ML18096A742

Proposed TS 3/4.1.1 Re Boration Control Shutdown Margin, Table 3.3-4 Re ESFAS Instrumentation Trip Setpoints & Table 3.3-5 Re ESF Response Times

ML18096A742
Person / Time
Site:	Salem
Issue date:	05/26/1992
From:	Public Service Enterprise Group
To:
Shared Package
ML18096A741	List: ML18096A740 ML18096A742
References
NUDOCS 9206010259
Download: ML18096A742 (13)

Text

(

I 3/4.1 REACTIVITY CONTROL SYSTE~S 3/4.1.1 BORATION CCNT~O(

SHUTDOWN MARGIN - Tavg > 2oo*F LIMITING CONDITION FOR OPERATION Mr/~

3.1.1.1 The SHUTDOWN MARGIN shall be!. 1.61 Ak/k.

APPLICABILITY:

MODES 1., a*. 3, and 4.

ACTION:

tVJ{~

With the SHUTDOWN MARG!N < 1.61 Ak/k, i1T111ed1at1ly initiate and continue boration at> 10 gpm of 20,000 ppm boric: acid solution or equivalent until the required SHUTDOWN MARGIN is restored.

SURVEILLANCE REQUIREMENTS Md~

4. 1

• 1

• 1. 1 The SHUTDOWN MARG IN sha 11 be d1termi ned ta bl !. 1. 6~.:. I</~:

a.

Within one hour after detection of an inoperable control rod(s) and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ther11ft1r while the rod(s) is inoperable. If tht inoperable control rod is innovable or untrippable, tht above required SHUTDOWN MARGIN shall be increased by an amount at least equal ta the withdrawn wor-th of the i111novabl1 or untrippable control rod(s).

b.

When in MOOES 1 or 21, at 111st onct per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that control bank withdraw.1.is wHhin the limits of Specification 3.1.3.S.

c *. When in MOOE 21", within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to achieving reactor criticality by verifying that the predicted critical control rod position is.within the limits of specification 3.1.3.5.

See Special Test Exception 3.10. 1

. With "eff !. 1.a

With Keff < 1.0 SALEM

• UNIT 1 3/4 1-1 83 I

~A:_?e~ '~ 7 r;,~;~fo 1~~e ' I~ o.J i()(t(/(

Qll ly.

REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

d.

Prior to initial operation above S~ RATED THERMAL POWER after each fuel loading, by consideration of the factors of e below, with the control banks at the maximum insertion limit of Specification 3.1.3.5.

e.

When in MODES 3 or 4, at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by consideration of the following factors:

1.

Reactor coolant system boron concentration,

2.

Control rod position,

3.

Reactor coolant system average temperature,

4.

Fuel burnup based on gross thermal energy generation,

5.

Xenon concentration, and

6.

Samarium concentration.

4.1. l. l.2 The overal 1. core reactivity balance shall be compared to oredicted values to demonstrate agreement ~ithin + l~ 1k/k at least once per 31 Effective Full Power Days (EFPO).

This comparison shall consider at least those factors stated in Specification 4.1.1.1.1.e, above.

ihe predicted reactivity values shall be adjusted (normalized) to corre-scond to the actual core conditions prior to exceeding a fuel burnup of SO Effective Full Power Days after each fuel loading.

SALEM

• UNIT 1 3/ 4 1-2

c z.....

-I w

I N

~

TABLE 3.3-4 (Continued\\

ENGINEERED SAFETY FEATURE ACTUATION SYStEH 1

~NSTRUHENTATION TRIP SETPOINTS

-- --------------4-..-a..~~~=

FUNCTIO"AL UNIT

2.

CONTAINMENT SPRAY

a.

Manual Initiation

b.

Autollilttc Actuatton Logic

c.

Containment Pressure--tttgh-Htgh

. 3.

CONTAINMENT ISOLATION

1.

Manual

2.

From Safety Injection Automatic Actuation logic

b.

Phase NON Isolation.

1.

Hanua 1

2.

