ML18096A742

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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  PSEG icon.png
Issue date: 05/26/1992
From:
Public Service Enterprise Group
To:
Shared Package
ML18096A741 List:
References
NUDOCS 9206010259
Download: ML18096A742 (13)
v • d • e


Text

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is innovable or untrippable, tht above required SHUTDOWN MARGIN shall be increased by an amount at least equal ta the withdrawn wor-th of the i111novabl1 or untrippable control rod(s).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

(

I

~A:_?e~

1~~e '

'~ 7 I~ o.J i()(t(/(

r;,~;~fo 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

TABLE 3.3-4 (Continued\

ACTUATION SYStEH ~NSTRUHENTATION TRIP SETPOINTS 1

ENGINEERED SAFETY--FEATURE

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

c ALLOWABLE VALUES z

-I FUNCTIO"AL UNIT TRIP SETPOJNT

. ~

2. CONTAINMENT SPRAY
a. Manual Initiation Not Appltcable Not Appltcable e
b. Autollilttc Actuatton Logic Not. ~ppl tcable Not Applicable
c. Containment Pressure--tttgh-Htgh a-: ps 1g <ff pstg

. 3. CONTAINMENT ISOLATION w

N I

1. Manual Not Appltcable Not Appl tcable

~

2. From Safety Injection Not Appl kable Not Appl tcable Automatic Actuation logic
b. Phase NON Isolation .
1. Hanua 1 Not Applicable Not Appltcable
2. Automatic Actuation logic Not Applicable Not Applicable
l. -Containment Pressure--High-High ~ ~ psig ~ ~pstg
c. Containment Ventilation Isolation

@V <f£D

l. Manual Not Applicable Not Appl tcable

e IAILE J.]*4 CContlnytd)

H

~

toil

... fMICllRIAL Miii EIGllEEBEp SAFETY FEATURE ACIUAIIOI IVIIEI lllTIUIEITAllOI JllP SETPOllTI Illr lllPOIU ALLOMAllE YALUEI Z. Cont1ln*1nt At*oeph1re

, , , Itbh J.J-6 G1e1ou1 l1dte1ctlvlty

4. IIEAI Liii llOLAllOI
  • . l1nu1l
b. Auto*ttl~ Actu1tlon Lo1lc lot Appl lc1ble lot Appl lctbh lot Appl I c1bh e

w w

c. Cont1ln*1nt Pr11eur1**ll1h*ll1h  !. ~p1l1 lot Appllc1bl1

!.~**

I ~

4. It*** Flow In lMO It*** Lin**** a* funct loo defined ** ~~ct Ion N

!_ defined **

"' ll1h Coincident Mith foll0Me1 A AP corr1epondln1 folloM1: A 4p correepondln1 I1v1 ** LoM*loM or to 401 of full *t*** flow to 441 of full ate** flow It*** line rr1eeur1 ** loM b1tw11n 01 1nd ZOI lo1d ind b1tM11n 01 ind 201 lo1d ind then* AP lncr111ln1 lln11rly then

  • 4p lncre1eln1 llne1rlv to
  • AP corr1epondln1 to to
  • 4p correepondln1 to 1101 of full *t*** floM 1t 111.51 of full 1te1* flow et fut l lotd. full lo1d.

