Text

Proposed Tech Specs,Incorporating Correction of Various Editorial Errors That Have Been Identified in SQN TSs
	ML20087D274
Person / Time
Site:	Sequoyah
Issue date:	08/07/1995
From:	; TENNESSEE VALLEY AUTHORITY
To:	;
Shared Package
ML20087D257	List: ML20087D255; ML20087D274;
References
	NUDOCS 9508100257
	Download: ML20087D274 (48)
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'(2) TVA'shall maintain intr rim emergency support facilities' (Technical Support .

Center, Operations Support Center and the Emergency Operations Facility) ,

until the final f acilities are complete. ,

1. Relief and Safety Valve Test Reauirements (Section 22.2; ll.D 1) y TVA shall conform to the results of the EPRI test program. TVA shall -

provide documentation for qualifying (a) reactor coolant system relief and r safety valves, (b) piping and supports; and (c) block valves in accordance with the review schedule given in SECY 81491 as approved by the' -;

Commission.

(24) Comoliance with Reaulatorv Guide 1.97 TVA shallimplement modifications necessary to comply with Revision 2 of Regulatory Guido 1.97, " Instrumentation for Light Water Cooled Nuclear Power Plants to Assess Plant Conditions During and Following An Accident," dated December 1980 by startup from the Unit 2 Cycle 4 refueling outage.

5 r il nc I ter al & ter ion R197 he e[or a ei[ter'i or o[e rv illa ce req ire e s ' e tif' d ' te [

lic ns .e' re ues for s vei a e ' te val x nsi n te v ,m er , 4 all ext nd t O to r , 9,t c 'nci w' h C ci f li g u g.Te te in r i al no e ee a t tal of .5 o h fo 1- nt s voi a e, 8 o th for 3 mo h rv ill n s an 7 .5 n s'

r 4- on s rv illa c . . -

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D. Exemptions from certain requirements sf Ap'pendices G and J to 10 CFR Part 50 are described in the Office of Nuclear Reactor Regulation's Safety Evaluation Report, Supplements No.1. These exemptions are authorized by law and,will not endanger life or property or the common defence and security and are otherwise in the public interest.

The exemptions are, therefore, hereby granted. The granting of these exemptions are authorized with the issuance of the License for Fuel Loading and Low Power Testing, 3 dated February 29,1980. The facility will operate, to the extent authorized herein, Act, .

and the regulations of the Commission. ' Additional exemptions are listed in 'l AE .

Attachment 1.

E. . Physical Protection The licensee shall fully implement and maintain in effect all provisions of the l Comrnission approved physical security, guard training and qualification, and safeguards- l contingency plans including amendments made pursuant to provisions of the l Miscellaneous Amendments and Search Requirements revision to.10 CFR 73.55 l (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). l' The Safeguards Contingency Plan is incorporated into the Physical Security Plan. The -l plans, which contain Safeguards Information protected under 10 CFR 73.21, are . - l R77 entitled: "Sequoyah Physical Security Plan," with revisions submitted through 'l -

November 23,1987; and "Sequoyah S'e curity Personnel Training and Qualification Plan," l.

with revisions submitted through April 16,1987. Changes made in accordance with l 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein. l l January 3,-1995 '!

Amendment No.-193 1 9508100257 950807 !

PDR ADOCK 05000327 P PDR

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T :INDEX LIMITING-CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS .

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'SECTION PAGE'

'7

+

J/4.6.3 CONTAINMENT ISOLATION VALVES..... ....... ................ 3/4 6-17 3/4.6.4 COMBUSTIBLE GAS CONTROL Hydrogen Analyzers ........................'............... '3/4 6-24' .

lectrir N edir h flygawa MmcKnew Sysrem . . . . . . . . ,. . . . . .

6-

. F, 3/4.6.5 ntt. M SED -

A 3/4t,-zsy, Ice Bed................................................... 3/4 6-26_

Ice Bed Temperature Monitoring System..................... 3/4 6-28 I ce Co nden s e r Doo rs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4.6-29 Inlet Door Position Monitoring System..................... 3/4.6-31 Divider Barrier Personnel Access Doors and .

Equipment Hatches....................................... 3/4 6-32i Containment Air Return Fans............................... 3/4 6-33

$6 dim Floor Drains.............................................. 3/4 6 Refueling Canal 0 rains.................................... 3/4 6 ,

Divider Barrier Sea 1...................................... 3/4.6 -3/4.6.6' VACUUM RELIEF VALVES...................................... 3/4 6-38 3/4.7 PLANT SYSTEMS 3/4.7.1- TURBINE CYCLE Safety Va1ves............................................. 3/4.7-1 Auxiliary Feedwater System........... .................... 3/4 7-5 3 Condensate Storage Tank..............:.................... 3/4 7-7 Activity.................................................. 3/4 7-8:

Main Steam Line Isolation Va1ves............. . ............ 3/4 7 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION............ 3/4 7-11 '

3/4.7.3 COMPONENT COOLING WATER SYSTEM............................. 3/4l7 3/4.7.4 ESSENTIAL RAW COOLING WATER SYSTEM 1 Essential Raw Cooling Water System....................... 3/4 7-13 j u

R120 .l

.SEQUOYAH -' UNIT 1 VIII Amendment June 1, 19 [116 I 1

Nj( , E .y -

l INDEX j i

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS PAGE SECTION Motor. 0perated Valves Thermal Overload Protection. . . . . . . . . 3/4 8-)(/

g R65 ,

Isolation 0evices......................................... 3/4 8-p q 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION.........y............................. 3/4 9-1 3/4.9.2 INSTRUMENTATION.. ........................................ 3/4 9-2

- 3/4.9.3 DECAY TIME................................................ 3/4 9-3 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS......................... 3/4 9-4 3/4.9.5 COMMUNICATIONS............................................ 3/4 9-5 3/4.9.6 MANIPULATOR CRANE......................................... 3/4 9-6 3/4.9.7 CRANE TRAVEL - SPENT FUEL PIT AREA........................ 3/4 9-7 3/4.9.8 . RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION ,

All Water Levels.......................................... -3/4 9-8 Low Water Level.......................................... 3/4 9-8a' 3/4.9.9 CONTAINMENT. VENTILATION ISOLATION SYSTEM. . . . . . . . . . . . . . . . . . 3/4 9-91 ,

3/4.9.10 WAT ER L EVE L- R E ACTO R VE S S E L. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 9-10 3/4.9.11 SPENT FUEL PIT WATER LEVEL................................ 3/4 9-11 3/49.12 AUXILIARY BUILDING GAS TREATMENT SYSTEM................... 3/4 9-12 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTOOWN MARGIN........................................... 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS..... 3/4 10-2 3/4.10.3

PHYSICS TESTS............................................. .3/4 10-3 3/4.10.4 REACTOR C00LANT. LOOPS..................................... 3/4 10-4 3/4.10.5 POSITION INDICATION SYSTEM - SHUTD0WN..................... ~3/4 10-5 1

, ~l October :22, 1987 i X Amendment No. 61 4 SEQUOYAH - UNIT 1 i

J

TABLE 2.2-1 (Continued)

N REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS E

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s NOTATION (Continued) e g NOTE 5: Trip Tiine Delay - Steam Generator Water Level ~~ Low-Low x

[ T, = -0.00583)(P)3 + (0.735)(P)2 - (33.560)(P) + 649.5 0.99 SEC$.

T,=. -0.00532)(P)3 + (0.678)(P)2 - (31.340)(P) + 589.5 l 0. 9 seg.

Where:

P = RCS Loop AT Equivalent to Power (% RTP). P 5,50% RTP R145 T = Time delay for Steam Generator Water level - Low-Low 8

Reactor Trip, one Steam Generator. affected. [.5EcS.)

T" = Time delay for Steam Generator Water Level -- Low-Lo

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Reactor Trip, two or more Steam Generators affected. (Sets.)

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. REACTIVITY CONTROL SYSTEMS p0SITION INDICATION SYSTEMS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.3.2 The shutdown and control rod position indication system and the

' the control rod positions within i 12 steps. demand position indica APPLICABILITY: MODES 1 and 2.

ACTION:

a.

With either: a maximum of one rod position indicator per bank inoperable 1 R122 by the movable incore detectors at least once per 8 hou immediately after any motion of the non-indicating rod which exceeds 24 steps in one direction since the last determination of the rod's position, or 2.

Reduce within THERMAL POWER to less than 50% of RATED THERMAL P 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

b.

With either:a maximum of one demand position indicator per bank inoperable 1.

Verify that all rod position indicators for the affected bank are OPERABLE and that the most withdrawn rod and the least ,

withdrawn rod of the bank are within a maximum of 12 steps of each other at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , or 2.

