ML20206S013

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Proposed Tech Specs 3.3.3.3, Seismic Instrumentation & Associated Bases,Relocated to Plant Technical Requirements Manual
ML20206S013
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 01/15/1999
From:
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20206S010 List:
References
NUDOCS 9901270159
Download: ML20206S013 (20)
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Text

___.

ENCLOSURE 2 TENNESSEE VALLEY AUTHORITY l

SEQUOYAH PLANT (SQN)

UNITS 1 AND 2 PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE TS-98-09 MARKED PAGES I.

AFFECTED PAGE LIST Unit 1 Index Page V 3/4 3-44 3/4 3-45 3/4 3-46 B 3/4 3-2 B-3/4 3-3' Unit 2 Index Page V 3/4 3-45 3/4 3-46 3/4 3-47 B 3/4 3-2 B 3/4 3-3 II.

MARKED PAGES See attached.

~

9901270159 990115 PDR ADOCK 05000327 P

PDR_

E3-1

=

9 M

k LIMITI9G CON'DITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION FAqE 3/4.2 POWER DISTnTnUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE (AFD) 3/4 2-1 x

3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR-FQ (Z) 3/4 2-5 3/4.2.3 NUCLEAR ENTHALPY ECT CHANNEL FACTOR.

3/4 2-10 R142 3/4.2.4 QUADRANT POWER TILT RATIO.

3/4 2-12 3/4.2.5 DNB PARAMETERS 3/4 2-15 3/4.3 Ile rxUrim.nTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION.

3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION 3/4 3-14 3/4.3.3 MONITORING INSTRUMENTATION-RADIATION MONITORING INSTRUMENTATION 3/4 3-39 MOVABLE INCORE DETECTORS 3/4 3-43

.(.OO N h.........

3/4 3-4 SEISMIC INSTRUMENTATION.

METEOROLOGICAL INSTRUMENTATION 3/4 3-47 REMOTE SHUTDOWN INSTRUMENTATION-3/4 3-50 CHLORINE DETECTION SYSTEMS (DELETED) 3/4 3-54 ACCIDENT MONITORING INSTRUMENTATION.

3/4 3-55 FIRE DETECTION INSTRUMENTATION (DELETED) 3/4 3-58 lR231 DELETED.

3/4 3-70 R152

-EXPLOSIVE GAS MONITORING INSTRUMENTATION 3/4 3-71 4.

August 12, 1997 SEQUOYAH - UNIT 1 V

Amendment No. 62,'i138, 148, 227 i

I

. 'IiGTRUMENTATION SEISMIC INSTRUMENTATION

[

s.

LIMITING CONDITION FOR OPERATION l

n;s 5 pac. Cad a

,s dele +ad

^

3.3.3.3 '5: :ei:rt: :: nit: ring in:tru::ntation she.;n in Tebie 2.0 7 shall be

\\

~~ e_

v1 wnnwww1 _

ADP1 f r A A T I_ f TV-Et 311 tj7;;,

?.CT!0$

a.

uith ene er mere

$ y$

n$t 74 ng gn t7ement; an;p;733;; ;;7 g;7,_

-then 30 deys, prepare sad submit s Special Report to the Commission-pursuant to Spect'ic: tier 5.9.2 within the next 10 d:y cutlining the cause of the neifwuctien end the plan; fer restering t+te instrument (s) to OPERA 0LC status.-

-b.

The previcien: c' Spect'ication: 3.0.3 :nd 3.0.4 are not j

pplic:ble.

helcYe 3/4 3-W TI re u 3/f 3-46 are f

g j

i

\\ SURVEILLANCE REQUIREMENTS'

,Q 19

~

(k 4.3.3.3.

Each of the above seismic monitnring instruments shall be de nstrated OPERABLE by e performance of the CHANNEL CHECK, CHANNEL CALIBRATIOJ and CHANNEL FUNCT L TEST operations at the frequencies shown in Ta l'e 4.3-4.

