Text

Proposed Tech Specs Deleting Ref to Three Loop Operation
	ML20128E578
Person / Time
Site:	Sequoyah
Issue date:	05/21/1985
From:	; TENNESSEE VALLEY AUTHORITY
To:	;
Shared Package
ML20128E553	List: ML20128E548; ML20128E578;
References
	NUDOCS 8505290419
	Download: ML20128E578 (21)
	v • d • e

r-2.0 SAFETY LIMITS AND' LIMITING SAFETY SYSTEM SETTINGS

~

i 2.1 SAFETY LIMITS REACTOR CORE 2.1.1 The combination of THERMAL POWER, pressurizer pressure, and the highest operating loop coolant temperature (T,yg) shall not exceed the limits shown in Figures 2.1-1,:nd 2.'-2 fer ' : d 21::; :;:::ti: , ::p:;;i;;;3 APPLICABILITY: MODES 1 and 2.

ACTION:

Whenever-the point defined by the combination of the highest operating loop average temperature and THERMAL POWER has exceeded the appropriate pressurizer pressure line, be in HOT STANDBY within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

REACTOR COOLANT SYSTEM PRESSURE 2.1.2 The Reactor Coolant System pressure shall not exceed 2735 psig. '

APPLICABILITY: MODES 1, 2, 3, 4 and 5.

ACTION:

MODES 1 and 2 Whenever the Reactor Coolant System pressure has exceeded 2735 psig, be in HOT STANDBY with the Reactor Coolant System pressure within its limit within i hour.

MODES 3, 4 and 5 Whenever the Reactor Coolant System pressure has exceeded 2735 psig, reduce the Reactor Coolant System pressure to within its limit within 5 minutes.

SEQUOYAH - UNIT 1 2-1 i 8505290419 850521 PDR ADOCK 05000327 p PDR b

ure 2.1-2 Reactor Core Safety Limi - Three Loops i eration This pag ft blank p ing NRC appro of three loop ope ion O

T -

1 l

b e

i l ,

i

+

SEQUOYAH - UNIT 1 2-3

REACTIVITY CONTROL SYSTEMS CONTROL R00-INSERTION LIMITS LIMITING CONDITION FOR OPERATION 3.1.3.6, The control banks shall be limited in physical insertion as shown in Figureg 3.1-1,6 APPLICABILITY: MODES 1* and 2*#.

ACTION:

With the control' banks inserted beyond the above insertion limits, except for surveillance testing pursuant to Specification 4.1.3.1.2, either:

a. Restore the control banks to within the limits within two hours, or

b. Reduce THERMAL POWER within two hours to less than or equal'to that fraction of RATED THERMAL POWER which is allowed by the group position using the above figures, or

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

SURVEILLANCE REQUIREMENTS 4.1.3.6 The position of each control bank shall be determined to be within.

the insertion limits at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during time intervals when the Rod Insertion Limit Monitor is inoperable, then verify the individual rod positions at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , o

"See Special Test Exceptions 3.10.2 and 3.10.3.

With K,ff greater than or equal to 1.0.

SEQUOYAH - UNIT 1 3/4 1-21 -

. . = - -

- ..:- - . u .: . . . .

m -- - - .

Figu .1-2 le ank pe NRC a val of three operat r

w <hd.

l l cs _

one 4

9 e

SEQUOYAH - UNIT 1 3/4 1-23 i

l

~

PI

. ,/

TABLE 3.2-1 iE DNB PARAMETERS S

E i LIMITS C

5

-d 4 Loops In 3 L p; in PARAMETER Operation Cp ratien** -

w Reactor Coolant System T,yg < 583*F Pressurizer Pressure > 2220 psia

u,

Limit not applicable during either a THERMAL POWER ramp in excess of 5% RATED THERMAL POWER _

3: per minute or a THERMAL POWER step in excess of 10% RATED THERMAL POWER, physics test, or performance {j((h g, of surveillance requirement 4.1.1.3.b. 4

=7

~

U$ **Li-it; pending "RC appr ;;l of 310 p operati:n I

4

, TABLE 3.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION e

e MINIMUM c-TOTAL NO. CHANNELS CHANNELS APPLICABLE D FUNCTIONAL UNIT TO TRIP

] OF CHANNELS OPERABLE MODES ACTION 6

1. Manual Reactor Trip 2 2 1, - 2, arid

1 1 h3

2. Power Range, Neutron Flux 4 2 3 1, 2 2

3. Power Range, Neutron Flux 4 2 3 1, 2 2 High Positive Rate

4. Power Range, Neutron Flux, 4 2 3 1, 2 2 High Negative Rate

5. Intermediate Range, Neutron Flux 2 1 2 1, 2, and

3 w 6. Source Range, Neutron Flux 4 A. Startup 2 1 2 2g ,, and

4 B. Shutdown 2 0 3, 4 and 5 1 5 7., Overtemperature Delta T four Loop Operation 4 2 3 1, 2 6, h

ree Leep Oper:ti:r. '