Reduce within THERMAL POWER to less than 50% of RATED THERMAL P 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . ,

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l SEQUOYAH - UNIT 1 3/4 1-17 Amendment No. 118 June 23, 1989 6 moeuske

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3/4.2 POWER DISTRIBUTION LIMITS. ,{

'l 3/4.2.1' AXIAL FLUX' DIFFERENCE (AFD) R23 LIMITING CONDITION FOR OPERATION 3.2.1-- The indicated AXIAL FLUX DIFFERENCE (AFD) shall be maintained within:

the limits specified in the COLR. - lR15' APPLICABILITY: MODE 1 above 50% RATED THERMAL POWER

R23-ACTION:

a. With the indicated AXIAL FLUX DIFFERENCE outside'of the limits speci- R15?

fied in the COLR;

1. Either restore the indicated AFD to within the limits within IR151 8

15 minutes, or

2. Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 30 minutes and reduce the Power Range Neutron Flux-High R23 Trip setpoints to less than or equal to 55 percent of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ,

b. THERMAL POWER shall not be increased above 50% of RATED THERMAL POWER unless the indicated AFD is within the limits specified in the- l R151 COLR.

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W 4 Set SteconL Test' GCEPilos) .3.10. 2-A A i 3/4 2-1 Amendment No. 19,=155 SEQUOYAH - UNIT l' ..

OCT 23 EB1

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1 TABLE 3.3-1 (Centinued)

TABLE NOTATION n i With the reactor trip system breakers in the closed' position and the control l od drive system capable of rod withdrawal, and fuel in the reactor vessel.

fs M e a d e ri ed ti .

The provisions of Specification 3.0.4 are not applicable.

Source Range outputs may be disabled above the P-6 (Block of Source Range Reactor Trip) setpoint. R140 ACTION STATEMENTS ACTION 1 -

With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or ce in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and/or open the reactor trip breakers.

ACTION 2 -

With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and POWER OPERATION may proceed provided the following conditions are satisfied:

a.

The inoperable channel is placed in the tripped condition R51 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b. h51 The Minimum Channels OPERABLE requirement is met; however, I 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 R145 for surveillance testing of other channels per Specification 4.3.1.1.1.

c.

The QUADRANT Technical POWER Specification TILT RATIO is monitored in accordance w 3.2.4.

R139 l

l SEQUOYAH - UNIT 1 MAY 161990 3/4 3-5 Amendment No. 47,135,136, 141

s

'I TABLE 3.3-1 (Continued)

ACTION 11 -

With the number of OPERABLE channels one less than the Tota Number of Channels, STARTUP and/or POWER OPERATION may procee R145 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)

ACTION 12 -

With the number of channels OPERABLE one less than required by H the Minimum Channels OPERABLE re STANOBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however,quirement, one channel may be be in bypassed at least HOT for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.1.1.1 provided the other channel is OPERABLE.

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m. r uo er f an el E BL ch n s ne/ s h o 1 a wi te E P E 1 P- ( o V t o lo P er

) op ra e a el in e ri e c ea or r ps st i , e he i . t,hi our ,

/ .j/opA aElon ,a co in NI AL AT u i p fo m e/o t6 x re ui ed /

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ACTION 14 -

/ /

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

ACTION 15 -

With one of the diverse trip features (undervoltage or shunt trip-attachment) inoperable, restore it to operable status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the breaker inoperable and apply ACTION 12.

The breaker shall not be bypassed while one of the diverse trip features is inoperable except for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for performing maintenance to restore the breaker to OPERABLE status.

ACTION 16 -

With the number of OPERABLE channels one less than the min channels operable requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or open the reactor trip breakers within the next hour.

SEQUOYAH - UNIT 1 3/4 3-8 MAY 161990 Amendment No. 54, 141

. TABLE 3.3-3 (Continued) .

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

Trip function automatically blocked above P-11 and may be blocked below R145 hen Safety Injection on. Steam Line Pressure-Low is not blocked.

t 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 foilowing 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 R145 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 R145 '

proceed provided the following conditions are satisfied:

a. The inoperable channel is p U ed 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- R145 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 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 lali 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. /f/7//747,168 June 25, 1993

[

TABLE 3.3-7 SEISMIC MONITORING INSTRUMENTATION MINIMUM MEASUREMENT INSTRUMENTS IiSTRUMENTS AND SENSOR LOCATIONS RANGE OPERABLE If Triaxial Time-History Accelerographs

a. 0-XT-52-75A, Containment, Elev. 734 0-1.0g _1

b. 0-XT-52-758, Annulus, Elev 680 0-1.0g la R85

c. 0-XR-52-77, Diesel Building, 0-1.0g 1 Elev. 72?.

2. Triaxial Pea Accelerographs 84

a. 0-XR Containment, SIS Pipe, Elev. 70 0-5.0g 1 R85-

b. 0-XR-52-83, Containment, UHI Pipe, Elev. 706 0-5.0g I

c. 0-XR-52 ontrol Building, MCR, Panel 0-M-25, Elev. 739 0-5.0g 1

3. Biaxial Seismic Switches

a. 0-XS-52-79, Annulus, Elev. 680 0.025-0.25g 1*

R85 ,

b. 0-XS-52-80, Annulus, Elev. 680 0.025-0.25g 1* i

c. 0-XS-52-81, Annulus, Elev. 680 0.025-0.25g 1*

4. Trjaxial Response-Spectrum Recorders i

a. 0-XR-52-86, Annulus, Elev. 680 2-25.4 Hz, 0.003-32g 1* l

b. 0-XR-52-87, Reactor Containment 2-25.4 Hz, 0.003-32g 1 R85 Bldg., Elev. 734

c. 0-XR-52-88, Aux. CR,'Elev. 734 2-25.4 Hz, 0.003-32g 1 l

d. 0-XRd52-39, Diesel Building 2-25.4 Hz, 0.003-32g 1 Elev. 722 "With reactor. control room indication l

3/4 4.8 Amendment No. M 81 SEQUOYAH - UNIT 1 September 1, 1988

r.; .

TABLE 4.3-4 SEISMIC MONITORING INSTRUMENTATION SURVE -_

CHANNEL CHANNEL INSTRUMENTS AND SENSOR LOCATIONS _ CHECK CHANNEL FUNCTIONAL CALIBRATION TEST

1. Triaxial Time-History Accelerographs

a. 0-XT-52-75A, Containment, Elev. 734 M* R*** SA b 0-XT-52-758, Annulus, Elev. 680** M* R*** SA

c. 0-XR-52-77, Diesel Building, Elev. 722 M* gg3 R*** SA

2. Triaxial Peak Accelerographs

a. 0-XR , Containment, SIS Pipe NA Elev. 702 R NA

b. 0-XR-52-83, Containment, UNI Pipe, NA Elev. 706 R NA R85

c. 0-XR-52 Control Building MCR, Panel 0- -25, Elev. 739 NA R NA (

3. Blaxial Seismic Switches

a. 0-XS-52-79, Annulus, Elev. 680** '

1 M R SA

b. 0-XS-52-80, Annulus, Elev. 680**

M R SA

c. 0-XS-52-81, Annulus, Elev. 680** ;

M R SA

4. Triaxial Response-Spectrum Recorders -

a. 0-XR-52-86**, Annulus, Elev. 680 M I R SA

b. 0-XR-52-87, Reactor Containment NA Bldg., Elev. 734 R -NA

c. 0-XR-52-88, Aux. CR, Elev. 734 R85 j NA R NA

d. 0-XR-52-89, Diesel Building, NA Elev. 722 R' NA

Except seismic trigger \ i

- - - - With reactor Includes control seismic room indications.

trigger i I

SEQUOYAH - UNIT 1 3/4 '3-46 Amendment No. 77 81 September 1, 1988 !

y, TABLE 3.3-10 (Continued) o c: ACCIDENT MONITORING INSTRUMENTATION S

E MINIMUM

TOTAL NO. CHANNELS ACTION-l g INSTRUMENT OF CHANNELS REQUIRED 2 1 R163~

[ 12. Reactor Coolant System Subcooling Margin 2 Monitor (Instrument Loops94-101,-102)

13. Containment Water Level (Wide Range) 2 2 1 R153 (Instrument Loops63-178,-179)

14. Incore Thermocouples 65 l a. Core Quadrant-(1) 2(1/ Train) 1 2(1/ Train) 1

o. Core Quadrant (2) y c. Core Quadrant (3) 2(1/ Train) 1 2(1/ Train) 1

d. Core Quadrant (4)

R163

15. Reactor Vessel Level Instrumentation 6 2 1

a. Dynamic Range I trument Loops68-367, 370)

Lowet 2 1

b. -Uppee Range (Instrument Loops68-368, 371) urect 2 1

' >a c. 4 ewer Range Q

a (Instrument Loops68-369,372)

-M 16. Containment Area Radiation Monitors 4

$5 a. Upper Compartment. 2 1 R153 "P (Instrument Loops90-271,-272) w 4

b. Lower Compartment 2 1 M

(Instrument Loops90-273,-274)

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REACTOR COOLANT SYSTEM 3/4.4.11 REACTOR COOLANT SYSTEM HEAD VENTS LIMITING CONDITION FOR OPERATION j R137 3.4.11 At least one Reactor Coolant System Head Vent (RCSHV) path shall be OPERABLE.*

APPLICABILITY: MODES 1, 2, and 3. R120 ACTION:

i

a. With no RCSHV path OPERABLE *, restore at least one path to OPERABLE status within 30 days or be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and HOT R137 4 SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ,

b. The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS _

4.4.11 Each RCSHV path shall be demonstrated OPERABLE at least once per 18 l R137 months by:

a.h Verifying that the upstream manual isolation valves are locked in the V open position, lR137

b. Operating each remotely controlled valve through at least one cycle. 1120 from the control room, and

c. Verifying flow through each RCSHV path. R137 R120

Inoperable paths must be maintained closed with power removed from the valve R137 actuators. If any RCSHV path is declared inoperable while in an applicable MODE, power shall be removed from the valve actuators within one hour.