Automatic Actuation logic

l. -Containment Pressure--High-High

c.

Containment Ventilation Isolation

l.

Manual TRIP SETPOJNT

~

Not Appltcable Not. ~ppl tcable

< a-: ps 1 g Not Appltcable Not Appl kable Not Applicable Not Applicable

~ ~

psig

@V Not Applicable ALLOWABLE VALUES Not Appltcable Not Applicable

<ff pstg Not Appl tcable Not Appl tcable Not Appltcable Not Applicable

~ ~pstg

<f£D Not Appl tcable e

e

~

H toil...

w w

I N

I r g=....

N...

IAILE J.]*4 CContlnytd)

EIGllEEBEp SAFETY FEATURE ACIUAIIOI IVIIEI lllTIUIEITAllOI JllP SETPOllTI fMICllRIAL Miii Z.

Cont1ln*1nt At*oeph1re G1e1ou1 l1dte1ctlvlty

4.

IIEAI Liii llOLAllOI l1nu1l

b.

Auto*ttl~ Actu1tlon Lo1lc

c.

Cont1ln*1nt Pr11eur1**ll1h*ll1h

4.

It*** Flow In lMO It*** Lin****

ll1h Coincident Mith I1v1 ** LoM*loM or It*** line rr1eeur1 ** loM Illr lllPOIU

,,, Itbh J.J-6 lot Appl lc1ble lot Appl lctbh

!. ~p1l1

~

!_ a* funct loo defined **

foll0Me1 A AP corr1epondln1 to 401 of full *t*** flow b1tw11n 01 1nd ZOI lo1d ind then* AP lncr111ln1 lln11rly to

• AP corr1epondln1 to 1101 of full *t*** floM 1t fut l lotd.

l1v1 ?.. UJ*f

?.. 600 p1l1 *t*** line pr111ur1 ALLOMAllE YALUEI lot Appl I c1bh lot Appllc1bl1

!.~**

~~ct Ion defined **

folloM1:

A 4p correepondln1 to 441 of full ate** flow b1tM11n 01 ind 201 lo1d ind then

• 4p lncre1eln1 llne1rlv to

• 4p correepondln1 to 111.51 of full 1te1* flow et full lo1d.

,,.,, ?.. 541*1

?.. 579 pel1 ate** line pr1eeur1 e

Add:

TABLE 3.3-5 ENGINEERED SAFETY FEATURES RESPONSE ITEMS INITIATING SIGNAL AND FUNCTION

l.

Manual

a.

Safety Injection (ECCS)

Feedwater I*olation Reactor Trip (SI) containment I*olation-Pha*e "A" Containment Ventilation Isolation Auxiliary Feedwater Pumps Service Water Sy*tem Containment Fan Cooler

b.

containment Spray Containment !*elation-Ph&** "B" Containment Ventilation Isolation

c.

Containment Isolation-Ph&** "A" Containment Ventilation Isolation

d.

Steam Lin* I*olation

2.

containment Pr***ure-High

a.

Safety Injection (ECCS)

b.

Reactor Trip (from SI) c *.

reedwater I*olation

d.

containment I*olation-Pha** "A" containment Ventilation I*olation

f.

Auxiliary Feedwater Pump*

9*

Service Water Sy*t*m Con+.. :,,,,,~,,+.&;" U.krs SALEM -

t:NIT l

- 3/4 3-2"'

RESPONSE TIME IN SECONDS Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applical:lle Not Applicable Not Applical:lle Not applicable Not Applicable Not Applicable Not Applical:lle

~27.0(l)

~2.0

~10.0

$17.0(2)/27.0(3)

Not Applical:ll*

$60

~~

$13.0(2)/

• (3)

Amen~nt No. 132

TABLE J.3-5 IContir.ued)

ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION

3.

Pressurizer;: P;:es !1!.U:!!-Low

a.

Safety Injection (ECCS)

b.

Re-actor Trip (from SI)

c.

Feedwater I*olation

d.

Containment holation - Pha*e "A"

e.

Containment Ventilation I*olation

f.