1** 3 1, 2 0

8. Overpower Delta T

Four Loop Operation 4 2 3 1, 2 6,

'":: '::; 0;:r: tier 1** 3 1, 2 0

9. Pressurizer Pressure-Low 4 2 3 1, 2 6

10. Pressurizer Pressure--High 4 2 3 1, 2 6

11. Pressurizer Water Level--High 3 2 2 1, 2 7

TABLE 3.3-3 N

j@ ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SE E

, MINIMUM

c. TOTAL NO. CHANNELS CHANNELS APPLICABLE g5 FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE H0 DES ACTION a

>" 1. SAFETY INJECTION, TURBINE TRIP AND FEE 0 WATER ISOLATION

a. Manual Initiation 2 1 2 1,2,3,4 20

b. Automatic Actuation 2 1 2 1,2,3,4 15 Logic

c. Containment 3 2 2 1,2,3 16*

,, Pressure-High s

['

j,

, d. Pressurizer Pressure - Low 3 2 2 1, 2, 3# 16*

u,

e. Differential _

1,2,3 Pressure Between.

,- Steam Lines - High Four Loops 3/ steam line 2/ steam line 2/ steam line 16*

Operating any steam line

,u_.. .. ,r...-. :.. ,000s. .._ .i..... s.. ,,

A.,.l!. !. 7. :-,:"'

I'.

....- ' ' ' ' _r.'"

' , ..' ' ::~ I',III' I ".'"

i!5hrl ~'I r e

TABLE 3.3-3 (Continued) y ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION 8

E MINIMUM i TOTAL NO. CHANNELS CHANNELS APPLICABLE e

z FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

f. Steam Flow in Two 1, 2, 3" Steam Lines-High Four Loops 2/ steam line 1/ steam line -1/ steam line 16*

Operating any 2 steam lines .

It.ru Lxp; 2/cperatin; !"# eny

/ 1/epareting 17 n___,. _ ..___ i __ ____ .: _._,_ 3 __

r+cr 'ne

$ COINCIDENT WITH EITHER g w T --Low-Low 1, 2, 3 avg Four Loops 1Tavg/ loop 2T avg any 1T avg any 16*

Operating loops 3 loops Three Loops 1Tavg/ 1"#T avg in 1T avg in any 17 Operating operating any operating two operating loops loops loops OR, COINCIDENT WITH Steam Line Prassure-Low 1, 2, 3 H

Four Loops 1 pressure / 2 pressures 1 pressure 16*

Operating loop any loops any 3 loops

,m__ .

.y.......,

, #N .v . . . . . .

,v.......

ChCISIii.5 O^C y rrsIiI.5 ir. 07.} Or di iri CI.h A

?::; it!..; I::; ;;;r;t' ;; 1 :p:

e

v, TABLE 3.3-3 (Continued)

E g ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION 5lE m MINIMUM

' TOTAL NO. CHANNELS CHANNELS APPLICABLE g FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION Z

g c. Containment Ventilation Isolation -

1) Manual 2 1 2 1,2,3,4 19 -

b

2) Automatic Isolation 2 1 2 1,2,3,4 15 Logic

3) Containment Gas 2 1 1 1,2,3,4 19 Monitor Radioactivity-High

4) Containment Purge 2 1 1 1,2,3,4 19 Air Exhaust Monitor y Radioactivity-High

5) Containment Particu- 2 1 1 1,2,3,4 19

[ late Activity High

,1 co

4. STEAM LINE ISOLATION ~>

IS

a. Manual 1/ steam line 1/ steam line 1/ operating 1,2,3 25 j -

steam line s 7

, il :* b. Automatic 2 1 2 1,2,3 23 db Actuation Logic

.i! )

5

c. Containment Pressure-- 4 2 3 1,2,3 18 3ca High-High g cn g 'R d. Steam Flow in Two 1,2,3

{l Steam Lines--High Four Loops 2/ steam'line 1/ steam ifne 1/ steam line 16*

Operating any 2 steam lines Thron Innne 9 /nna s+ t an 1 000 /--, i/---- :__ s, Annemtinry insE kin [

e nn s[4 nn ,+ E' 54 ter u ne 1

TABLE 3.3-3 (Continued)

M ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION jg S

E MINIMUM CHANNELS CHANNELS APPLICABLE TOTAL NO. ACTION c: TO TRIP OPERABLE MODES FUNCTIONAL UNIT OF CHANNELS g5 w

- COINCIDENT WITH EITHER 1, 2,' 3 T --Low-Low any 16*

avg Four Loops 2T any 1T 1Tavg/ loop j,,gvg 3108%9 Operating vm___ ,____

~~r' : :.ava,

...- ,'."..r ,' :_ _ lava ;"_ .'ava_ "

.-..r.... "."3

...,.r......., -,

-rs . o e . . 3 1::; ?::p .

OR, COINCIDENT WITH 1, 2, 3

Steam Line Pressure-Low 1 pressure 16*

U$ Four Loops 1 pressure / 2 pressures Operating loop any loops any 3 loops

'### pc;;;;r: 1 ;r ;;;r: '-

I T.'.. L..p; ' pr;;; ;/

r

ting '

: ; ' :ny ;:r- :ny 2 :;:r-C;:r: tin;

( :t'n; 1::p : tin; ': ;c t

5. TURBINE TRIP &

FEE 0 WATER ISOLATION 2/ loop in 2/ loop in 1, 2, 3 16*

a. Steam Generator 3/ loop Vater Level-- any oper- each oper-High-High 'ating loop ating loop r

s l

2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.1- SAFETY LIMITS

' REACTOR CORE 2.1.1 The comoination of THERMAL POWER, pressurizer pressure, and the highest

. operating loop coolant temperature (Tavg) shall not exceed the limits shown in Figures 2.1-l 'and 2.1-2,f:r ' ::d 2 1::p :pcr;ti: , 7::;;;tiv:la.

APPLICABILITY: MODES 1 and 2.

ACTION:

Whenever the point defined by the comoination of the highest operating loop average temperature and THERMAL POWER has exceeded the appropriate pressurizer pressure line, be in HOT STANDBY within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

REACTOR COOLANT SYSTEM PRESSURE 2.1.2 The Reactor Coolant System pressure shall not exceed 2735 psig.

APPLICA3ILITY: MODES 1, 2, 3, 4 and 5.

ACTION:

MODES'l and 2 Whe er the Reactor Coolant System pressure has exceeded 2735 psig, be

.in Hur STANDBY with the Reactor Coolant System pressure within its limit within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

MODES 3, 4 and 5 - -

Whenever the Reactor Coolant System pressure has exceeded 2735 psig, reduce the Reactor Coolant System pressure to within its limit within 5 minutes.

SEQUOYAH - 2 2-1

.~: - :. . : *. ~ ~. . . .~ . - ,

. . . . . ~ "~ ~ ; .

FIGURE .1-2 R tor Core fety L t Thre cops in eration Th pendin NRC appro I three 1 opera n.

l bb b O hl h Q.

1 SEQUOYAH - 2 2-3

REACTIVITY CONTROL SYSTEMS CONTROL R00 INSERTION LIMITS r.

LIMITING CONDITION FOR OPERATICN 3.1.3.6 The control banks shall be limited in physical insertion as shown'in Figur 3.1-li .-d 2.'-2.

l --

APPLICABILITY: MODES la and 2*#, .

ACTION: ~

With the control banks inserted beyond the above insertion limits, except for surveillance testing pursuant to Specification 4.1.3.1.2, either:

a. Restore'the control banks to within the limits within two hours, or

b. Reduce THERMAL POWER within two hours to less than or equal to that fraction of RATED THERMAL POWER which is allowed by the group position using the above figures, or

c. Be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

50RVEILLANCE REQUIREMENTS 4.1.3.6 .The position of each control bank shall be determined to be within the insertion limits at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during time intervals when the Rod Insertion Limit Monitor is inoperable, then verify the individual rod positions at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

"See Special Test Exceptions 3.10.2 and 3.10.3.

With K,7f greater than or equal to 1.0.

SEQUOYAH - UNIT 2 3/4 1-21

REACTIVITY CONTROL SYSTEMS

~

ure -2 ft b nk n N ap oval th lo o a on TMS OcWe E-toe ed SEQUOYAH - UNIT 2 3/4 1-23

TABLE 3.2-1 g DNB PARAMETERS 5!

E '

LIMITS ,

4 Loops In -5L::;;Ir^^^a-PARAMETER Operation , li g. m n . 2 u ,

v-v- - -- j

< 583*F

^^

Reactor Coolant System T,yg Pressurizer Pressure > 2220 psia

i .

w 1

i '?