I l1v1 ?.. UJ*f

?.. 600 p1l1 *t*** line pr111ur1

,,.,, ?.. 541*1

?.. 579 pel1 ate** line pr1eeur1

..r

.g=

N

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

l. Manual
a. Safety Injection (ECCS) Not Applicable Feedwater I*olation Not Applicable Reactor Trip (SI) Not Applicable containment I*olation-Pha*e "A" Not Applicable Containment Ventilation Isolation Not Applicable Auxiliary Feedwater Pumps Not Applicable Service Water Sy*tem Not Applicable Containment Fan Cooler Not Applical:lle
b. containment Spray Not Applicable Containment !*elation-Ph&** "B" Not Applical:lle Containment Ventilation Isolation Not applicable
c. Containment Isolation-Ph&** "A" Not Applicable Containment Ventilation Isolation Not Applicable
d. Steam Lin* I*olation Not Applical:lle
2. containment Pr***ure-High
a. Safety Injection (ECCS) ~27.0(l)
b. Reactor Trip (from SI) ~2.0 c *. reedwater I*olation ., ~10.0
d. containment I*olation-Pha** "A" $17.0(2)/27.0(3)
    • containment Ventilation I*olation Not Applical:ll*
f. Auxiliary Feedwater Pump*

$60 ~~

9* Service Water Sy*t*m $13.0(2)/ * (3)

Add: , ,, . Con+..:,,,,,~,,+ .&;" U.krs SALEM - t:NIT l - 3/4 3-2"' Amen~nt No. 132

TABLE J.3-5 IContir.ued)

ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIM!! IN SECONps

3. Pressurizer;: P;:es !1!.U:!!-Low
a. Safety Injection (ECCS) s 21.0< 1 >112.0 12 l
b. Re-actor Trip (from SI) s 2.0
c. Feedwater I*olation s 10.0
d. Containment holation - Pha*e "A" $ 18. 0 ( 2 )
e. Containment Ventilation I*olation Not Applicable
f. Auxiliary Feedwater Pump* $ 60 9* Service Water Sy*t*m $ 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 RESPONSE TI!q IN SECONDS

6. Steam Flow in Iwo Steam Lines-High Coincident with Steam Line Pres1ure-Low
a. Safety Injection (ECCS) $ 12.0( 2 ) /22.o( 3 l
b. Reactor Trip (from SI) s 2.0
c. Feedwater Isolation $ 10.0
d. Containment I1olation-Pha1e "A" $ l7.0< 21 ;21.0< 3 l
e. Containment Ventilation I1olation Not Applicablt
f. Auxiliary Feedwat*r Pump* $ 60
. S1rvic1 Wat1r Sy1tem $ l4.0< 2 >;4a.0< 3 l
h. St*&m Line I1olation $ a.o *
7. Containrn*nt pre11yre--High-High
a. Containment Spray
b. Containmtnt Iaolation-Pha** "&* Not Applic&Dlt
c. St*&m Line Iaolation $ 7.0 *

~. ~ 49,9

8. Stttm G1n1rat9r Wattr Level--High High
b. reedwater Iaolation $ 10.0
9. sieam 99n1r1tor W1t1r L1v1l--L9w-Lgw
    • Motor-Driven Auxiliary Ftedwater .,

Pwnp*(4) $ 60.0

b. Turbine-Driven Auxiliary reedwater Pwnp*(S) $ 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

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. 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).

b. 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.
c. 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 A-Jd.'

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

.... TRIP SETPOINT ALlflMBLE VALUES

~

FUNCTIONAL UNIT N

2. CONTAllllENT SPllAY
a. Manual Initiation Not Applicable Not Applicable e
b. Aut.atlc Actuation logic Not Appllcable Not Appllcabl*
c. Contal1111ent Pre&&ure--Htgh-Hlgh ~@*ta
3. CONTAINMENT ISOLATION /5:0 ~**

lb.O w ** Phase *A* Isolation

  • w
1. Manual Not Applicable Not Applicable 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 16.0
c. .

Contal1111ent Ventilation l&olatton 15".0

1. Manual Not Applicable Not Appltuble
2. Aut~ttc Actualton Logtc Nol Appl tcabl* Not Applicable

IAILE ],J-4 <<Continued>

ENGINEEREp SAFEI! fEAIURE ACTUATION SJSIEM INSJBUMEITATIOI TRIP SETPOllTS FUICllOIAL VIII IllP HTPOIU ALLOHAILE VALUES

2. Cootaln*ent At*o*phere Per Table J.J-6 Ge5eou1 ladloectlvlty
4. STEAM i11E llOLAllOI
    • Manual llot Appl I ubh llot Applicable
b. Auto*atlc Actuation Lo1lc llot Applicable llot Applicable
c. Conteln**nt Preaeure*-ll9h-Ml1h