Auxiliary Feedwater Pump*

9*

Service Water Sy*t*m RESPONSE TIM!! IN SECONps s 21.0< 1 >112.0 12 l s 2.0 s 10.0

$ 18. 0 ( 2 )

Not Applicable

$ 60

$ 49.0< 1 >113.0< 2>

4.

Differential Pr***ure Between Steam Line*-Hiqh Safety Injection (ECCS)

$ 12.0<2 >122.0< 3>

b.

Reactor Trip (from SI)

$ 2.0

c.

Feedwater I*olation s 10.0

d.

containment I*olation - Pha*e "A"

$ 17.0<2 >121.0< 3 >

Containment Ventilation I*olation Not Applicable

f.

Auxiliary Feedwater Pump*

s 60 9*

Service Water Sy*t*m s 13.0<2 >/48.0< 3>

S.

Steam Flow in Two St*1111 Lin** - High Coincident with Tavq -- Low-Low

a.

Safety Injection (ECCS) s 15.75<2>;25.75< 3>

b.

Reactor Trip (from SI) s 5.75

c.

Feedwater I*olation s 15.0

d.

containment I*olation - Pha*e *A*

s 20.15< 2 >;30.15< 3>

containment Ventilation I*olation

• • Applicable

f.

Auxiliary Peedwater Pwnp*

s 61.75

q.

Service Water Sy*tem

$ 15.75<2 >;50.15< 3 >

b.

Steam Line I*olation

$ 10.75

~13.75 until r**tart following th* tenth refueling outage.

SALEM - UNIT 1 3/4 3-28 Amendeent No.132

TABLE 3.3-5 (Con~;nuectL ENGINE!RED SAFETY FEATURES RESPONSE TIMJ:S INITIATING SIGNAL ANO FUNCTION

6.

Steam Flow in Iwo Steam Lines-High Coincident with Steam Line Pres1ure-Low

a.

Safety Injection (ECCS)

b.

Reactor Trip (from SI)

c.

Feedwater Isolation

d.

Containment I1olation-Pha1e "A"

e.

Containment Ventilation I1olation

f.

Auxiliary Feedwat*r Pump*

S1rvic1 Wat1r Sy1tem

h.

St*&m Line I1olation

7.

Containrn*nt pre11yre--High-High

a.

Containment Spray

b.

Containmtnt Iaolation-Pha** "&*

c.

St*&m Line Iaolation

~.

8.

Stttm G1n1rat9r Wattr Level--High High

b.

Turbine Trip reedwater Iaolation

9.

sieam 99n1r1tor W1t1r L1v1l--L9w-Lgw Motor-Driven Auxiliary Ftedwater Pwnp*(4)

b.

Turbine-Driven Auxiliary reedwater Pwnp*(S)

RESPONSE TI!q IN SECONDS

$ 12.0( 2 ) /22.o( 3 l s 2.0

$ 10.0

$ l7.0< 21 ;21.0< 3 l Not Applicablt 60

$ l4.0< 2 >;4a.0< 3 l

$ a.o Not Applic&Dlt

$ 7.0

~ 49,9

$ 2.5

$ 10.0

$ 60.0

$ 60.0

$10.0 aecond* until r1atart following the tenth refueling out191.

SAI.EH -

UNIT l 3/4 3-29 Amen~nt ?lo. 132 I

A-Jd.'

3/4. 1 REACTIVITY CONTROL SYSTEMS 3/4. 1. 1 BORATION CONTROL SHUTDOWN MARGIN - Tavg > 200°F LIMITING CONDITION FOR OPERATION At/d.* ~

3. 1. 1. 1 The SHUTDOWN MARGIN shall be greater than or equal to 1.6% delta k/K.

APPLICABILITY:

MODES 1, 2~, 3, and 4.

ACTION:

A:rlt/: ~

\\:/!;5:./

With the SHUTDOWN MARGIN less than 1.6% delta k/k, immediately initiate and continue boration at greater than or equal to 10 gpm of a solution containing greater than or equal to 20,000 ppm boron or equivalent until the required SHUTDOWN MARGIN is restored.