4.3.3.3.2 Each of t above seismic monitoring instruments ctuated during a seismic event shall be.

tored to OPERABLE status withj1 r24 hours and a j

CHANNEL CALIBRATION perfor.,

within 5 days followingAbe seismic event. Data shall be retrieved from actua instruments and ansflyzed to determine the l

magnitude of the vibratory groun otion. A 5 JH:Tal Report shall be prepared and submitted to the Commission purs nt to ecification 6.9.2 within 10 days

~

describing the magnitude, frequency spe m and resultant effect upon facility features important to safety.

i i

i E000YAH - UNIT 1 3/4 3-44 i

7 1:

TABLE 3.3-7 1-SEISMIC MONITORING INSTRUMENTATION l

MINI l

MEASUREMENT INST INSTRUMENTS AND SENSOR LOCATIONS RANGE OP BLE

.1.

Triaxial. Time-History Accelerographg

a. 0-XT-52-75A, Containment, Elev. 734 0-1.0g 1

R85

b. 0-XT-52-758, Annulus, Elev. 680 0-1.0g 1*

l

c. 0-XR-52-77, Diesel Building, Elev. 722 0-1.0g 1

2..

' Triaxial Peak Accelerographs R2:.7

a. 0-XR-52-84, Containment, SIS Pipe, Elev. 702 0.0g i

R85

b. 0-XR-52-83, Containment, UHI Pipe, Elev. 706 0-5.0g 1

R217

c. 0-XR-52-82, Control Building, MCR, l

i.

- Panel 0-M-25, Elev. 739 0-5.0g I

3.

Biaxial Seismic Switches

[

a. 0-XS-52-79, Annulus, Elev..

0.025-0.25g 1*

R85

b. 0-XS-52-80, Annulus, El 680 0.025-0.25g 1*
c. 0-XS-52-81, Annulus, E
v. 680 0.025-0.25g 1*

4.

Triaxial Response-Spec um Recorders R85

a. 0-XR-52-86, Annu s, Elev. 680 2-25.4 Hz, 0.003-32g 1*
b. 0-XR-52-87, R ctor Containment 2-25.4 Hz, 0.003-32g 1

i -

dg., Elev. 734 j

l.

c.

0-XR-5

, Aux. CR, Elev. 734 2-25.4 Hx, 0.003-32g 1

f d.

0-X 2-89, Diesel Generator, 2-25.4 Hz, 0.003-32g I

L E1

. 722

)

{

  • With actor control room indication I

~

October 4, 1995 L

SEQUOY'AH - UNIT 1 3/4 3-45 Amendment No. 12, 81, 213

TABLE 4.3-4 l

, SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS C

i j

CHANNEL-CHANNEL F

IONAL INSTRUMENTS AND SENSOR LOCATIONS CHECK CALIBRATION EST 1.

Triaxial Time-History Acceleregraphs

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

R***

SA R85

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 R217

a. 0-XR-52-84, Containment, SIS Pipe, NA R

NA l

Elev. 702 R85

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

NA

/s*fg Elev. 706 R2]7 NA R

NA

c. 0-XR-52-82, Control Building, MCR, Panel 0-M-25. Elev. 739

</

3.

Biaxial Seismic Switches

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

M R

SA R85

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

N R

SA

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

M R

SA 4.

Triaxial Response-Spectr Recorders

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

R SA R85

b. 0-XR-52-87, Reac r Containment NA R

NA '

B1

. Elev. 734

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

NA

d. 0-XR-52-8), Diesel Building, NA R

NA Elev. 7 t

  • Exfept seismic trigger fth reactor control room indications neludes seismic trigger October 4, 1995 SEQUOYAH - UNIT 1 3/4 3-46 Amendment No. 12, 81. 213

INSTRUMENTATION BASES The measurement of response time at the specified frequencies provides assurance that the protective and ESF action function associated with each channel is completed within the time limit assumed in the accident analyses.

No credit was taken in the analyses for those channels with response times indicated as not applicable in the updated final safety analysis report.

l R194 i

Response time may be demonstrated by any series of sequential, overlapping or total channel test measurements provided that such tests demonstrate the total channel response time as defined. Sensor response time verification may i

be demonstrated by either 1) in place, onsite or offsite test measurements or

2) utilizing replacement sensors with certified response times.

Action 15 of Table 3.3-1, Reactor Trip System Instrumentation, allows the breaker to be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for the purpose of performing R58 maintenance. The 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is based on a Westinghouse analysis performed in WCAP-10271, Supplement 1, which determines bypass breaker availability.

