Generator 2/ shutdown 1/ shutdown 2/ shutdown 1, 2, 3, 4 34 Start and Load board board board 5####, 6####

Shed Timer M

b.

6.9 kv Shutdown Board Y'

Degraded Voltage

~

1.

Voltage Sensors 3/ shutdown 2/ shutdown 3/ shutdown 1, 2, 3, 4 34 board board board 5####, 6####

2.

Diesel Generator 2/ shutdown 1/ shutdown 2/ shutdown 1, 2, 3, 4 34 Start and Load board board board 5####, 6####

S[

Shed Timer a

EI 3.

SI/ Degraded 2/ shutdown 1/ shutdown 2/ shutdown 1, 2, 3, 4 34 E

Voltage Logic board board board

{

Enable Timer

?

.E W

fa l

~

1 5 TABLE 3.3-3 (Continued)

TABLE NOTATION

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

1. Trip function automatically blocked above P-11 and may be blocked below P-ll when Safety Injection on Steam Line Pressare-Low is not blocked.

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

1. 1. 1. When Associated Diesel Generator is required to be OPERABLE By LC0 3.8.1.2, "AC Sources-Shutdown." The Provisions of Specification 3.0.4 are not applicable.

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 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 test-ing 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 Speci fication 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 inoper-able channel is placed in the bypassed condition and the Minimum Channels OPERABLE requirement is met; 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 Speci fication 4.3.2.1.1.

ACTION 19 -

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

SEQUOYAH - UNIT 2 3/4 3-22 Amendment No. 55, 132, 158, 174 a

TABLE 3.3-3 (Continued)

ACTION 21 -

With less than the Minimum Number of Channels OPERABLE, declare the associated auxiliary feedwater pump inoperable, 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 appro-priate ACTION statement (s) for those functions.

Functions to be evaluated are:

a.

Safety Injection Pressurizer Pressure Steam Line Pressure Negative Steam Line Pressure Rate b.

Deleted c.

Turbine Trip Steam Generator Level High-High Feedwater Isolation Steam Generator Level High-High l

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 H0T 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 inoper-able and take the ACTION required by Specification 3.7.1.5.

ACTION 34 -

a.

With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or enter applicable Limiting Condition (s) For Operation and Action (s) for the associated diesel generator set made inoperable by the channel, b.

With the number of OPERABLE channels less than the Total Number of Channels by more than one, restore all but one i

channel to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or enter I

applicable Limiting Condition (s) for Operation and i

Action (s) for the associated diesel generator set made inoperable by the channels.

SEQUOYAH - UNIT 2 3/4 3-23 Amendment No. 55, 116, 132, 150, 174

TABLE 3.3-3 (Continued)

ACTION 35 -

a.

With the number of OPEPABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or enter applicable Limiting Condition (s) For Operation and Action (s) for the associated auxiliary feedwater pump made inoperable by the channel.

b.

With the number of OPERABLE channels less than the Total Number of Channels by more than one, restore all but one channel to OPERABLE status within I hour or enter appli-cable Limiting Condition (s) For Operation and Action (s) for the associated auxiliary feedwater pump made inoperable by the channel.

ACTION 36 -

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.

For the affected protection set, the Trip Time Delay for one affected steam generator (T is adjusted to match the Trip Time Delay for multiple aff)ected steam generators (T,)

within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

c.

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

ACTION 37 -

With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided that within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , for the affected protection set, the Trip Time Delays (T,djuste[)to 0% RTP.

and T threshold power level for zero seconds time delay is a ACTION 38 -

With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided that within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , for the affected protection set, the Steam Generator Water Level - Low-Low (EAM) channels trip setpoint is adjusted to the same value as Steam Generator Water Level - Low-Low (Adverse).

SEQUOYAH - UNIT 2 3/4 3-23a Amendment No. 132, 150, 174

TABLE 3.3-4 (Continued) m iE ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS S!

$E FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES i

c; ii. RCS Loop aT Equivalent to "j

Power > 50% RTP Coincident with Steam 215.0% of narrow range 214.4% of narrow Generator Water Level--

instrument span range instrument span Low-Low (Adverse) and Containment Pressure (EAM) 10.5 psig 10.6 psig or Steam Generator Water 210.7% of narrow range 110.1% of narrow range Level--Low-Low (EAM) instrument span instrument span d.

S.I.