. I m9nt po v ri y ha/t e n al is at o /v v ae ockId n pos'tio i iv4d t e Cy e4 ef li g u . hi w iv r R127-n n o -

m bdis e fi st Mo e o a o w g ss a e ve ai r a 1 v ti n e e o me t v if map al s a o, va/pri i v e pe . esfw11 /

f SEQUOYAH - UNIT 1 3/4 4-28 Amendment No. 116, 123, 133 March 22, 1990

REACTOR COOLANT SYSTEM 3/4.4.12 LOW TEMPERATURE OVER PRESSURE PROTECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.12 At least one of the following Overpressure Protection Systems shall be OPERABLE:

a. Two power operated relief valves (PORVs) with a nominal lift setting less than or equal to that shown in Figure 3.4-4, or

b. The Reactor Coolant System (RCS) depressurized with an RCS vent of greater than or equal to 3 square inches.

APPLICABILITY: MODE 4, MODE 5 and MODE 6 with the reactor vessel head on.

ACTION:

a. With one PORV inoperable, in MODE 4 either:

R16

1. Restore the inoperable PORV to operable status within 7 days, or

2. Depressurize and vent the RCS through at least a 3 square inch vent within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , or

3. Ensure pressurizer level is maintained less than or equal to 30 percent.

b. With one PORV inoperable in MODES 5 or 6, either (1) restore the PORV to operable status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , or (2) complete depressurization and venting of the RCS through at least a 3 square inch vent within a total of 32 hours3.703704e-4 days 0.00889 hours 5.291005e-5 weeks 1.2176e-5 months .

c. With both PORVs inoperable, depressuriz and ent the RCS through at least a 3 square inch vent wichin 8 ho s7

d. With the RCS vented per ACTIONS a,b, or c, verify the vent pathway at least once per 31 days when the pathway is provided by a valve (s) that is locked, sealed, or otherwise secured in the open position; )

otherwise, verify the vent path every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

e. When 9CS temperature is less than 350 F, both safety injection pumps j and one centrifugal charging pump shall be made incapable of automatic injecti o the RCS, Should any of these pumps be found actually capable o auto tic injection, return the pump (s) to incapable statu withf12hoursordepressurizeandventRCSthrough at least a 3 squ vent within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . 1

f. In the event either the PORVs or the RCS vent ('s) are used to mitigate an RCS pressure transient, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 30 days. The report shall describe the circumstances initiating the transient, the effect of the PORVs or RCS vent (s) on the transient, and any corrective action necessary to prevent recurrence.

g. The provisions of Specification 3.0.4 are not applicable.

SEQUOYAH - UNIT 1 3/4 4-29 Amendment No.157 March 30, 1992

'4' 4 i

. ^

~

i CONTAINMENT SYSTEMS !

1 HYDR 0 GEN MITIGATION SYSTEM LIMITING CONDITION FOR OPERATION l I

, 3.6.4.3 The primary containment hydrogen mitigation system shall be operable. -

APPLICABILITY: MODES 1 and 2.

ACTION:

With one train of hydrogen mitigation system inoperable, restore the-inoperable-train to OPERABLE status within 7 days or increase the surveillance interval '

of S.R. 4.6.4.3 from 92 days to 7. days on the operable train until the 6 inoperable train is returned to OPERABLE status.

ll -

SURVEILLANCE REQUIREMENTS 4.6.4.3 The hydrogen mitigation system shall be demonstrated OPERABLE:

a. At least once per 92 days by energizing the ' supply breakers and -

verifying that at least 66 of 68 igniters are energized.* '

b. At least once per .18 months by verifying the temperature of each '

igniter is a minimum of 1700 F. R37 p

1 l

" Inoperable igniters must.not be on corresponding redundant circuits.which provide coverage for.the same region.

i y

i March 29, 1984-SEQUOYAH - UNIT l'

- 3/4 6-25a Amendment No.33 1

n

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PLANT SYSTEMS

~3/4.7.9 SNUBBERS

_' LIMITING CONDITION FOR_ OPERATION 3.7.9. All safety-related snubbers shall be OPERABLE. lR43 APPLICABILITY: MODES 1, 2, 3 and 4. (MODES 5 and 6 for snubbers located on systems or partial systems required OPERABLE in those MODES.)

ACTION:

With one or more snubbers inoperable, within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months replace or restore the

. inoperable snubber (s) to OPERABLE status and~ perform an engineering evaluation.

^

on the attached component or declare the attached system inoperable and follow the appropriate ACTION statement for that system.

SURVEILLANCE REQUIREMENTS 4.7.9. Each safety-related snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements R43 of Specification 4.0.5.

a. Inspection Groups The snubbers may be categorized into two major gro'ups ba ed onj/ ether the snubbers are accessible or inaccessible during reacto )e ion.

These major groups may be further subdivided-into subgroups aased.on design, environment, or other. features which may be expected to affect the OPERABILITY of the snubbers within the subgroup. Each_ subgroup R15 may be tested independently in accordance with 4.7 9.d through 4.7.9.h.

b. Visual Inspection Schedule and Lot Size All of-the safety-related snubbers shall be included in one population or they shall be categorized as accessible or inaccessible for visual inspection. If used, the accessible or inaccessible categories shall be 313 considered separately for visual inspections.

When recombining categories into one population, the shorter interval of the categories shall be used.

The visual inspection interval?for the population or each category shall be determined based upon the criteria provided in Table 4.7.9-1. and the t first inspection interval determined using this criteria shall be based upon the previous. inspection interval as established by the requirements in effect before the' amendment which incorporated this change was issued by the NRC. ~

[e 3/4 7-21 Amendment No. 39,153 SEQUOYAH - UNIT 1 SEP 101991

,m . m . - . . . _ . . . . _ _ . . . _

'Q.

1. e s.

Table 4.7.9'-1 (continued)

. SNUBBER VISUAL INSPECTION INTERVAL or .

Note 4: If the numberAunacce able snubbers is equal to or less than the-number olumn ut greater than the.. number in Column A, the next inspection i terval shall be the same.as the previous interval.

Note 5: If the number of' unacceptable snubbers is equal to or greater.than. a13; the number in Column.C, the next inspection interval shall be two-thirds of the previous interval. However, if the number of unaccep- j table snubbers is less than the number in Column C but greater than -

.' the number in Column B, the next interval shall be' reduced propor-tionally by interpolation,;that is, the previous interval shall be reduced by a. factor that is one third ~of the ratio'of the' difference between the number'of unacceptable snubbers found during the previous.

interval and the number in Column B:to the difference in the numbers in Column B and C.

Note 6: -The provisions of Specification 4.0.2 are applicable for all.

inspection intervals up.to and' including 48 months.

n

)

1 1

i September 10,.1991 ,

3/4 7-21b- Amendment No.153 SEQUOYAH - UNIT.1 s

v s l* _

po '

,..ey ELECTRICAL POWER SYSTEMS

~

-SURVEILLANCE REQUIREMENTS (Continued)

f. L At least once per 10 year by:

1. Draining each fuel oil storage tank, removing the accumulated ,

sediment and cleaning the tank using a sodium hypoclorite a solution, and' 2.- Performing a pressure' test of those portions of the' diesel fuel oil system design to Section III, subsection ND of the. ,

ASME Code at a test pressure equal to 110 percent of the system design pressure. ,

4.8.1.1.3 The 125-volt D.C. distribution panel,125-volt D.C. battery bank and associated charger for each diesel generator shall be demonstrated OPERABLE:

a. At least once per 7 days by verifying:

1. That the parameters in Table 4.8-la meet the Category A limits. 1

2. That the total battery terminal voltage is greater _than or equal to 124-volts on float charge.

b. At least once per 92 days by:

1. Verifying that'the parameters in Table 4.8-la meet the Category B limits,

2. ; Verifying there is no visible. corrosion at either terminals or connectors,.or the cell to terminal connection resistance of' these items is less than 150 x 10 6 ohms, and 3.- Verifying that the average electrolyte temperature of 6 connected ,

cells is above 608F. H

c. At least'once per 18 months by verifying.that:

1. The cells, cell plates and battery racks show no visual l indication of. physical damage or abnormal, deterioration. .

l

2. The battery to battery and terminal connections are clean, I tight and coated with anti-corrosion material. l

3. The resistance of each cell to terminal connection is'less 0 than or equal to 150 x 10 8 ohms.

RS6 -

4.8'.1.1.4 Reports _ - All diesel generator failures, valid or non-valid, shall.