O i

5N 23

=~ a Limit not applicable during either a THERMAL POWER ramp in excess of 5% of RATED THERMAL M!

" POWER per minute or a THERMAL POWER step in excess of 10% of RATED gTHERMAL POWER, ph

^^

test, or performance of surveillance requirement 4.1.1.3.b. 77 Gg . ;-, r ..J.. ,.';^^ app.;.;? c,f 2 ?;;p ;;; ret!;.; d 7

03 . .

/

D PJ Un

't

TABLE 3.3-1 REACIOR TRIP SYSTEM INS 1RUMINTATION

$ MINIMUM e 10TAL NO. CilANNELS CilANNELS APPLICABLE c FUNCTIONAL UNil Of CilANNELS IO IRIP OPERABLE MODFS AC110N

1. Manual Reactor Trip 2 1 .2 1, 2, aiid ^ 1

[

2. Power Range, Neutron Flux 4 2 3 1, 2 2

3. Power Range, Neutron Flux 4 2 3 1, 2 2 liigh Positive Rate

4. Power Range, Neutron Flux, 4 2 3 1, 2 2 liigh Negative Rate *

5. Intermediate Ran0e, Neutron Flux 2 1 2 1, 2, and

3

{

Y 6. Source Range, Neutron Flux A. Startup 2 1 2 2##, and

4 B. Shutdown 2 0 1 3, 4 and 5 5

7. Overtemperature AT 6, Four Loop Operation 4 2 3 1, 2

^

! ; . . . '. _ g 2 7. . _ ; .c. O !** 3 1, 2

8. Overpower al 6, Four Loop Operation 4 2 3 1, 2

! ;.. L .., 0 .7 . . t . .. . 4 l'* 3 ;,. .,

9. Pressurizer Pressure-Low 4 2 3 1, 2 6

10. Pressurizer Pressure--HIOh 4 2 3 1, 2 6

11. Pressurizer Water Level--liigh 3 2 2 1, 2 7

TABLE 3.3-3 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION 8

5

MINIHilM TOTAL NO. CilANNELS CllANNELS APPLICABLE 0F CIIANNELS TO TRIP OPERAllLE MODES ACil0N E FUNCTIONAL UNil "4

na 1. SAFETY INJECTION, TURBINE TRIP AND FEEDWA1ER ISOLATION 2 1,2,3,4 20

a. Manual Initiation 2 1

b. Automatic Actuation 2 1 2 1,2,3,4 15 Logic 2 2 1, 2, 3 16*

c. Containment 3 u, Pressure-High A 2 1, 2, 2# 16*

u, d. Pressurizer 3 2

4 u

Pressure - Low

e. Differential 1, 2, 3 Pressure Between Steam Lines - High Four Loops 3/ steam line 2/ steam line 2/ steam line 16*

Operating any steam line i... , _ , _ , , r .. __.1 i # # #i . . .. _ er_.__..:_.. i, L';U Y5 tI[ E*'55E*_" ':

E, [t[$EI-ES"

_ , a: ;it.

l

7 IABLE 3.3-3 (Continue @

m pg ENGINEERED SAFETY IEATURE ACillA110N SY51[M INSTRliMENTATION C

c2 g HINIMUM I TOTAL NO. CHANNELS CHANNELS APPLICABLE

OF CHANNELS TO IRIP OPERABLE H0 DES ACTION FUNCTIONAL UNIT C ##

z 1, 2, 3

q f. Steam Flow in Two Steam Lines-liigh Four Loops 2/ steam line 1/ steam line 1/ steam line 16*

Operating any 2 steam lines

,,4 ### r.,m.,, i s iv vi

__ i_ .y7 7 4 / m. , , i f . _;. i

..>.i.,. ii y .i:

n;- s.. __

.m

_ e. 3. i ;

ste2- . . _

w

's COINCIDENT Willt EITHER ##

T --Low-tow 1, 2, 3 av9 ,

,i' 16*

ai Four Loops 1T avg / loop 2I avg any 1T avgany Operating loops 3 loops ri . , _ _ . , iy i i ###r _ i1 ,_ _ _ . ,,

1A101, ; ,,,, . . Id XU . m + I2'm n, ;>,.7~ mmi3Y9imm >m,

,- ,, i ,. , .,

'-v- a r OR, COINCIDENT Willi ##

Steam Line Pressure-Low I , 2, 3 Four Loops 1 pressure / 2 pressures 1 pressure 16*

Operating 1.oop any loops any 3 loops n - . , 88# ,.m_ _

.__r. i. r_...