See 1 above (all SI Setpoints) w1 e.

Loss of Power Start w

4 L'

l.

Voltage Sensors 15520 volts 25472 volts 2.

Load Shed Timer 1.25 seconds 1.25 0.09 seconds

!f f.

Trip of Main Feedwater N.A.

N.A.

g[

Pumps 3g g.

Auxiliary Feedwater Suction 1 2 psig (motor driven pump) 2 1 psig (motor driven pump)

Pressure-Low 2 13.9 psig (turbine driven 2 12 psig (turbine driven pump) z P

pump) h.

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

.P 5.5 seconds (tur :ne driven 5.5 seconds 10.55 seconds g-pump)

(turbine driven pump)

U F

/

I l

TABLE 3.3-4 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS j

FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES

.i 7.

LOSS OF POWER E

Z a.

6.9 kv Shutdown Board Undervoltage Loss of Voltage m

1.

Voltage Sensors 35520 volts 35472 volts 2.

Diesel Generator Start and Load Shed Timer 1.25 seconds 1.25 10.09 seconds b.

6.9 kv Shutdown Board-Degraded Voltage I

1.

Voltage Sensors 6456 volts 36403.5 volts (dropout)

I w

$6626.5 volts (reset) e i

h 2.

Diesel Generator Start anu Load Shed Timer

<300 seconds

$321 seconds 3.

SI/ Degraded Voltage Logic j

Enable-Timer 10 seconds 10 seconds 1 0.75 seconds

<=

8.

ENGINEERED SAFETY FEATURE 5

ACTUATION SYSTEM INTERLOCKS z

?

a.

Pressurizer Pressure 1.

Not P-ll, Automatic Unblock 5 1970 psig 5 1975.2 psig of Safety Injection on m*

Increasing Pressure I

b 2.

P-ll, Enable Manual Block of 3 1962 psig

't 1956 8 psig Safety Injection on Decreasing Pressure C

e n --

m

TABLE 3.3-5 (Continued)

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

10. Loss of Power Start l

a.

Auxiliary Feedwater Pumps s 60(")

11.

Trio of Main Feedwater Pumos a.

Auxiliary Feedwater Pumps s 60(")

12.

Loss of Power 0) a.

6.9 kv Shutdown Board - Degraded

< 10 Voltage or loss of Voltage 13.

RWST Level-Low Coincident with Containment Sumo level-Hiah and Safety Inh etion a.

Automatic Switchover to Containment Sump s 250 14.

Containment Purae Air Exhaust Radioactivity - Hiah a.

Containment Ventilation Isolation s 10")

SEQU0YAH - UNIT 2 3/4 3-32 Amendment No. 18, 68, 158, 174

r I

i INSTRUMENTATION TABLE 3.3-5 (Continued)

TABLE NOTATION (7) Diesel generator starting and sequence loading delays not included. Offsite power available.

Response time limit includes opening and closing of valves l

to establish SI path and attainment of discharge pressure for centrifugal charging pumps.

(8) Diesel generator starting and sequence loading delays not included. Response time limit includes operating time of valves.

(9) Diesel generator starting and sequence loading delays included.

Response

time limit includes operating time of valves.

(10) The response time for loss of voltage is measured from the time the load shedding and diesel generator start signal is generated from the loss of voltage timer until the time full voltage is restored by the diesel.

The response time for degraded voltage is measured from the time the load shed-ding signal is generated, either from the degraded voltage or the SI enable timer, to the time full voltage is restored by the diesel.

The response time of the timers is covered by the requirements on their setpoints.

(11) The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 for the turbine-driven Auxiliary Feedwater Pump.

(12) The following valves are exceptions to the response times shown in the Table and will have the values listed in seconds for the initiating signals and the function indicated:

Valves:

FCV-67-89, -90, -105, -106 Response times:

7.b, 75(8)/85*

Valve:

FCV-70-141 Response times:

7.b, 70(8'/80""

(13) Containment purge valves only.

Containment radiation monitor valves have a 4

response time of 6.5 seconds or less.

(14) Does not include Trip Time Delays.

Response times noted include the transmitters, Eagle-21 process protection cabinets, solid state protection cabinets, and actuation devices (up to and including pumps). This reflects the response times necessary for THERMAL POWER in excess of 50% RTP.