~

be reported to the Commission pursuant to Specification 6.9.2.2.

T M M gdh [e M M fp[ de M t,d udeyfl/c4D R141 3/4 8-6 Amendment No.-52,137 SEQUOYAH - UNIT 1 April 27, 1990

i: )

c..

ELECTRICAL POWER SYSTEMS-SURVEILLANCE REQUIREMENTS 4.8.2.3.1 Each D.C. bus train shall be determined OPERABLE and energized with tie breakers open between redundant busses at least once per 7 days by verifying correct breaker alignment, indicated power availability from the charger and battery, and voltage on the bus of greater than or equal to 125 volts.

4.8.2.3.2* Each 125-volt battery bank and charger shall be demonstrated OPERABLE: lR41

a. At least once per 7 days by:

1. Verifying that the parameters in Table 4.8-2 meet the Category A limits, and

2. Verifying total battery terminal voltage is greater than or equal to 129-volts on float charge,

b. At least once per 92 days and within 7 days after a battery discharge ,

(battery terminal voltage below 110-volts), or battery overcharge !

(battery terminal voltage above 150-volts), by:

1. Verifying that the parameters in Table 4.8-2 meet the Category B-limits,

2. Verifying there is no visible corrosion at either terminals or connectors, or the connection resistance of these items is less than 150 x 10 8 ohms, and

3. Verifyin that the average electrolyte temperature of 6 connected cells is above 60'F.

c. At least once per 18 months by verifying that:

1. The cells, cell plates and battery racks show no visual indication of physical damage or abnormal deterioration,

2. The cell-to-cell and terminal connections are clean, tight and-coated with anti-corrosion material,

3. The resistance of each cell-to-terminal connection is less than or equal to 150 x 10 8 ohms, and

4. The battery _ charger will supply at'least 150 amperes at 125 volts for at least 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

This surveillance includes Battery Bank V, but not charger V. R41 January 24, 1985 SEQUOYAH - UNIT 1- 3/4 8-12 Amendment No. 37 g

w *': ,

g. l.* i'

' ELECTRICAL POWER SYSTEMS-SURVEILLANCE REQUIREMENTS (Continued)

L d. At least once per 18 months by verifying that the battery capacity is adequate to supply and maintain in OPERABLE status all of the actual or simulated emergency loads for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months when the battery is subjected to a battery service test.

/ e. At least once p 60 months by verifying that the battery capacity is at least 8 the manufacturer's rating when subjected to a l'R33 performance discharge test. Once per 60 month interval,-this performance discharge test may be performed in lieu of the battery service test.

f. Annual performance discharge tests of battery capacity shall, be .

given to any battery that shows signs of degradation or has reached 85% of the service life expected for the application. Degradation is indicated.when the battery capacity drops more than 10% of rated capacity from its average on previous performance tests, or is below 90% of the manufacturer's rating.

i t h ca ec i ti ' p1 e e d i t a u ip)(e f 1 i t nd e el g u g or fo o n c p1 e R33 m f at nw c ve i ea i r. /

a I

SEQUOYAH - UNIT 1 3/4 8-13 Amendment Nol 29 May 5, 1983

?$g ,

a

, g.

e f .

REFUELING OPERATIONS LOW WATER LEVEL L

~

' LIMITING CONDITION FOR OPERATION 3.9.8.2 Two independent-Residual Heat Removal (RHR) loops-shall be OPERABLE.*

APPLICABILITY: MODE 6 when the water level- e the top of.the. reactor R16 pressure vessel flange is less than 23 fee ACTION:

a. With less than the required RHR loops OPERABLE, immediately initiate corrective action.to return the required RHR loops to OPERABLE status as soon as possible.

b. The provisions of-Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.8.2 The required Residual Heat Removal loops shall be determined OPERABLE per Specification 4.0.5.

-^The normal or emergency Dower source may be: inoperable for each RHR loop.

D9?@7M77777 MUM 7/7M7" - R14 MAR- 251982.

A e N 2 SEQUOYAH . UNIT 1 3/4 9-8a

4

.

INDEX

(

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS ,

i l

SECTION PAGE ;

3/4.6.3 CONTAINMENT ISOLATION VALVES.............................. 3/4 6-17 3/4.6.4 COM8USTISLE GAS CONTROL Hydrogen Monitors......................................... 3/4 6-24 Electric sgg ................ 3/4 6-25 -

HydrogenkrIGXT0;ntre , jo@cri;;; Oi;trikt d I;;niti:n System. . . . .

. . . . 3/4 6-26

^

3/4.6.5 ' ICE CONDENSER Ice Bed................................................... 3/4 6-27 Ice Bed Temperature Monitoring System..................... 3/4 6-29 Ice Condenser 00ers....................................... 3/4 6-30 Inlet Door Position Monitoring System..................... 3/4 6-32 Divider Barrier Personnel Access Doors and Equipment Hatches....................................... 3/4 6-33 Q Containment Air Return Fans............................... 3/4 6-34 Floor 0 rains.............................................. 3/4 6-35 Refueling Canal 0 rains....................................

3/4 6-36 Di vi de r Barri e r Sea' . . . . . . . . . . . . . . . : . . . . . . . . . . . . . . . . . . . . . . 3/4 6-37 3/4.6.6 VACUUM RELIEF VALVE.i...................................... 3/4 6-39 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE Safety Va1ves............................................. 3/4 7-1 Auxi l i ary Feedwate r. Sys tem. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4,7-5 Condensate. Storage Tank................'................... 3/4.7-7 Activity...............[.................................. 3/4 7-8=

Main Steam Line Isolation Va1ves.......................... 3/4 7 3/4. 7.' 2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION........... 3/4 7-11 3/4.7.3 COMPONENT COOLING WATER SYSTEM............................ 3/4 7-12 SEQUOYAH - UNIT 2 VIII

1.;

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.8.3 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES Containment Penetration Conductor Overcurrent Protective 0evices................................................. 4 -

t Hotor Operated Valves Thermal Overload Protection. . . . . . . . 3/4 8-)ff0 21 R53 L Isolation Devices............'....................... ..... 3/4 8-)6 l 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION....................................... 3/4 9-1 3/4.9.2 INSTRUMENTATION........................................... 3/4 9-3 3/4.9.3 DECAY TIME................................................ 3/4 9-4 3/4.9.4- CONTAINMENT BUILDING PENETRATIONS......................... 3/4 9-5 3/4.9.5 COMMUNICATIONS............................................ 3/4 9-6 3/4.9.6 MANIPULATOR CRANE......................................... -3/4 9-7 3/4.9.7- CRANE TRAVEL - SPENT FUEL PIT AREA. . . . . . . . . . . . . . . . . . . . . . . . 3/4 9-8 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION All Water Levels.......................................... 3/4 9-9 Low Water Level........................................... 3/4 9-10 3/4.9.9 CONTAINMENT VENTILATION ISOLATION SYSTEM.................. 3/4 9-11 3/4.9.10 WATER LEVEL - REACTOR VESSEL. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 9-12 3/4.9.11 WATER LEVEL SPENT FUEL PIT.............................. 3/4 9-13 3/4 9.12 AUXILIARY BUILDING GAS TREATHENT SYSTEM................... 3/4 9 .