? _

r....... .

r_

7 . . . .

e ns, ,, s e i _i __ -

1

"J 6

, , , , - - , r-'

'^

Yr - -

T " ' -

1 u,

TABLE 3. 3-3 (Continueil) j! ENGINEERED SAFETY FFATURE ACIUATION SYSTEM INSlRUMENTATION

'S

> MINIMUM

APPLICABLE TOTAL NO. CllANNELS CilANNELS FUNCTIONAL UNIl 0F CilANNEls 10 TRIP OPEl!ABLE MODES ACTION

[.

z El c. Containment Ventilation -

ea Isolation I) Maniua l 2 1 2 1,2,3,4 19

2) Automatic Isolation 2 1 2 1,2,3,4 IS Logic

3) Containment Gas 2 1 1 1,2,3,4 19 Monitor Radioactivity-High

4) Containment Purge 2 1 1 1,2,3,4 19 ce Air Exhaust Moniitor 22 Radioac t ivi ty-liigh i' 5) Containment Particu- 2 I I I, 2,.3, 4 19 E$ late Activity liigh

4. STEAM LINE ISOLAIION

a. Manual 1/ steam line 1/ steam line 1/ operating 1, 2, 3 25 steam line '-

b. Automatic 2 1 2 1,2,3 23 Actuation Logic

c. Containment Pressure-- 4 2 3 1,2,3 18 liigh-liigh

d. Steam fluw in Iwo 1, 2, 3 Steam Lines--liigh Four Loops 2/ steam line 1/ steam line 1/ steam line 16*

Operating any 2 steam lines vm . ,____ e r _ . . . . r ., . i f ## , _ _. . i,

'. Z.'Ti'"" ,,...___.[,r.._

',ZTI C" n.

._..i.._'

_ _ _'li'. . ,

I AllLE 3.3-3 (Continuedl

)b ENGINEERED SAFETY IEATtlRE ACTUATION SYSILM INSlRtlHENTATION 8

Y

HINIMUM

TOTAL NO. CllANNELS CilANNELS - APPLICABLE OPERABLE MODES ACTION OF CllANNELS TO TRIP E FUNCTIONAL UNIT G

na COINCIDENT Willt EITilER 1, 2, 3 T --Low-Low 16"

- U Four Loops 1T avg / loop 2T any iT any ygggvg 3jgggg Operating

.,,s '".

. . . h. T. .T" 3

.! . !. a...3y

..., .r ..._'"avo .. --u f ava

, (. ". ,', '

?__,.

-- u u, OR, COINCIDENI WITil 1, 2, 3 3: Steam Line Pressure-

' u, Low -

'. 16*

"' Four Loops I pressure / 2 pressures I pressure Operating loop any loops any 3 loops

'### p-err"rc '

prerr_r #-

" ~r- !^^pr i precru r/

^; _ r c i ! . . , cper ting ! rep : 2ny r;cr- 2ny 2 ;:r-ci L., ' r :, 2*' ; !repr

5. TURBINE TRIP &

FEEDWA1ER ISOLATION 3/ loop' 2/ loop in '2/ loop in I , 2, 3 16*

a. Steam Generator Water Level-- any oper- each oper-ating loop ating loop liigh-liigh

ENCLOSURE 2 JUSTIFICATION FOR PROPO3ED CHANGE IN TECHNICAL SPECIFICATIONS FOR UNITS 1 AND 2 SEQUOYAH NUCLEAR PLANT (TVA SQN TS 64)

This proposed change deletes all the references to three-loop power operations. When the technical specifications were originally issued to TVA, NRC left in place all the references to three-loop operation. TVA has no plans to pursue approval of the three-loop operation at Sequoyah.

Additionally, this change is being requested to eliminate the possibility of these technical specification requirements being inappropriately applied, resulting in an NRC violation. This change is administrative in nature and as documented in the attached significant hazards consideration detenmination, no significant hazards considerations are involved.

i

_.a

6.

SIGNIFICANT HAZARDS CONSIDERATIONS

1. Is the probability of an occurrence or the consequences of an accident previously evaluated in the safety analysis report significantly-

. increased?

No. This change is administrative only and removes unused and unnecessary information from the technical specifications.

2. Is the possibility for an accident of a new or different type than evaluated previously in the safety analysis report created?

No. See number 1 above.

3. Is the margin of safety significantly reduced?

No. See number 1 above.

.

ML20128E578

Text

Navigation menu

Search