SEQUOYAH - UNIT 2 3/4 3-33a Amendment No. 18, 47, 68, 174, 96, 132, 73 e

e TABLE 4.3-2 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REOUIREMENTS CHANNEL MODES FOR WHICH jE 5@

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

Main Steam Generator Water 25 Level--Low-Low

^*

1.

Steam Generator Water S

R Q

1, 2, 3 Level--Low-low (Adverse) 2.

Steam Generator Water S

R Q

1, 2, 3 Level--Low-Low (EAM) 3.

RCS Loop AT S

R Q

1, 2, 3 4.

Containment Pressure S

R Q

1, 2, 3 (EAM) d.

S.I.

See 1 above (all SI surveillance requirements) 2l e.

Loss of Power Start 1.

Voltage Sensors N.A.

R M

1, 2, 3

~

2.

Load Shed Timer N.A.

R N.A.

1, 2, 3 f.

Trip of Main Feedwater N.A.

N.A.

R 1, 2 gr Pumps EL g.

Auxiliary Feedwater Suction N.A.

R M

1,2,3 m

C Pressure-Low a

[

h.

Auxiliary Feedwater Suction N.A.

R N.A.

1, 2, 3 Transfer Time Delays

.o

_Ed 7.

LOSS OF POWER a.

6.9 kv Shutdown Board -

f" Loss of Voltage kh 1.

Voltage Sensors N.A.

R M

1, 2, 3, 4, 5#, 6#

2.

Diesel Generator Start N.A.

F, N.A.

1, 2, 3, 4, 5#, 6#

2d and Load Shed Timer

o-TABLE 4.3-2 (Continued)-

v, E

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION k

SURVEILLANCE REQUIREMENTS CHANNEL MODES FOR WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE E

FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED b.

6.9 kv Shutdown Board -

~

Degraded Voltage 1.

Voltage sensors N.A.

R M

1, 2, 3, 4, 5#, 6#

2.

Diesel Generators N.A.

R N.A.

1, 2, 3, 4, 5#, 6#

Start and Load Shed Timer 3.

SI/ Degraded Voltage N.A.

R N.A.

1, 2, 3, 4 g

logic Enable Timer y

8.

ENGINEERED SAFETY FEATURE g

ACTUATION SYSTEM INTERLOCKS a.

Pressurizer Pressure, N.A.

R(2)

N.A.

1,2,3 P-ll/Not P-ll F

3 b.

Deleted

?g c.

Steam Generator N.A.

R(2)

N.A.

1, 2 Level, P-14

?

9.

AUTOMATIC SWITCHOVER TO g$

CONTAINMENT SUMP Og a.

RSWT Level - Low S

R Q

1,2,3,4 COINCIDENT WITH C

Containment Sump Level - High S

R Q

1, 2, 3, 4

?

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

M b.

Automatic Actuation Logic N.A.

N.A.

M(1) 1, 2, 3, 4

4 TABLE 4.3-2 (Continued)

TABLE NOTATION When associated diesel generator is required to be OPERABLE by LC0 3.8.1.2, "AC Sources - Shutdown."

(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. 39,174

4

~

PLANT SYSTEMS BASES AUXILIARY FEEDWATER SYSTEM (continued) because of a main steam line or feedwater line break and a single failure of the B-train motor driven AFW pump. The two redundant sources must be aligned such that No. 1 steam generator source is open and operable and the No. 4 steam generator source is closed and operable.

For instances where one train of emergency raw cooling water (ERCW) is declared inoperable in accordance with technical specifications, the AFW turbine-driven pump is considered operable since it is supplied by both trains of ERCW.

Similarly, the AFW turbine-driven pump is considered operable when one train of the AFW loss of power start function is declared inoperable in accordance with technical specifications because both 6.9 kilovolt shutdown board logic trains supply this function. This position is consistent with American National Standards Institute /ANS 58.9 requirements (i.e., postulation of the failure of the opposite train is not required while relying on the TS limiting condition for operation).

3/4.7.1.3 CONDENSATE STORAGE TANK The OPERABILITY of the condensate storage tank with the minimum water volume ensures that sufficient water is available to maintain the RCS at HOT STANDBY conditions for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months with steam discharge to the atmosphere concur-rent with total loss of off-site power. The contained water volume limit includes an allowance for water not useable because of tank discharge line location or other physical characteristics.

SEQUOYAH - UNIT 2 B 3/4 7-2a Amendment No. 105, 174

.., ~

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