3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 RADIATION MONITORING INSTRUMENTATION The OPERABILITY of the radiation monitoring channels ensures that 1) the radiation levels are continually measured in the areas served by the individual channels and 2) the alarm or automatic action is initiated when the radiation

/

level trip setpoint is exceeded, j

3 /4. 3. 3. 2 MOVABLE INCORE DETECTORS The OPERABILITY of the movable incore detectors with the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the reactor core. The OPERABILITY of this system is demonstrated by irradiating each detector used and determining the acceptability of its voltage curve.

For the purpose of measuring F,(z) or FL a full incore flux map is used.

Quarter-core flux maps, as defined in WCAP-8648, June 1976, may be used in recalibration of the excore neutron flux detection system, and full incore flux maps or symmetric incore thimbles may be used for monitoring the QUADRANT POWER TILT RATIO when one Power Range Channel is inoperable.

3/4.3.3.3 SEISMIC INSTRUMENTATION n;z S delefd.b

-- The OPEPJL,. qeescd.., ;sI.. Of the sc4smie-instrument: tion enswer that zuf44t-ien c:p:bility is ev:il:bic te prcmptly detemine the m:gnitude of a seismis-event-and evaluate the re:pcase-ef-these-feature importent to :sfety.

This c+pab444ty

-4e-+equired-tc permit-comparisen ef--the me:sweu response to that4&ed-fr the SEQUOYAH - UNIT 1 B 3/4 3-2 Amendment No. 54, 190 November 9, 1994

\\

i INSTRUMENTATION i

BASES am 4mm s.,4.

<m. +sm < "ity to deter =ine if plant shutd;wn is required

---pur4uant te Appendiv "8" cf 10 CP Part 100.

All p 04f4 d ::::wement r:ng::

--represent the mini =" range: Of th: instre: nt:.

Thi: instrumentati n i: -

R85 centistent with the recert:nd tion: Of R:gulat ry Cuid: 1.12, "Instre ntat4en-

-fer E:rth;2:k::," April 1974.

1 3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere.

This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the p'Onsite Meteorological Programs," February 1972.ublic and is consisten 3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION The OPERABILITY of the remote shutdown instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT STANDBY of the facility and the potential capability for subsequent cold shut-down from locations outside of the control room.

3R This capability is required in the event control room habitability is lost and is consistent with General Design Criterion 19 of 10 CFR 50.

3/4.3.3.6 CHLORINE DETECTION SYSTEMS R66 This specification deleted.

3/4.3.3.7 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables following an accident.

This capability is consistent with the recommendations of Regulatory Guide 1.97, Revision 2, " Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During R153 and Following an Accident," December 1980.

4 l

The postaccident monitoring instrumentation limiting condition for opera-j tion provides the requirement of Type A and Category 1 monitors that provide information required by the control room operators to:

R163 Permit the operator to take preplanned manual actions to accomplish safe plant shutdown.

Determine whether systems important to safety are performing their intended functions.

I SEQUOYAH - UNIT 1 B 3/4 3-3 Amendment No. 62, 81, 149 159 July 9, 1992

/

l l

INDEX

,. w

-,)

W LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION p.A_qg l

i 3/4.2 POWER DISTRIBUTION LIMITS j

i 3/4.2.1 AXIAL FLUX DIFFERENCE'(AFD) 3/4 2-1 i

~

i 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR-FQ(Z) 3/4 2-4

]

3/4.2.3 NUCLEAR ENTHALPY HOT CHANNEL FACTOR.,

3/4 2-8 1

3/4.2.4 QUADRANT POWER TILT RATIO 3/4 2-10 R130 j

3/4 2.5

.DNB PARAMETERS 3/4 2-13 j

3/4.3 TNSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION.

3/4 3-1 l

3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION 3/4 3-14 3/4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION 3/4 3-40

)

3/4 3-44 MOVABLE INCORE DETECTORS ISMICINSTRUMENTATION.(O6MI8O 3/4 3-4

.......,..... s 3/4 3-48 M5TEOROLOGICAL INSTRUbENTATION REMOTE SHUTDOWN I'NSTRUMENTATION 3/4 3-51 CHLORINE DETECTION SYSTEMS (DELETED).

.3/4 3-55 R54 ACCIDENT MONITORING INSTRUMENTATION.

3/4 3-56 FIRE DETECTION INSTRUMENTATION (DELETED) 3/4 3-59 lR218 DELETED.........................