SURVEILLANCE REQUIREMENTS

4. 1. 1. 1. 1 The SH~~ MARGIN shall be determined to be greater than or equal to 1. 6% delta k/k *

a.

b.

c.

Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after detection of an inoperable control rod(s) and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter while the rod(s) is inoperable.

If the inoperable control rod is i11111ovable or untrippable, the above required SHUTDOWN MARGIN shall be increased by an amount at least equal to the withdrawn worth of the immovable or untrippable control rod(s).

When in MODE l or MODE 2 with K greater than or equal to 1.0, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by veri?~f ng that control bank withdrawal is within the limits of Specification 3. 1.3.5.

When in MODE 2 with K less than 1.0, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to achieving reactor cri!ftality by verifying that the predicted criti-cal control rod position is within the limits of Specification 3.1.3.5.

• See Special Test Exception 3. 10. 1 SALEM - UNIT 2 3/4 1-1

REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

d.

Prior to initial operation above ~ RATED THERMAL POWER after each fuel loading, by consideration of the factors of e below, with the control banks at the maximum insertion limit of Specification 3. 1.3.5.

e.

Whan in MODES 3 or 4, at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by consideration of the following factors:

1.

Reactor coolant system boron concentration,

2.

Control rod position,

3.

Reactor coolant systetll average temperature,

4.

Fuel burnup based on gross therllljll energy generation,

5.

Xenon concentration, and

6.

SamariUll concentration~

4. 1. l. 1.2 Th* overall core reactivity balance shall be compared to predicted values to d1110nstrate agreement within : lS delta k/k at least once per 31 Effective Full Power Days (EFPO).

This comparison shall consider at least those factors stated in Specificativn 4. 1. 1. 1. l.e, above.

The predicted reactivity values shall b* adjusted (normalized) to correspond to the actual core conditions prior to exceeding a fuel burnup of 60 Effective Full Power Days after each fuel loading.

SALEM - UNIT 2 3/4 l-2

~

TABLE 3.3-4 (Continued) r-

!R ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTllltENTATION TRIP SETPOINTS c:

z FUNCTIONAL UNIT TRIP SETPOINT ALlflMBLE VALUES

~

N

2.

CONTAllllENT SPllAY e

a.

Manual Initiation Not Applicable Not Applicable

b.

Aut.atlc Actuation logic Not Appllcable Not Appllcabl*

c.

Contal1111ent Pre&&ure--Htgh-Hlgh

~@*ta

~**

3.

CONTAINMENT ISOLATION

/5:0 lb.O Phase *A* Isolation w

1.

Manual Not Applicable Not Applicable w

• N

2.

frc111 Safety Injection Not Appllcabl*

Not Applicable Auto.atlc Actuation logic

b.

Plaas* *a* l&olatlon e

1.

lllnual Not Appltcabl*

llot Appl tcabl*

2.

Auto.atlc Actuation logic llot Applicable Not. Appllcele

3.

Contal.-nt Pn11un--Htgb-Hlgb

~~p*ta

~**

c.

Contal1111ent Ventilation l&olatton 15".0 16.0

1.

Manual Not Applicable Not Appltuble

2.

Aut~ttc Actualton Logtc Nol Appl tcabl*

Not Applicable

w

~

w I tJ OI i

I i

=-rt if. -

C> -

IAILE ],J-4 <<Continued>

ENGINEEREp SAFEI! fEAIURE ACTUATION SJSIEM INSJBUMEITATIOI TRIP SETPOllTS FUICllOIAL VIII

2.

Cootaln*ent At*o*phere Ge5eou1 ladloectlvlty

4.

STEAM i11E llOLAllOI Manual

b.

Auto*atlc Actuation Lo1lc

c.

Conteln**nt Preaeure*-ll9h-Ml1h

d.

