Text

Proposed Tech Specs Revising Surveillance Requirement 4.7.1.5 & Table 3.3-5
	ML18094B374
Person / Time
Site:	Salem
Issue date:	03/29/1990
From:	; Public Service Enterprise Group
To:	;
Shared Package
ML18094B373	List: ML18094B372; ML18094B374;
References
	NUDOCS 9004110216
	Download: ML18094B374 (8)
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(

TAB l£ 3.3-5 (Continued)

ENG INEERE 0 SAFETY FEAT~ES RESPONSE TIMES IN IT IAT ING SIGNAL AN 0 FUNCTION

3. Pressurizer Pressure-Low

a. Safety Injection (ECCS)

b. Reactor Trfp (from SI)

c. Feedwater Isolation

d. Containment Isolation-Phase *A*

e. Containment Ventilation Isolation

f. Auxiliary FeedWater Pu~s

g. Service Water System

4. Differential Pressure Between Steam Lfnes-Hig!!

a. Safety Injection (ECCS)

b. Reactor Trf p (from SI)

c. FeedWater Isolation

d. Contaf n.. nt Isolation-Phase *A*

e. Containment Yentflatf on Isolatfon

f. Au x11 ta*ry F eedwater Pu111>s

g. Service Water System

5. Steam F 1 ow 1 n two Steam L1 nes - Hf gh Cot net dent wfth Tavg --Low-low

a. Safety Injection (ECCS)

b. Reactor Trf p (from SI)

c. Feedifater Isolatf on

d. Contaf n111nt Iso1at1on.Phase *A*

e. Conta1nlleftt Yent111t1on Isolation

f. Aulrll1iFY FMdwiter. Pu111PS

g. S*n1 ~A! W1ter System ti. Steam Lf ne Iso 1at1 on SAWI *UNIT 1 3/4 3-28 RESPONSE TIME IN SECON CS

! 27.0(l)/12.0(2)

! 2.0

! 7.0

! 18.0(2)

Not App 11e1b1 e

< 60

-! 49.o(l)/13.o(2)

! 12.0(2)/22.0(3)

! 2.0

! 7.0

< 11.0(2)/27.0(3)

-Not Applf cable

< 60

-! 13.oC2)/48.oC3)

! 15.75(2)/25.75(3)

! 5.75

< 10.75

-! 20.75(2)/30.75(3)

Not Applicable

< 61.75

-( 15.75(2)/50.75(3)

-< l&.11

- ut75l Amendment No. 84

\\

e*

TAB LE 3.3-5 (Contf nued)

ENGINEERED SAFETY FEATIJlES RESPONSE TIMES INITIATING SIGHAL AND FUNCTION

6. Steam flow fn Two Stea* L1nes-tf19h Cof ncf dent wfth Steam lf n* Pressure-low

1. S1fety Injection (ECCS)

b. Re1ctor Trf p (frot1 SI)

c. Feedwater lsolatf on

d. Cont1f n11ent Isol1tf on.Ph1se *A*

- - Cont1f nment Ventf l1t~on Isol1tf on

f. Auxf lflry Feedwater Pu-.s

g. Service Water System

h. Stea* lf ne Isol1tfon

1. Cont11 rment Pressure-Hf gh-Hf gh

- Cont1inmnt Spray

b. Cont1f n11ent Isolation-Phase -a*

c. Stea* Ltne Isol1tf on

d. Contaf neent Fan Cooler

8. Stea* Generator Water level~isf!-Hi;h

1. Turbine Tr1p-

b. F1edw1ter Isolation

9. St1111 Generator Water Level-Law-Low

a. Motor-Driven Auxf ltar,y F1edlf1ter PUllps(4)

b. Turbine-Driven Aux1111ry FHdWater Pullps(5)

SA Wt

tlUT 1 3/4 3-29 RESPONSE TIME IN SECON CS

< 12.0(2)/22.0(3)

=

< 2.0

-< 7.0

-< 11.0(2)/27.0(3)

Not Applicable

< 60

-.! 14.0(2)/48.0(3)

< 8t:9~

10.0

! 45.0 Not 1ppl1c1ble

~ r.e-..-.izo.o J

< 40.0

< 2.5

-( u.o

( 60.0

< 60.. 0 Amendment No.