3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTOOWN MARGIN........................................... 3/4 10-1 I 3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS..... 3/4 10-2 3/4.10.3 PHYSICS-TESTS............................................. 3/4 10-3 SEQUOYAH - UNIT 2 'X Amendment No.53 October 22, 1987

TABLE 2.2-1 N REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS O

TRIP SETPOINT ALLOWABLE VALUES g FUNCTIONAL UNIT

' 1. Manual Reactor Trip Not Applicable Not Applicable E Low Setpoint - s 25% of RATED Low Setpoint - 5 27.4% of RATED l R132 Z 2. Power Range, Neutron Flux THERMAL POWER THERMAL POWER m

High Setpoint - s 109% of RATED High Setpoint - s 111.4% of l R132 THERMAL POWER RATED THERMAL POWER s 6.3% of RATED THERMAL POWER R36

3. Power Range, Neutron Flux, s 5% of RATED THERMAL POWER with High Positive Rate a time constant 1 2 seconds with a time constant 2 2 seconds

4. Power Range, Neutron Flux, s 5% of RATED THERMAL POWER with s 6.3% of RATED THERMAL POWER R36 High Negative Rate a time constant 2 2 seconds with a time constant 2 2 seconds m 5. Intermediate Range, Neutron s 25% of RATED THERMAL POWER s 45.20% of RATED THERMAL POWER m Flux

6. Source Range, Neutron Flux s 105 counts per second s 1.45 x 10 5counts per second

7. Overtemperature AT See Note 1 See Note 3

8. Overpower AT See Note 2 See Note 4 R132 1 1970 nsi9 2 1964.8 psig

9. Pressurizer Pressure--Low

,p W- c

10. Pressurizer Pressure--High < 2385 psig s 2390.2 psig y{ & .~ -

11. Pressurizer Water Level--High s 92% of instrument span s 92.7% of instrument span

%a@ e 190% of design flow per loop

189.4% of design flow per loop

y

12. Loss of Flow M

Design flow is 91,400 gpm per loop.

.U

- n v.

. ;y TABLE-2.2-1 (Continued)

S REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS ix r NOTATION (Continued)

~

E Z

" NOTE 3: The channel's maximum trip setpoint shall not exceed its computed trip point'by more than 1.9 percent AT span.

R132' NOTE 4: The channel's maximum trip setpoint shall_not exceed its computed trip setpoint by more than 1.7 percent AT span.

7 M

NOTE 5: Trip Time Delay - Steam Generator Water Level--Low-Low T,='{(-0.00583)(P)2 + (0.735)(P)2 - (33.560)(P) + 649.5}{0.99 .sec s.

T,= ((-0.00532)(P)3 + (0.678)(P)2 - (31.340)(P) + 589.5){0.99 sec s.

Where: ,

P = RCS Loop AT Equivalent to Power (% RTP), P < 50% RTP Ts= Time dela for Steam Generator Water Level--Low-Low Reactor Trip, one Steam Generator y affecte . (sets.')

=oa ca g- T,= Time delay for Steam Generator Water Level--Low-Low Reactor Trip, two or more Steam-

-I g Generators affected. (secs.)

c,5 e 5.s [.

3-

'] E

REACTIVITY CONTROL SYSTEMS R0D DROP TIME LIMITING CONDITION FOR OPERATION 3.1.3.4 The individual full length g (shutdown and control) rod drop time from _!

the fully withdrawn position shall be less than or equal to 2.7 seconds from R1$

beginning of decay of stationary gripper coil voltage to dashpot entry with: ;

a. T,yg greater than or equal to 541*F, and

b. All reactor coolant pumps operating.

APPLICABILITY: Modes 1 and 2.

ACTION:

a. With the drop time of any full length rod determined to exceed the above limit, restore the rod drop time to within the above limit prior to proceeding to MODE 1 or 2.

b. With the rod drop times within limits but determined with 3 reactor coolant pumps operating, operation may proceed provided THERMAL POWER is restricted to less than or equal to 71% of RATED THERMAL POWER.

SURVEILLANCE REQUIREMENTS 4.1.3.4 .The rod drop time of full length rods shall be demonstrated through measurement prior to reactor criticality:

a. For all rods following each removal of the reactor vessel head,

b. For specifically affected individual rods following any maintenance ,

on or modification to the control rod drive system which could affect the drop time of those specific rods, and R20

c. At least once per 18 months n

y , e e ly r

Fully withdrawn shall be the condition where shutdown and control banks are R98-at a position within the interval of >222 and 1231 steps withdrawn, inclusive.

i l

SEQUDYAH - UNIT 2 3/4 1-19 Amendment No. 20, 98, 130 .

l October 2, 1990 t

g l

l 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE (AFD)

R21 LIMITING CONDITION FOR OPERATION 3.2.1 The indicated AXIAL FLUX DIFFERENCE (AFD) shall be maintained within the limits specified in the COLR. R14f-APPLICABILITY: MODE .1 above 50% of RATED THERMAL POWER *. R21 ACTION:

a. With the indicated AXIAL FLUX DIFFERENCE outside of the limits R140 specified in the COLR;

1. Either restore the indicated AFD to within the limits within R14f 15 minutes, or

2. Reduce THERMAL POWER te less than 50% of RATED THERMAL POWER R21 within 30 minutes and reduce the Power Range Neutron Flux-High Trip setpoints to less than or equal to 55 percent of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

b. THERMAL POWER shall not be increased above 50% of RATED THERMAL POWER unless the indicated AFD is within the limits specified R14f in the COLR.

t i Sct Secci At_ ' Test Exteerto N J. /o. 2

& s i

3/4 2-1 Amendment No. 21,146 SEQUOYAH - UNIT 2 March 30, 1992

TABLE 3.3-1 (Continued)

TABLE NOTATION With_the reactor trip system breakers in the closed position, the control rod drive system capable of rod withdrawal, and fuel in the ctor vessel, e ( s ia ed i e o ec v f ct on d i d r ou o s v e e cto 1 t oo al b p c i te i e e d' i .

The provisions of Specification 3.0.4 are not applicable.

1. S ource Range outputs may be disabled above the P-6 (Block of Source Range Reactor Trip) setpoint. R129 ACTION STATEMENTS ACTION 1 - With the number of OPERABLE channels one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and/or open the reactor trip breakers.

ACTION 2 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/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 . R39

b. 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 R132 Specification 4.3.1.1.1.

c. The QUADRANT POWER TILT RATIO is monitored in accordance with Technical Specification 3.2.4.

l R122 j

i i

l l

SEQUOYAH - UNIT 2 3/4 3-5 Amendment No. 39, 122, 129, 132 00T 3 10

, - r..

.:(

L: ,1 q

TABLE 3.3-l'(Continued)-

ACTION 10 - 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-(T3 and Tg ) threshold

]{

power level for zero seconds time delay is adjusted to 0%

RTP.

R132 4

ACTION'11 - With the number of OPERABLE channels. one less than the Total Number of Channels, STARTUP and/or POWER OPERATION l 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 1 (EAM) channels trip setpoint is adjusted to the same value as Steam Generator Water Level - Low-Low (Adverse).-

ACTION 12 - With the number of OPERABLE channels'one less than required by.

the Minimum Channels OPERABLE requirement, be in at least HOT-STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be. bypassed-for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for ~ surveillance testing per Specification 4.3.1.1.1 provided the other channel is OPERABLE.. 1 I I -

'i t t n er of P Bdc nn s e ss ha t .T ta N e of ha e d w th e E L le el bo e e

-7 ena e ea or tr s) et in pla .t e i op ab e an el

( in he ri e co it n th ,6 our , o era io ma c ti u 9/ y til er o n of he nex re ire CHpHE F CT N T ST p ACTION 14 - With the number of channels OPERABLE one less than required by.

the Minimum Channels OPERABLE requirement, be in at:1 east HOT ' '

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

~

ACTION 15 - With one of the diverse . trip features (undervoltage or

. shunt trip attachment) inoperable, restore it to operable status within 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months s-or declare the breaker ' inoperable and apply ACTION 12. The breaker shall not.be bypassed while one of the diverse trip features isfinoperable .

except for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for performing maintenance to' R46~

restore the breaker to OPERABLE' status.~

ACTION 16 - With the number of OPERABLE! channels one-less than'the ..

minimum channels operable-requirement, restore the inoperable' channel to operable status within.48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .or open the reactor trip breakers within.the next hour. '

1 ii a

l October 31[1990 SEQUOYAH - UNIT 2 3/4 3-8 Amendment No'.- -46;!132, 39 c- -

- w. ~

._ ____.__._m_m__.__- ___.--__ - _ - .

ga .

a

. .n fs ; :

' E.t m TABLE'3.3-3 (Continued) -[

$m . ENGINEERED' SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION' '?

5 x MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE g- 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 R132' line

2. CONTAINMENT SPRAY

a. Manual 2 1** 2 1,2 3,4 20- 5-

b. Automatic Actuation 2 1 2 1,2,3,4 15 Logic w c. Containment Pressure-- 4 2 3 1,2,3 18 1 High-High

~

3 m

3. CONTAINMENT ISOLATION.

a. Phase "A" -

Isolation o- 1) . Manual' 2 1 2 1,2,3,4 20 R

g. y

2) From Safety Injection 2 1 2 1,2,3,4- 15 g Automatic' Actuation w g logic

.~ g .

n C3 z

&?

e.o .*

p_s ; ,

-E3 * ~

~**Two switches must be. operated simultaneously for actuation.