St*** Flow In Two St*** Linea--

11th Coincident with Tev1 *-

low-Low or St*** Line Preeeure --

low IllP HTPOIU ALLOHAILE VALUES Per Table J.J-6 llot Appl I ubh llot Applicable

.!. ~J-' *11 1S:o

.!. A unction defined **

followe:

A 4P correepondln1 to 401 of full *te** flow between 01 and 201 load and then* 4P lncreeeln1 llneerly to

• AP correepondlo1 to 1101 of full *t*** flow et full load.

I *v1 ?.. 54J*t

?.. 600 p*l1 *t*** line preaeure llot Applicable llot Applicable

.!. ~***

~

.!. A iunctlon defined **

followa:

A 4P correapondlng to 441 of full ate** flow between 01 end 201 lo*d *nd then* ~p lncre*alng llneerly to

• 4p correapondlng to 111.51 of full ate** flow et full loed.

T ev1 ?.. 54PF

?.. 579 pelt *t*** line preeaure

w TA3!'...E J. J-5 ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL ANO FUNCTION

1.

Manual

2.

a.

Safety Injection (ECCS)

Feedwater I*olation Reactor Trip (SI)

Containment Isolation-Phase "A" Containment Ventilation Isolation Auxiliary Feedwater Pumpa Service Water Sy*tem Containment Fan Cooler

b.

Containment Spray Containment Isolation-Phase "B" Containment Ventilation I*olation

c.

Containment I*olation-Phase "A" Containment Ventilation I*olation

d.

Steam Lin* I*olation Containm1nt Pr***ure-High

a.

Saf1ty Injection (ECCS)

b.

R1actor Trip (from SI)

c.

F11dwat1r I*olation

d.

Containment I*olation-Pha** "A" containment Ventilation I*olation t*.

Awciliary reedwater Pump*

9*

service Water Sy*t*m U,,,fb.; 11111 e,,+ J:;.,.

Cao/er~

SALD -

UNIT 2 3/4 3-28 RESPONSE TIME IN SECONDS Not Applic&Dle Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicabl1 Not Applicable Not Applicable Not Applicable Not applicable Not Applicable Not Applicable Not Applicable

~ 21.0< 1 >

$ 2.0

~ 10.0

~ 17.0< 2 > /27.0( 3 )

Not Applica))le

~ 60 q5.'g) d 13.0< 2 > /4&re(l)

£:, 'tS:O 1 Amend.::11nt No. 111

~

e

~ABLE 3.3-5 rcontinuedl ENGIN!!REC SAFETY FEATUBES RESPONSE TIMES INITIATING SIGNl\\,L ANQ FUNCTION

6.

Steam Flow in Two Steam Lines-High Coincident with Steam Line Pressure-~ow

7.

a.

Safety Injection (ECCS)

b.

Reactor Trip (from SI)

c.

Feedwater Isolation

d.

Containment Isolation-Phase "A"

e.

Containment Ventilation I*olation

f.

Auxiliary Feedwater Pump*

9.

Service Water Sy*tem

h.

Steam Line Isolation Containment Pre**ure--High-Hiah

a.

Containment Spray

b.

Containment I*clation-Pha*e "B"

c.

Steam Line I*olation 4

CoRcaLnnieR& F*R Cool**

s.

Steam Generator Water tevel--High-Hiqb

b.

Turbine Trip Feedwater I*clation

9.

Steam Generator Water Level --Low-Low

a.

b.

Motor-Driven Auxiliary Feedwater Pump*(~)

Turbine-Driven Auxiliary Feedwater Pumpe(S)

RESPONSE TIM!! IN SECONDS s 12.0 12 >;22.01 3>

s 2.0 s 10.0 s 17.0< 2 >;21.0< 3 >

Net Applicable s 60 s 14.0< 2 >;4s.0< 3 >

s 8.0*

Gfi.o) s~

Not Applicable s 7.0*

40.0 s 2.5 s 10.0 s 60.0 s

60~0

$10.0 eecond* until re*tart followin9 the *ixth refuelin9 outage.

SAI.&H -

UNIT 2 3/4 3-30 Amendment No. 111 I