3/4 3-68 R134 EXPLOSIVE GAS MONITORING INSTRUMENTATION 3/4 3-69 August 12, 1997 SEQUOYAH - UNIT 2 V

Amendment No. 54, 130, 134, 218

.. - - - =

INSTRUMENTATION

- SEISMIC INSTRUMENTATION LIMITING CONDITION FOR OPERATION The
:que.Seet, os bie5eN.

71,;c

f: eenit r ng 4 :trementatier chew 4-T:ble 3.2 ' chel' be i

3.3.3.3

.m n e n n. e,

^""LIC^BILITY:

^t :l' time:.

APT me.T.AU.

n.

With One er acre seisai: ;;nitoring instrument; inoper:ble fer : r e.

th;n 30 days, prcp;re :nd ubmit ; Special "eport to the C; :i :ica pur:uant te Specificati;n 5.9.2 within the next 10 d y: Outlining th: cause of the selfunction and the plans for rc:tcring the

-4*ttrueent(s) t: 0"EE^.BLE Statur.

5.

The previsien; cf Specific:tien; 3.0.3 :nd 3.0.4 are not :ppif :ble.

1 3/43'l5 ll,j 3/+

3-47 nee olalebe eg f

a

\\

'5URVEILLANCE REQUIREMENTS 4.3.3.3.

Each of the above seismic monitoring instruments shall be demonstrat OPERABLEbytheperformanceoftheCHANNELCHECK,CHANNEJ own in CALIBRATIONaddCHANNELFUNCTIONALTESToperationsatthefrequencigst s

Table 4.3-4.

[L 4.3.3.3.2 Each of the ove seismic monitoring instruments uated during a seismic event shall be re red to OPERABLE status withi hours and a CHANNEL CALIBRATION performe ithin 5 days following) e seismic event.

Data shall be retrieved from actuate nstruments and ajr lyzed to determine the magnitude of the vibratory ground m ion.

A Spydal Report shall be prepared

~

and submitted to the Commission pursua to fecification 6.9.2 within 10 days describing the magnitude, frequency spect and resultant effect upon facility features important to safety.

l 9

s-00YAH - UNIT 2 3/4 3-45

l l

l l

TABLE 3.3-7 m

h/

SEISMIC MONITORING INSTRUMENTATION MINI MEASUREMENT INST ENT 1

INSTRUMENTS AND SENSOR LOCATIONS RANGE RABLE

'1.

Triaxial Time-History Accelerographs R72

a. 0-XT-52-75A, Containment, Elev. 734 0-1.0g 1
b. 0-XT-52-75B, Annulus, Elev. 680 0-1.0g 1*
c. 0-XR-52-77, Diesel Building, Elev. 722 0-1.0g 1

2.

Triaxial Peak Accelerographs i

R203

a. 0-XR-52-84, Containment, SIS Pipe, l

Elev. 702 0.0g 1

b. 0-XR-52-83, Contain:nent, UHI Pipe, Elev. 706 0-5.0g 1

R203

c. 0-XR-52-82, Control Building, MC l

Panel 0-M-25, Elev. 739 0-5.0g '

1 h

3.

Biaxial' Seismic Switches.

V f4 v

a. 0-XS-52-79, Annulus, Elev.

0.025-0.25g 1*

R72

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

, 1*

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

4.

Triaxial Response-Spec um Recorders

a. 0-XR-52-86, Annu us, Elev. 680 2-25.4 Hz, 0.003-32g le R72
b. 0-XR-52-87, actor Containment 2-25.4 Hz, 0.003-32g 1

/1dg., Elev. 734 c.

0-XR-5 -88, Aux. CR, Elev. 734 2-25.4 Hx, 0.003-32g 1

d.

0-X 89, Diesel Generator, 2-25.4 Hz, 0.003-32g 1

E

v. 722
  • With 'eactor control room indication t'

October 4, 1995 SEQUOYAH - UNIT 2 3/4 3-46 Amendment No. 72, 203

TABLE 4.3-4 I

jflSMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS i

^.

CHANNEL l(6j CHANNEL CHANNEL FUNCTIONAL i

~ ' " '

INSTRUMENTS AND SENSOR LOCATIONS CHECK CALIBRATION TEST j

1.