I3 $.

m. ,

=

. _ . .- .- . . _ - =. - - - . - . - . . . ._

TABLE 3.3-3 (Continued)

TABLE NOTATION

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

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

-11 when Safety Iniection on Steam Line Pressure-Low is not blocked. R132 i

P p e r p 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 l R132 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 lR132 ,

is OPERABLE.

ACTION 16 - Deleted.

R132 ,

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- R132 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-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 lR158 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 . .

4 SEQUOYAH - UNIT 2 3/4 3-22 Amendment No. 55/,/132, 158 June 25, 1993-

E TABLE 3.37 .

SEISMIC MONITORING INSTRUMENTATION MINIMUM MEASUREMENT INSTRUMENTS INSTRUMENTS AND SENSOR LOCATIONS RANGE OPERABLE

1. Triaxial Time-History Accelerographs

a. 0-XT-52-75A, Containment, Elev. 734 0-1.0g i U2

b. 0-XT-52-758, Annulus, Elev. 680 0-1.0g la

c. 0-XR-52-77, Diesel Building, Elev. 722 0-1.0g i

2. Triaxial Peak Accelerographs 84

a. 0-XR-52-Af', Containment, SIS Pipe, Elev. 702 0-5.0g l'

b. 0-XR-52-83, Containment, UHI Pipe, R72 Elev. 706 0-5.0g 1 0 XR 52-)4', Control Building, MCR, Q anel P 0-M-25 Elev. 739 0-5.0g ,

1

3. Biaxial Seismic Switches l a.b-XS-52-79, Annulus,Elev.680 0.025-0.25g 1* I

b. 0-XS-52-80, Annulus, Elev. 680 0.025-0.25g la '

c. 0-XS-52-81, Annulus, Elev. 680 0.025 . 25g la

4. Triaxial Response-Spectrum Recorders

a. 0-XR-52-86, Annulus, Elev. 680 2-25.4 Hz, 0.003-32g 1*

b. 0-XR-52-87, Reactor Containment 2-25.4 Hz, 0.003-32g 1 R72 Bldg. Elev. 734

c. 0 XR-52-88, Aux. CR, Elev. 734 2-25.4 Hx, 0.003-32g 1 !

l

d. 0-XR-52-89, Diesel Generator, 2-25.4'Hz, 0.003-32g 1 l Elev. 722 1

"With reactor control room indication ll SEQUOYAH - UNIT 2 3/4 3-46 Amendment No. 72 September 1, 1988

U i, TABLE 4.3-4 SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ;

CHANNEL I CHANNEL CHANNEL FUNCTIONAL IN!TRUMENTS AND SENSOR LOCATIONS CHECK CALIBRATION TEiT

1. Triaxial Time-History Acceleregraphs

a. 0-XT-52-75A, Containment, Elev. 734 M* R*** SA R72

b. 0-XT-52-758, Annulus, Elev. 680** M* R*** -SA

c. 0-XR-52-77, Diesel Building, Elev. 722 M* R*** SA

2. Triaxial Peak Accelerographs

a. 0-XR , Containment, SIS Pipe. NA R NA Elev. 7 NA R7.

b. 0-XR-52-83, Containment, UHI Pipe, NA R Elev. 70 ,

Control Building, MCR, NA R NA

c. 0-XR-52 '

Panel 0 25, Elev. 739

3. Biaxial Seismic Switches SA

a. 0-XS-52-79, Annulus, Elev. 680** H R SA g72

b. 0-XS-52-80, Annulus, Elev. 680** M R SA

c. 0-XS-52-81, Annulus Elev. 680** M R 4 Traixial Response-Spectrum Recorders SA

a. 0-XR-52-86**, Annulus,Elev. 680 M R

b. 0-XR-52-87, Reactor Containment NA R /A R72.

Bldg, Elev. 734 NA

c. 0-XR-52-88, Aux. CR, Elev. 734 NA R NA

d. 0-XR-52-89, 0!esel Building . NA R Elev. 722 1

Except seismic trigger 1 I

- With reactor control room indications

- - Includes seismic trigger 3/4 3-47 Amendment No. 72 ,

SEQUOYAH - UNIT 2 September 1, 1988

4:J,

~

TABLE 3.3-10 (Continued) 1 m ,

ACCIDENT MONITORING INSTRUMENTATION Y

2 MINIMUM

TOTAL NO. CHANNELS g 0F CHANNELS REQUIRED' ACTION INSTRUMENT -

12. Reactor _ Coolant System Subcooling Margin 2 2 1 lR14 Monitor-(Instrument Loops94-101,-102)

13. Containment Water' Level (Wide Range) 2 2 1 R135 (Instrument Loops63-178,-179)

14. Incore Thermocouples 65

a. 2(1/ Train) 1 Core Quadrant (1)

b. Core Quadrant (2) 2(1/ Train) 1

c. Core' Quadrant-(3) 2(1/ Train) 1 g d.- Core Quadrant (4) 2(1/ Train) 1 I;> 15. Reactor Vr.ssel' Level Instrumentation 6 w

R14 E a. Dynamic Range 2 1 Instrument Loops68-367, 370)

. - Lo m 4 b. W Range . .

2 1

'(Instrument Loops .68-368, 371)

i Urreg 2 1

c. 4. ewer Range g(

(Instrument Loops68-369,~372)-

g . ._ ,

B

% 16. Containment' Area Radiation Monitors u

a. Upper Compartmenti 2 1 4

5. E . . .

R1'35

- (Instrument Loops90-271,-272)

._w O b. Lower Compartment 2 1 4 (Instrument Loops90-273,-274);

]'

w

+ 4 - y 4 ----&

'~R_EACTOR COOLANT SYSTEM 3/4.4.11 REACTOR COOLANT SYSTEM HEAD VENTS LIMITING CONDITION FOR OPERATION 3.4.11 At least one Reactor Coolant System Head Vent (RCSHV) path shall be R120 OPERABLE.n

. APPLICABILITY: MODES 1, 2, and 3.

ACTION:

a. With no RCSHV path OPERABLE *, restore at least one path to OPERABLE status within 30 days or be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . R120

b. The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.4.11 Each RCSHV path shall be demonstrated OPERABLE at least once per 18 months by: R120l a./ Verifying that the upstream manual isolation valves are locked in the open position, R120

b. Operating each remotely controlled valve through at least one cycle from the control room, and

c. Verifying flow through each RCSHV path.

Inoperable paths must be maintained closed with power removed'from the valve actuators. If any RCSHV path is declared inoperable while in an applicable R120 MODE, power shall be removed.from the valve actuators within one hour hpfenh55t y'v f t tthe p r m a a i d r[

An e n s i i w v t te f uta .

~

a r s te a on ti e as s. -

e rt o ta e o v/ri th m t) a e a i.

SEQUOYAH - UNIT 2 3/4 4-33 Amendment No. 106, 112, 120, 138 December 17, 1990 pCp yy "CD R138

4 REACTOR COOLANT SYSTEM 3/4.4.12 LOW TEMPERATURE OVERPRESSURE PROTECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.12 At least one of the following Overpressure Protection Systems shall be OPERABLE:

a. Two power operated relief valves (PORVs) with a nominal lif t setting less than or equal to that shown in Figure 3.4-4, or

b. The Reactor Coolant System (RCS) depressurized with an RCS vent of greater than or equal to 3 square inches.

APPLICABILITY: MODE 4, MODE S and MODE 6 with the reactor vessel head on.

ACTION:

a. With one PORV inoperable, in MODE 4 either: l R14l

1. Restore the inoperable PORV to operable status within 7 days, or

2. Depressurize and vent the RCS through at least a 3 square inch i vent within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , or

3. Ensure pressurizer level is maintained less than or equal to 30 percent.

! b. With one PORV inoperable in MODES S or 6, either (1) restore the l PORV to operable status within 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .s, or (2) complete I depressurization and venting of the RCS through at least a 3 square l inch vent within a total of 32 hours3.703704e-4 days 0.00889 hours 5.291005e-5 weeks 1.2176e-5 months .

c. With both PORVs inoperable, depress rize and vent the RCS through at l 1 east a 3 square inch vent within hours / (

d. With the RCS vented per ACTIONS a, , or c, verify the vent pathway l at least once per 31 days when the pathway is provided by a valve (s) !

that is locked, sealed, or otherwise secured in the open position; i otherwise, verify the vent path every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . j

e. When RCS temperature is less than 350*F, both safety injection pumps l and one centrifugal charging pump shall be made incapable of automatic injecti nto h RCS. Should any of these pumps be found j actually capable of tomati injection, return the pump (s) to l incapable status wit 12 ho s or depressurize and vent RCS through at least a 3 squar ic ent within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , j i

f. In the event either the PORVs or the RCS vent (s) are used to mitigate an RCS pressure transient, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 30 days. The report shall describe the circumstances ,

initiating the transient, the effect of the PORVs or RCS vent (s) on 4 the transient, and any corrective action necessary to prevent recurrence.