~J-' *11

~***

1S:o w d. St*** Flow In Two St*** Linea-- .!. A unction defined **

~

....... 11th Coincident with .!. A iunctlon defined **

~ followe: A 4P correepondln1 followa: A 4P correapondlng w Tev1 *- low-Low or to 401 of full *te** flow I to 441 of full ate** flow tJ St*** Line Preeeure -- low between 01 and 201 load and OI between 01 end 201 lo*d *nd then* 4P lncreeeln1 llneerly then* ~p lncre*alng llneerly to

  • AP correepondlo1 to to
  • 4p correapondlng to 1101 of full *t*** flow et 111.51 of full ate** flow et full load. full loed.

I *v1 ?.. 54J*t T ev1 ?.. 54PF

?.. 600 p*l1 *t*** line  ?.. 579 pelt *t*** line preaeure preeaure i::I i=-

rt

.if

.C>

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

1. Manual
a. Safety Injection (ECCS) Not Applic&Dle Feedwater I*olation Not Applicable Reactor Trip (SI) Not Applicable Containment Isolation-Phase "A" Not Applicable Containment Ventilation Isolation Not Applicable Auxiliary Feedwater Pumpa Not Applicable Service Water Sy*tem Not Applicabl1 Containment Fan Cooler Not Applicable
b. Containment Spray Not Applicable Containment Isolation-Phase "B" Not Applicable Containment Ventilation I*olation Not applicable
c. Containment I*olation-Phase "A" Not Applicable Containment Ventilation I*olation Not Applicable
d. Steam Lin* I*olation Not Applicable
2. Containm1nt Pr***ure-High
a. Saf1ty Injection (ECCS) ~ 21.0< 1 >
b. R1actor Trip (from SI) $ 2.0
c. F11dwat1r I*olation ~ 10.0
d. Containment I*olation-Pha** "A" ~ 17.0< 2 >/27.0( 3 )
    • containment Ventilation I*olation Not Applica))le t*. Awciliary reedwater Pump* ~ 60 q5.'g) 9* service Water Sy*t*m d 13.0< 2 > /4&re(l)

U,,,fb.;11111 e,,+ J:;.,. Cao/er~

1

'". £:, 'tS:O SALD - UNIT 2 3/4 3-28 Amend.::11nt No. 111

.., ,..,. ~

  • ~ABLE e

3.3-5 rcontinuedl ENGIN!!REC SAFETY FEATUBES RESPONSE TIMES INITIATING SIGNl\,L ANQ FUNCTION RESPONSE TIM!! IN SECONDS

6. Steam Flow in Two Steam Lines-High Coincident with Steam Line Pressure-~ow
a. Safety Injection (ECCS) s 12.0 12 >;22.01 3 >
b. Reactor Trip (from SI) s 2.0
c. Feedwater Isolation s 10.0
d. Containment Isolation-Phase "A" s 17.0< 2 >;21.0< 3 >
e. Containment Ventilation I*olation Net Applicable
f. Auxiliary Feedwater Pump* s 60
9. Service Water Sy*tem s 14.0< 2 >;4s.0< 3 >
h. Steam Line Isolation s 8.0*
7. Containment Pre**ure--High-Hiah
a. Containment Spray Gfi.o) s~
b. Containment I*clation-Pha*e "B" Not Applicable
c. Steam Line I*olation s 7.0*

4 CoRcaLnnieR& F*R Cool**

' 40.0

s. Steam Generator Water tevel--High-Hiqb
b. Feedwater I*clation s 10.0
9. Steam Generator Water Level --Low-Low
a. Motor-Driven Auxiliary Feedwater s 60.0 Pump*(~)
b. Turbine-Driven Auxiliary Feedwater Pumpe(S) .,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

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