Triaxial Time-History Acceleregraphs R72

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

R***

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 R203

a. 0-XR-52-84, Containment, SIS Pipe, NA NA l

1 Elev. 702 R72

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

NA Eley. 706 R203

c. 0-XR-52-82, Control Building, MCR, R

NA l

Panel 0-M-25, Elev. 739

/

h f

3.

81 axial Seismic Switches

'v

a. 0-XS-52-79, Annulus, Elev. 6 0 M

R SA R72 0'

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

R SA f

M R

SA

c. 0-XS-52-81, Annulus, ley. 6 4.

Traixial Response-Spectrum corders

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

R SA R72

b. 0-XR-52-87, Reacto Containment

, NA R

NA Bldg Elev. 734

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

NA

,i

d. 0-XR-52-89 Diesel Building, NA.

R NA

~

l Eley, 72 1

l

  • Exce seismic trigger
    • Wi reactor control room indications
      • I cludes seismic trigger October 4, 1995 SEQUOYAH - UNIT 2 3/4 3-47 Amendment No. 72, 203 1

l INSTRUMENTATION f

BASES 6

REACTOR TRIP SYSTEM AND ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION (Continued) i i

The measurement of response time at the specified frequencies provides i

assurance that the protective and the engineered safety feature actuation associated with each channel is completed within the time limit assumed in the accident analyses.

No credit was taken in the analyses for those channels with response times indicated as not applicable in the updated final safety analysis report.

R182 Response time may be demonstrated by any series of sequential, overlapping or total channel test measurements provided that such tests demonstrate the total channel response time as defined.

Sensor response time i

verification may be demonstrated by either 1) in place, onsite or offsite test measurements or 2) utilizing replacement sensors with certified response times.

Action 15 of Table 3.3-1, Reactor Trip System Instrumentation, allows the breaker to be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for the purpose of performing R46 maintenance.

The 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is based on a Westinghouse analysis performed in l

WCAP-10271, Supplement 1, which determines bypass breaker availability.

~

The placing of a channel in the trip condition provides the safety function of the channel.

If the channel is tripped for testing and no other BR-10 condition would have indicated inoperability, the channel should not be declared inoperable.

e 3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 RADIATION MONITORING INSTRUMENTATION The OPERABILITY of the radiation monitoring channels ensures that 1) t'he radiation levels are continually measured in the areas served by the individual channels and 2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded.

3/4,3,3.2 MOVABLE INCORE DETECTORS The OPERABILITY of the movable incore detectors with the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the reactor core.

The OPERABILITY of this system is demonstrated by irradiating each detector used and determining the acceptability of its voltage curve.

. - ~

l For the purpose of measuring F (X,Y Z) or Fa(X,Y) a full incore flux map q

lR214 is used. Quarter-core flux maps, as defined in WCAP-8648, June 1976, may be used in recalibration of the excore neutron flux detection system, and full incore flux maps or symmetric incore thimbles may be used for monitoring the QUADRANT POWER TILT RATIO when one Power Range Channel is inoperable.

(3/4.3.3,3 SEISMIC INSTRUMENTATION rne urtnra!Lir: ni the ceirrie inetr ---t:tien -""uree

  • k"t

?"fficient p dility i: cvrilable te p:Orptly d:t-ermin; th; m:F.itud Of : Stieri C't::t

-' ---lust; th: :::perr: Of th::: featur;: imp;rtan; :: ::fety. Thi:

pthility i: r;quir:d t0 permit ;; perieen af Chu umaesced resp;n : Le that ured in the R7z v

April 21, 1997 SEQUOYAH - UNIT 2 B 3/4 3-2 Amendment Nos. 46, 72, 182, 214

INSTRUMENTATION r

g

\\c BASES

--3/4. 3. 3. 3 SEISMie-fMTRUMENTATION (Cuntinued) d ;ign bes4s for the f :ility to d:te =in if pl:nt shutdown i: r quired purssent te Appendix "A" Of 10 CFP, Port 100.

All :pe ifi d =ca;ur:: nt r:nge:

represent the ininima: r:ng ; cf th instrum:nt;.

The in;tre entatier 1:

R72 consistent with the re;;x:ndetiens of "seguletery Cuid: 1.12, "Is tru=ent tion fer Certhquekes," April 197' 3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data is available for estimating potential radiation l

doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere.