The provisions of Specification 3.0.4 are not applicable. l g.

3/4 4-34 Amendment No.147 SEQUOYAH - UNIT 2 March 30, 1992 l

. i

(( . {c %

f y

EMERGENCY CORE COOLING SYSTEMS i

,3/4.5.2 ECCS' SUBSYSTEMS - T Greater Than or Equal to 350 F gyg LIMITING CONDITION FOR OPERATION

.5.2 Two independent emergency core cooling system (ECCS) subsystems shall ;

be OPERABLE with each subsystem comprised of:

a. One OPERABLE centrifugal charging pump,

b. One OPERABLE safety injection pump, l I

c. One OPERABLE residual heat removal heat exchanger,

d. One OPERABLE residual heat removal pump, and ,

e. An OPERABLE flow path capable of taking suction from the refueling water storage tank on a safety injection signal and automatically transferring suction to the containment sump during the recirculation chase of operation.

APPLICfBILITY: MODES 1, 2 and 3.

j I

ACTIflN_:

a. With one ECCS subsystem inoperable, restore the inoperable subsystem '

to OPERABLE states within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b. In the event the ECCS is actuated and injects water into the Reactor Cm, int System, a REPOR1ABLE EVENT shall be prepared and submitted. R28 -

to ue Commission pursuant to Specification 6.6.1. This report shall include a descriptior, of the circumstances of the actuation and the total accumulated actuation cycles to date. The current value of the usage factor for each affected safety injection nozzle shall'be provided in this Special Report whenever its value exceeds 0.70.

SURVEILLANCE REQUIREMENTS 4.5.2 Each ECCS subsystem shall_be demonstrated OPERABLE:

a. At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that the following valves are in the indicated positions with power to the valve eperators removed:

OT : i i gne e r di 1 ar[n u

~

o[ e t e er toc c e1 ,

o r. t C m r at e al f a i on 3 h r /

on'g sat id t ie in c oi s -]

b e n (a . h .t po r"

/

( % exp rpI 9 08 J, y 3 1984.- /

~

j l

.i SEQUOYAH - UNIT 2. 3/4 5-4 Amendment No. 28, 131- Ru OCT 291990 j

l e

CONTAlHMENT SN5TEMS HYDROGEN MITICATION SYSTE[

LIMITING CONDITION FOR OPERATION 3.6.4.3 The primary containment hydrogen mitigation system shall be operable.

APPLICABILITY: MODES 1 and 2 I

ACTION:

With one train of hydrogen mitigation system inoperable, restore the inoperable train to OPERABLE status within 7 days or increase the surveillance interval of S.R. 4.6.4.3 from 92 days to 7 days on the operable train until the inoperable train is retruned to OPERABLE status.

R2:

SURVEILLANCE REQUIREMENTS 4.6.4.3 The hydrogen mitigation system shall be demonstrated OPERABLE:

a. At least once per 92 days by energizing the supply breakers and verifying that at least 66 of 68 igniters are energized.*

b. At least once per 18 months by verifying the temperature of each igniter is a minimum of 1700 F.

Inopetoble igniters must not be on corresponding redundant circuits which provide coesrage for the same region.

SEQUOYAH - UNIT 2 3/4 6-26 Amendment No. 21 SEP 2 S 1983

4 l

[l:

4- ELECTRICAL POWER SYSTEMS

' SURVEILLANCE REQUIREMENTS (Continued)

f. At least once per 10 yearhby:

1. Draining each fuel oil storage tank, removing the accumulated

, sediment and cleaning the tank using a sodium hypoclorite solution, and

2. Performing a pressure test of those portions of the diesel >

fuel oil system designed to Section III, subsection ND of the ASME Code at a' test pressure equal to 110 percent of the system design pressure.

4.8.1.1.3 The 125-volt D.C. distribution panel, 125-volt D.C. battery bank and associated charger for each diesel generator shall be demonstrated OPERABLE:

a. At least once per 7 days by verifying:

1. That the parameters in Table 4.8-la meet the Category A limits.

2. That the total battery terminal voltage is greeter than or R8 equal to 124 volts on float charge.

b. At least once per 92 days by:

1. Verifying that the parameters in Table 4.8-la neet the Category B limits,

2. Verifying there is no visible corrosion at either terminals or connectors, or the cell to terminal connection resistance of these items is less than 150 x 10 6 ohms, and

3. Verifyin. hat the average electrolyte temperature of 6 connected cells is abov9 60 F.

c. At least once per 18 months by verifying that:

1. The cells, cell plates and battery racks show no visual indication of physical damage or abnormal deterioration.

2. The battery to battery and terminal connections are clean, tight'and coated with anti-corrosion material.

3. The resistance of each cell to terminal connection is less than or equal to 150 x 10 6 ohms.

r*~"7 l// / / / /

/*/dp h u e n e a f in ur ei SEQUOYAH - UNIT 2 3/4_8-6 Amendment No. 8 December 23, 1982

..j.

A

- ELECTRICAL POWER SYSTEMS SURVEILLANCE' REQUIREMENTS p 2. Verifying total battery terminal voltage is greater than or p equal to 129-volts on float charge. l L b. At least once per 92 days and within 7 days after a battery discharge j' (battery terminal voltage below 110-volts), or battery overcharge (battery terminal voltage above 150-volts), by:

l i

l. 1. Verifying that the parameters in Table 4.8-2 meet the Category B !

limits, J L i

2. Verifying there is no visible corrosion at either terminals or {

connectors, or the connection resistance of these items is less j than 150 x 10 8 ohms, and

3. Verifyin that the average electrolyte temperature of 6 connected cells is above 60 0F.

c. At least once per 18 months by verifying that:

1. The cells, cell plates, and battery racks show no visual indication of physical damage or abnormal deterioration,

2. The cell-to-cell and terminal connections are clean, tight, and coated with anti-corrosion material,

3. The resistance of each cell-to-terminal connection is less than

~

or equal to 150 x 10 8 ohms, and

4. The battery charger will supply at least 150 amperes at 125-volts for at least 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

d. At least once per 18 months by verifying that the battery capacity is adequate to supply and maintain in OPERABLE status all of the actual or simulated emergency loads for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months when the battery is subjected to a battery service test.

e. At least once - 60 months by verifying that the battery capacity is at least 8 f the manufacturer's rating when subjected to a R1@

performance discharge test. Once per 60 month interval, this <

performance discharge test'may be performed in lieu of the battery service test.

f. Annual performance discharge tests of battery capacity shall be given to any battery that shows signs of degradation or has reached 85% of the service life expected for the application. Degradation is indicated when the battery capacity drops more than 10% of rated capacity from its average on previous performance tests, or is below

, 90% of the manufacturer,'s rating.

e st i ta .

7 SEQUOYhH - UNIT 2 3/4 8-13 Amendment No.18 MlY R 10%

u.

' yyyn .

., 4 9.

- s y _.

9 REFUELING-OPERATIONS r

' LOW WATER LEVEL. r LIMITING CONDITION FOR OPERATION -

3.9.8.2 Two independent Residual Heat Removal (RHR) loops shall be OPERABL'E.*-

APPLICABILITY: . MODE 6 when the water level ve the top of the reactor pressure vessel flange is less than 23 feet "

ACTION:

a. With less than the required RHR loops OPERABLE, immediately initiate corrective action to return the required RHR loops to OPERABLE status as soon as possible.

b. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.8.2 -The required Residual Heat-Removal loops shall be determined'0PERABLE-per Specification 4.0.5.

l F

b

~

The normal or emergency power source may be ~ inoperable for each RHR loon. -,

.SEQUOYAH - UNIT 2 - 3/4 9-10 ,

2"i'r

, ._.,p.

(Aji > , '

p: ;;.. -

'[ '.

ENCLOSURE 2 i PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE SEQUOYAH NUCLEAR PLANT (SON) UNITS 1 AND 2 DOCKET NOS. 50-327 AND 50-328 (TVA-SON-TS-95-12)

DESCRIPTION AND JUSTIFICATION FOR EDITORIAL ERROR CORRECTIONS AND REMOVAL OF NONAPPLICABLE PROVISIONS f

e 1

2 4

i

y %3.,f.kg ' T

~-

c t:s I lf _

~ Descriotion of ' Chance 6 ;TVA proposes to modify the Sequoyah Nuclear Plant (SON) Units 1 and 2 technical.

. specifications (TSs) to incorporate corrections to the following TS text.