84 l

PLANT SYSTEMS MAIN STEAM LINE ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.7. l.S Each main steam line isolation valve shall be OPERABLE.

APPLICABILITY:

MODES 1, 2 and 3.

ACTION:

MODES l - With one main steam line isolation valve inoperable, POWER OPERATION may continue provided the.inoperable valve is either restored to OPERABLE status or closed within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; otherwise be in. HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

I ~morel r(S)l MODES 2 - With one ain steam line isolation valv'eifnoperable, subsequent and 3 operation in MODEe:Ef 2 or 3 ir.ay proceed provided; fi('A-PD

a.

The isolation valve is maintained closed.

b.

The provisions of Specification 3.0.4 are not applicable.

Otherwise, be in HOT SHUTDOWN within the next 12 houl"'S.

SURVEILL~NCE REOUIREMEN'iS 4.7.l.5 Each main steam line isolation valve shall be demonstrated OPERABLE by verifying full closure within ~seconds when tested pursuant to Specification 4.0.S.

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~e c..ye-leo/ ofB11 t:t.vid +/it?fl e=-6Ged dur-11:J fo1o{)E.

~ or '3 fo ve6ty OfER.A-8/L-IT'/.

SALEM-UNIT 1 3/c1 i-iO

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PUNT SYSTE"S BAS£S 3/4.7.1.4 ACi!Vm The limitatians on s~ondary systsn s;ecifie activit:t ensur9 that th* resultant off-sita rad1at1an dcsa wi11 be 1imited to a smali fraction of 10 CrR Part 100 limits fo the event of a staam line ru1:rtur9.

rnis dase also includes the effects of a eoincident 1.0 GPM primary to sac:ndar~

tuce leak in the steam generatar of ttle aff~-=d staa111 line. Thesa

, values a1'"1! consistent with t.ie assumptions used in t.,e ac:ident analysas.

3/4.7. t.S MAIN m~M LINE !SOL~T!OM VALi/ES The OP~SILI'if of the main staam line isolation valves ensul""'..s that no mar9 t.,an one staam generator will b1owdown in the event of a staam line l""JPtu". This rutrietion is requirtd to 1) minimi:a the positive reactivity effects of the Reac~r Coolant Syst!!ll eco1down associated with the b1owcto~n. and 2) limit t.ie ):)T"essul"9 rise within eonta irment in the event the stsm line rupture oc:curs within eonta in-ment.

The OPE.~BILITY o'f the main staam isolation valves *..-ithin t.,e e1o.sur9 times of the surveillancs r~uir~ents are ccnsistant with the assumptions usa! u 'i reel Cl.

~utv'e;/fa,,ce feGf +;,r yi.~f fa~ f e 1.(;,.r M 1'/lJ w!v~,, ;1-/J

/'/16;?&/Q f, tYl ~IV tna-y 6e c.ycleol mor-e flf'I 011~e/ dur,Y>~ ~

{Jer-For-#ltll>Cf' ~ (;urve:/la~cp re~/.;~ 1 lc)/f{ f{p un/f

/e"11a/ri/'1j P1oo£

~ or 1.,.

3 3/4 i-3

.~e..,C:nent ~lo. 2:

TABLE 3.3-5 (Continued)

ENGINEERED SAFETY FEATLRES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION

3. Pressurizer Pressure-Low
a. Safety Injection (ECCS)
b. Reactor Tr1p (from SI)
c. Feedwater Isolation
d. Containment Isolation.Phase *A*
e. Containment Yent11atton Isolation f e Aux111ary Feedwater Pu~s
g. Service Water System
4.
Dt ffererrtil1 Pressure Between Steam Lines-Hi~
a. Safety Injection (ECCS)
b. Reactor Trip (from SI)
c. Feedwater Isolation
d. Containment Isolation-Phase *A~
e. Containment Ventilation Isolation
f. AuxiliJry Feedwater Puq>s
g. Service Water System
5. Steam F 1 ow in two Steam L1 nes
Hf gh Cot ncf dent with Tivg --1.ow*Low
a. Safety Injection (ECCS)
b. Reactor Tr1p (from SI)
c. Feedwater Isolation
d. Contaf nMnt Isolation.Phase *A*
e. Contafn.. nt Ventf latfon Isolation
f. Aux1111ry FHdwat1r Pumps
g. Service Water System
h. Steam Lf ne Isolation SALEM
UNIT 2 3/4 3-29 RESPO~SE TIME IN SEC ON CS
< z1.0Cl)112.0(2) *
-! 2.0
.!. 7.0
! is.oC2.l Not Applicable
< 60
-! 49.0(l)/13.0(2)
< 12.0(2)/22.0(3}
! 2.0
! 7.0
! 17.0(2)/27.0(3)
Not Applf cable
<"60
-! 13.0(2)/48.0(3)
! 15.75(2)/25.75(3)
< 5.75
-! 10.75
! 20.75(2)/30.75(3)
Not Applicable
.! 61.75
! 15.7§(2)/50.75(3)
< [*t 1 13*75' Amendment No.
56
TABLE 3.3-5 (Continued)
ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION
6.
Steam Flow in Two Steam Lines-High Coincident with Steam Line Pressure-Low
a.
Safety Injection (ECCS)
b.
Reactor Trip (from SI)
c.
Feedwater Isolation
d.
Containment Isolation-Phase "A"
e.
Containment Ventilation Isolation
.f.
Auxiliary Feedwater Pumps
g.
Service Water System*
h.
Steam Line Isolation
7.
Containment Pressure--High-High
a.
Cont~inment Spray
b.
Containment Isolation-Phase 11011
c.. Steam Line Isolation
d.
Containment Fan *cooler
8.
Steam Generator Water Level--High-High
a.
-Turbine Trip
b.
Feedwater Isolation
9.
Steam Generator Water Level --Low-Low
a.
Motor-Driven Auxiliary Feedwater Pumps(4)
b.
Turbine-Driven Auxiliary Feedwater Pumps(S)
RESPONSE TIME IN SECONDS 1 12.0<2>122.o(J).
~ 2.0 s 7.0 s 17.0<2J121.0<3J Not App li cab 1 e
< 60
~ 14. 0<2> /48. 0<3).
~ &:1t~
~
~ 45.0 *.
Not Applicable s~~. I
~ 40.0 (lo.o
~ 2.5 s 11. a
a 60. 0
.~ 60.0 SALEM - UNIT 2 3/4-3-30
e PLANT SYSTEMS MAIN STEAM LINE ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.7.1.5 *Each main steam line isolatfon valve shall be OPERABLE.
APPLICABILITY:
MODES 1, 2 and 3.
ACTION:
MODES 1 - With one main steam line isolation valve inoperable, POWER OPERATION may continue provided the inoperable valve is either restored to OPERABLE status or closed within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; Otherwise, be in HOT SHUTDOWN within t~e next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .
~r mor!I llsJ]
MODES 2 - Wi'th one main steam line isolation valve inoperable, subsequent and 3 operation in MODE~ 2 or 3 may proceed provided; iiJlr 0/)
a.
The isolation valve is maintained closed.
A
b.
The provisions of Specification 3.0.4 are not applicable.
Otherwise, be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .
SURVEILLANCE REQUIREMENTS 4.7.1.5 Each main steam line isolation valve shall be demonstrated OPERABLE by verifying full closure within,S,seconds when tested pursuant to Specification 4.0.5.
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PLANT SYSTEMS BASES 3/4.7. 1.4 ACTIVITY The limitations on secondary system specific activity ensure that the resultant offsite radiation dose will be limited to a small fraction of 10 CFR Part 100 limits in the event of a steam line rupture.
This dose also includes the effects of a co ind dent 1. 0 GPM primary to secondary tube 1 eak in the steam generator of the affected steam line.
These values are consistent with the assumptions used in the accident analyses.
3/4.7. 1.5 MAIN STEAM LINE ISOLATION VALVES The OPERABILITY of the main steam line isolation valves ensures that no more than one steam generator will bl~wdown in the event of a steam line rupture.
This restriction is required to 1) minimize the positive reactivity effects of the Reactor Coolant System cooldown associated with ~he blowdown, and 2) limit the pressure rise within containment in the event the main steam line rupture occurs within containment.
The OPERABILITY of the main steam isolation valves within the closure times of the surveillance requirements are consistent with the assumptions used in the accident analyses.
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"'J. or 3, SALEM - UNIT 2 B 3/4 7-3

ML18094B374

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