This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public and is consistent with the recommendations of Regulatory. Guide 1.23, "Onsite Meteorological Programs," February 1972.

i 3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION The OPERABILITY of the remote shttdown instrumentation ensures that suf-ficient capability is available to permit shutdown and maintenance of HOT

(-

STANDBY of the facility and the potential capability for subsequent cold shut-l down from locations outside of the control room..This capability is required BR l

in the event control room habitability is lost and is consistent with General Design Criterion 19 of 10 CFR 50.

l 3/4.3.3.6 CHLORINE DETECTION SYSTEMS R54 This specification deleted.

3/4.3.3.7 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables following an accident.

This capability is consistent with the recommendations of Regulatory Guide 1.97, Revision 2, " Instrumentation R135 i

for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During l

and Following an Accident," December 1980.

t.

The postaccident monitoring instrumentation limiting condition for opera-tion provides the requirement of Type A and Category 1 monitors that provide

-information required by the control room operators to:

R149 Permit the operator to take preplanned manual actions to accomplish safe

+

plant shutdown.

(-

SEQUOYAH - UNIT 2 8 3/4 3-3 Amendment Nos. 35,46,54,72,135 149 July 9, 1992

)

ENCLOSURE 3 TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT (SQN)

UNITS 1 AND 2 i

PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE TS REVISED PAGES I.

AFFECTED PAGE LIST Unit 1 Index Page V i

3/4 3-44 3/4 3-45 3/4 3-46 B 3/4 3-3 i

i Unit 2 Index Page V 3/4 3-45 3/4 3-46 3/4 3-47 j

B 3/4 3-3 i

II.

REVISED PAGES 1

See attached.

r E3-2

i INDEX LIMITING DONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS i

i t

EECTION PAGE i

3/4.2 POWER DISTRIBUTION LIMITS i

3/4.2.1.

AXIAL FLUX DIFFERENCE. (AFD) 3/4 2-1 t

3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR-FQ (Z) 3/4 2-5 l

3/4.2.3:

NUCLEAR ENTHALPY HOT CHANNEL FACTOR.

3/4 2-10 R142 1

3/4.2.4

' QUADRANT POWER TILT RATIO.

3/4 2-12 1

-3/4.2.5_

DNB PARAMETERS 3/4 2-15

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3/4.3 INSTRUMENTATION l

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- 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION..

3/4 3-1 i

3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION 3/4 3-14 i

. 3/4.3.3-MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION 3/4 3-39 i

MOVABLE INCORE DETECTORS 3/4 3-43 SEISMIC INSTRUMENTATION (DELETED) 3/4 3-44 l

METEOROLOGICAL INSTRUMENTATION-3/4 3-47.

j REMOTE SHUTDOWN INSTRUMENTATION 3/4 3-50 CHLORINE DETECTION SYSTEMS (DELETED) 3/4 3-54 ACCIDENT MONITORING INSTRUMENTATION.

3/4 3-55 I

FIRE DETECTION INSTRUMENTATION (DELETED) 3/4 3-58 lR231 f

DELETED'.

.3/4 3-70 R152 EXPLOSIVE GAS MONITORING INSTRUMENTATION 3/4 3-71 f

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I SEQUOYAH -l UNIT l' V.

Amendment No. 62, 138, 148, 227, L

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INSTRUMENTATION SEISMIC INSTRUMENTATION I

i LIMITING CONDITION FOR OPERATION

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3.3.3.3 This specification is deleted.

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t (Pages 3/4 3-44 through 3/4 3-46 are deleted) l i

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l SEQUOYAH - UNIT 1 3/4 3-44 Amendment No. 12, 81, 213,

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i INSTRUMENTATION BASES i

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3/4.3.3.3 SEISMIC INSTRUMENTATION 1

This specification is deleted.

l 3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data is available for estimating potential radiation

~ doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere. This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the 1

public and is consistent with the recommendations of Regulatory Guide 1.23, "Onsite Meteorological Programs," February 1972.

3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION The OPERABILITY of the remote shutdown instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT BR STANDBY of the-facility and the potential capability for subsequent cold shut-down from locations outside of the control room.

This capability is required in the event control room habitability is lost and is consistent with General Design Criterion 19 of 10 CFR 50, 3/4.3.3.6 CHLORINE DETECTION SYSTEMS This specification deleted.