Unit 1 l ' *- Correct index page Vil'l by adding the Hydrogen Mitigation System heading to l Section 3/4.6.4 and reference to page 3/4 6-25a for the location.

s i e Correct index page X by changing the referenced location for the Motor Operated Valves Thermal Overload Protection and Isolation Devices to pages 3/4 8-17 and ,

3/4 8-20, respectively, o Correct page 2-11 by adding the time units of seconds to the T, and T.,, values.

e Correct page 3/4 2-1 by adding the referenced footnote, "*See Special Test Exception 3.10.2," at the bottom of the page.

e Correct page 3/4 3-45 by changing the instrument number in item 2.a to 0-XR-52-84 and the instrument number in item 2.c to 0-XR-52 82. ,

le Correct page 3/4 3-46 by changing the instrument' number in Item 2.a to

, :0-XR 52-84 and the instrument number in item 2.c to 0-XR-52-82.

e Correct page 3/4 3 56a by changing the titles of item 15.b to " Lower Range" and item 15.c to " Upper Range."

e Correct page 3/4 4-29 by removing the

from Action c and changing the word "with" m Action e to "within."

.e Correct page 3/4 6-25a by adding the title of ." CONTAINMENT SYSTEMS" to the

. top of the page.

e. Correct page 3/4 7 21 by changing the word "one" in Surveillance - t Requirement (SR) 4.7.9.a to "on." -

e Correct page 3/4 7-21b by adding the word "of" to note 4 between the words number and unacceptable, e Correct pages 3/4 8-6 and 8-12 by adding the degree symbol to 60 F of l

. SRs 4.8.1.1.3.b.3 and 4.8.2.3.2.b.3, respectively. l k

l j

i l

NW ,.hs wn: ,

,_}_'

.2-Unit 2

o Correct index page Vill by changing the title of " Hydrogen Control Interim

- Distribution Ignition System" to " Hydrogen Mitigation System" for TS

Section 3/4.6.4. ;

e Correct index page X by changing the referenced location for the Motor Operated - ;

Valves Thermal Overload Protection and Isolation Devices to pages 3/4 8-18 and >

3/4 8-21, respectively.

e Correct page 2-5 by changing the trip setpoint equality symbol for item 10 to be

".$,, 2385 psig."

e Correct page 212 by adding the time units of seconds to the T, and T,, values. .

e Correct page 3/4 2-1 by adding the referenced footnote, "*See Special Test Exception 3.10.2," at the bottom of the page, e Correct page 3/4 316 by changing the footnote symbol for the applicable modes -

of item 1.f from "##" to "#."

e Correct page 3/4 3-46 by changing the instrument number in l' tem 2.a to i 0-XR-52-84 and the instrument number in Item 2.c to 0-XR-52-82.

-.e Correct page 3/4 3-47 by changing the instrument number in item 2.a to 0-XR-52-84 and the instrument numter in item 2.c to 0-XR-52-82.

e Correct page 3/4 3-57a by changing the titles of item 15.b to " Lower Range" and

- Item 15.c to " Upper Range."

e Correct page 3/4 4-34 by removing the ? from Action c and changing the word - a "with" in Action e to "within."

e Correct page 3/4 6-26 by adding the title of " CONTAINMENT SYSTEMS" to th+ . l top of the page.' ]

e Correct pages 3/4 8-6 and 8-13 by adding the degree symbol to 60 F of d SRs 4.8.1.1.3.b.3 and 4.8.2.3.2.b.3, respectively.

i j

i

~

4 4 k w -

s

,- .m y ,, -

f' x }

j 3 l

-1 The following provisions will be removed from the TSs.

Unit 1 i

. i e Remove item 2.C.25 for " Surveillance Interval Extension," on Operating License page 12.

Remove the # footnote from Action 3.1.3.2.a.1 for " Position Indication Systems -

Operating," on page 3/41-17. 1

Remove the *

footnote from Table 3.3-1 for " Reactor Trip System Instrumentation," on page 3/4 3 5. 1

Remove Action 13 from Table 3.3-1 for " Reactor Trip System Instrumentation," I on page 3/4 3-8.

Remove the ### footnote from Table 3.3 3 for " Engineered Safety Feature Actuation System Instrumentation," on page 3/4 3-22. I

Remove the # footnote from SR 4.4.11.a for " Reactor Coolant System Head Vents," on page 3/4 4 28.

Remove the

footnote from SR 4.8.1.1.2.f for "A. C. Sources," on

~

page 3/4 8-6.

t

Remove the

footnote from SR 4.8.2.3.2.e for "D. C. Distribution - Operating,"

on page 3/4 8-13.

Remove the *

footnote from the Applicability statement of TS 3.9.8.2 for " Low '

Water Level," on page 3/4 9-8a.

Unit 2 -

- Remove the

footnote from SR 4.1.3.4.c for'" Rod Drop Time," on ,

page 3/41-19.

Remove the *

footnote from Table 3.3-1 for " Reactor Trip System ,

Instrumentation," on page 3/4 3-5.

o Remove Action.13 from Table 3.3-1 for " Reactor Trip System instrumentation,"

on page 3/4 3 8.

Remove the ### footnote from Table 3.3-3 for " Engineered Safety Feature Actuation System Instrumentation," on page 3/4 3-22.

.e. Remove the # footnote from SR 4.4.11.a for " Reactor Coolant System Head ..

Vents," on page 3/4 4-33.

i

J <~

e 4

e Remove the

footnote from Limit;ng Condition for Operation 3.5.2 for "ECCS Subsystems," on page 3/4 5-4.

e Remove the

footnote from SR 4.8.1.1.2.f for "A. C. Sources," on s.ago 3/4 8-6.

e Remove the

footnote from SR 4.8.2.3.2.e for "D. C. Distribution - Operating,"

on page 3/4 8-13.

e Remove the *

footnote from the Applicability statement of TS 3.9.8.2 for " Low Water Level," on page 3/4 9-10.

Reason for Chanae The proposed changes correct errors of an editorial nature that have been identified in the SON TSs and removes the provisions that have exceeded the allowed time interval or the required conditions no longer exist. These changes will eliminate potential confusion that could be created by the errors and the outdated provisions that are no longer applicable in the SON TSs.

Justification for Channes The proposed revisions do not change the intent of TS requirements. These changes will clarify the TS verbiage, but will not affect the way the plant is maintained or operated. No setpoints or other plant functions are affected by the proposed revision.

Therefore, the proposed editorial corrections and elimination of outdated provisions will not adversely affect nuclear safety, but will clarify the TS verbiage.

Environmental imonet Evaluation The proposed change does not involve an unreviewed environmental question becauce operation of SON Units 1 and 2 in accordance with this change would not:

1. Result in a significant increase in any adverse envuonmentalimpact previously evaluated in the Final Environmental Statement (FES) a. modified by NRC's testimony to the Atomic Safety and Licensing Board, supplements to the FES, environmentalimpact appraisals, or decisions of the Atomic Safety and Licensing Board,

2. Result in a significant change in effluents or power levels.

3. Result in matters not previously reviewed in the licensing basis for SON that may have a significant environmentalimpact.

u. J

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54F .

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ENCLOSURE 3 PROPOSED TECHNICAL SPECIFICA TION CHANGE ,

SEQUOYAH NUCLEAR PLANT (SON) UNITS 1 AND 2 : ,

DOCKET NOS. 50-327 AND 50-328 -

(TVA-SON-TS 95-12; s

DETERMINATION OF NO SIGNIFICANT HAZA RDS CONSIDERATION 4

f a

9 f

?

k I

.- i 91 m w- w- s y y 1 g

B 31 6 6

.o.

Significant Hazards Evaluation TVA has evaluated the proposed technical specification (TS) change and has determined that it does not represent a significant hazards consideration based on' criteria established in 10 CFR 50.92(c). Operation of Sequoyah Nuclear Plant (SON) in accordance with the proposed amendment will not:

1. Involve a significant increase in the probability or consequences of an accident previously evaluated.

The proposed revisions do not change the TS requirements, plant setpoints or functiona. or plant operating practices. These changes provide clarifications to the '.sxisting T8s by correcting editorial errors and removing provisions that no longer apply in the specifications. The probability or consequences of an accident will not be increased by providing the proposed verbiage corrections that are editorial and nonintent.

2. Create the possibility of a new or different kind of accident from any previously analyzed.

No plant functions or compliance activities associated with the TS requirements have been affected by the proposed editorial changes. Therefore, the possibility.

of a new or different kind of accident is not created.

3. Involve a significant reduction in a margin of safety.

The proposed changes will not alter TS setpoint values or functions. The proposed corrections will enhance the application of TS requirements and will support the margin of safety provided by the T6s. Therefore, the margin of safety will not be reduced by the proposed revisions.

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ML20087D274

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