R66 l

3/4.3.3.7 ACCIDENT MONITORING INSTRUMENTATION

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The OPERABILITY of the accident monitoring instrumentation ensures that i

sufficient information is available'on selected plant parameters to monitor and assess these variables following an accident. This capability is consistent with the recommendations of Regulatory Guide 1.97, Revision 2, " Instrumentation-I for Light-Water-Cooled Nuclear Fower Plants to Assess Plant Conditions During R153 1

l and Following an Accident," December 1980.

l The postaccident monitoring instrumentation limiting condition for operation provides the requirement of Type A and Category 1 monitors that provide information required by the control room operators to:

Permit the operator to take preplanned manual actions to accomplish safe R163 plant shutdown.

Determine whether systems important to safety are performing their intended functions.

1 SEQUOYAH - UNIT 1 B 3/4 3-3 Amendment No. 62, 81, 149,

159, l

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l INDEX LIM'ITING DONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS l

L SECTION pg[g l

3/4.2 ' POWER DISTRIBUTION LIMITS I

1 3/4.2.1 AXIAL FLUX DIFFERENCE (AFD).

3/4 2-1 l

3/4.2 2 HEAT FLUX HOT CHANNEL FACTOR-FQ(Z)-

3/4 2-4

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3/4.2.3 NUCLEAR ENTHALPY HOT CHANNEL FACTOR.

3/4-2-8

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.3/4;2.4.

QUADRANT POWER TILT RATIO.

3/4 2-10 R130 t

'3/4 2.5-DNB PARAMETERS 3/4 2 l 3 /4. 3 INSTRUMENTATION 3/4.3.1

~ REACTOR TRIP SYSTEM INSTRUMENTATION.

3/4 3-1 i

3/4.3.2' ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION 3/4 3-14 I

3/4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION 3/4.3-40 MOVABLE INCORE DETECTORS 3/4 3-44

.3/4 3-45' l

SEISMIC INSTRUMENTATION.(DELETED)

METEOROLOGICAL INSTRUMENTATION 3/4 3-48

.i REMOTE SHUTDOWN INSTRUMENTATION 3/4 3-51' i

CHLORINE DETECTION SYSTEMS (DELETED).

.3/4 3-55 R54 s

- (5 l

ACCIDENT MONITORING INSTRUMENTATION.

3/4 3-56 FIRE DETECTION INSTRUMENTATION (DELETED) 3/4 3-59 lR218 l

_ DELETED.

.3/4 3-68 R134 i

EXPLOSIVE GAS MONITORING INSTRUMENTATION 3/4 3-69 l

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-- SEQUOYAH - UNIT 2 V

Amendment No. 54, 130, 134, 218, i

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INSTRUMENTATION EEISMIC INSTRUMENTATION LkMITINGCONDITIONFOROPERATION 3.3.3.3 This specification is deleted.

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(Pages 3/4 3-45 through 3/4 3-47 are deleted)

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SEQUOYAH - UNIT 2 3/4 3-45 Amendment No. 72, 203,

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INSTRUMENTATION BASES..

3/4.3.3.3 SEISMIC INSTRUMENTATION This specification is deleted.

l 3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION l

The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere.

This capability is required to evaluate the need for initiating pro **ctive measures to protect the health and safety of the public and is cons 'tnat with the recommendations of Regulatory Guide 1.23, "Onsite Meteorologa-1 Programs," February 1972.

3/4.3.3.5 REMOTE SILTDOWN INSTRUMENTATION The OPERABILITY of the remote shutdown instrumentation ensures that suf-ficient capability is available to permit shutdown and maintenance of HOT STANDBY of the facility and the potential capability for subsequent cold shut-down from locations outside of the control room.

This capability is required in the event control room habitability is lost and is consistent with General BR Design Criterion 19 of 10 CFR 50, 3/4.3.3.6 CIEORINE DETECTION SYSTEMS R54 This specification deleted.

3/4.3.3.7 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables following an accident. This capability is consistent with the recommendations of Regulatory Guide 1.97, Revision 2,

" Instrumentation R135 for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During l

and Following an Accident," December 1980.

The postaccident monitoring instrumentation limiting condition for operation provides the requirement of Type A and Category 1 monitors that R149 provide information required by the control room operators to:

Permit the operator to take preplanned manual action to accomplish safe plant shutdown l

SEQUOYAH - UNIT 2 B 3/4 3-3 Amendment Nos. 35, 46, 54, 72, 135, 149, l

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