ML20151H789

Proposed Tech Specs Removing Low Feedwater Trip from Tech Specs & Adding Requirements for Steam Generator Level Median Selector Function

ML20151H789
Person / Time
Site:	Prairie Island
Issue date:	07/18/1988
From:	NORTHERN STATES POWER CO.
To:
Shared Package
ML20151H778	List: ML20151H777 ML20151H780 ML20151H789
References
NUDOCS 8808020050
Download: ML20151H789 (5)

Text

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l EXHIBIT B

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l License Amendment Request Dated July 18, 1988 f Docket Nos, 50 282 License Nos. DPR.42  !

S0 306 DPR 60 l i

j Exhibit B consists of revised pages for the Prairie Island Nuclear f I Cenerating Plant, Units 1 and 2. Technical Specifications showing i l the proposed changes: l d

t i Pages: TS.2.3 3  !

j TS.2.3 6  !

Table TS.3.S.2 (Page 2 of 2) i .

1 Table TS.4.1 1 (Page 2 of 5) i l

i I I h

I 1 i

! i a >

l j

i i i i 1 i l l f

a i

A l

i i i l

yjSS*lME $N[f5 2 ,

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. __._ __ ___ _-- ____.-_- _ _ _ _ _ - _ - _ _ _ _ _ _ _ - _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . - - _ - - - _ _ g.. -www

79 F L ,J D A d L1 TS.2.3-3

_L _ _ _ _

g, . 0.002 for T > T' , o for T <T*

i o a 10, sec ,

f(i* .s defined in d. above.

f.

Mor coolant flow per loop ,190% of

.ticated loop flow as measured at loop I s

g. O, .: tor coolant pump motor breaker.

(1) Reactor coolant pump bus undervoltage -

175,% of normal voltage.

(2) Reactor coolant pung bus underfrequency -

158.2H" l

h. Power range neutron flux rate.

(1) Positive rate - 515% of rated power with a time conscant 22 seconds I .

(2) Negative rate - $15". of rated power with a time constant >_2 seconds

. 3. Other reactor trips

a. High pressurizer water level 190% of narrow range instrument span.

I

b. Low-low steam generator water level 15% of narrow range instrument span.

• e. Low steam generator water level - 115% of narrow range instrument in coincidence with steam /feedwater mismatch flow - 11.0 x 105 lbs/hr. -

d. Turbine Gener ter trip (1) Turbine stop valve indicators , closed (2) Lov auto stop oil pressure 145 psig

e. Safety injection - See specification 3.5 B. Protective instrumentation settings for reactor trip interlocks shall be as follows:

1. "At power" nactor trips that are blocked at ' low power -- -

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(low pressurizer pressun, high pressurizer level, and ~~T4-r-loss of flow for one or two loops) shall be ablocked whenever:

a. Power range neutron flux is all2% of rated power or,

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b. ti.rbine iced is d10% of full load turbins impulse pressure.

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• The lot: steam generator water level in coincidence with steam /feedvater mtsnatch trip may be deleted following installation of the digital feedvater control syscam incorporating the median signal selector

+necion.

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TS.2.3-6 The*othe:' reactor: trips specifi .m3s a lha ovida. additional

• protection'.'

r at v i ru a /

.e4 - r' h at i_ . [ The saf ety inj ection signal trips the reactor to decrease tha severity of the accident condition. The reactor is tripped when tha turbine generator trips above a power level equivalent to the load rejection capacity of

. the steam du=p valves. This reduces the severity of the less-of-load transient.

The posiefvs power range race trip provides protection against rapid flux

• increases which are characteristic of red ejection events from any gover 1 eval. Specifically, this trip cempliments the power range nuclear flux high and lov trip to assure that the criteria are met for rod ej ection from pc tial power.

Tho negative power range rate trip provides protection satisfying all IIII c:iteria to assure tha- d d-u: DNBR is naintained above 1.30 for Exxon Nuclear fuel and above 1.17 for Westinghouse fuel for all multiple control red drop accidents.- Analysis indicates (Section 14.1,.3) that in the case of a single rod ,

drop, a recurs to full power vill be initia'ted by. the acto =atic reactor control system in response to a continued full'pover turbine lead demand and it vill not result in a LN3R of less than 1.30 for Exxon Nuclear fuel or 1.17 for Westinghouse' fuel. Thus, auto =atic protection for a single rod drop is not required. Ad=ini-st:stive li=its in Specificasion 3.10 require a power reduction if design power distribution li=1ts are exceeded by a single =isaligned c dropped red.

References:

(1) TSAR 14.1.1 (2) ' TSAR Page 14-3 ~

' (3) . TSAR .14.2. 6 (4)a.TSAA.14.3.1

~ (5) TSAR ~14.1.2 *

(6) ' TSAR 7.2, 7.3 (7) TSAR 3.2.1 (8) TSAR 14.1.9 (9) ,

TSAR 14.1.11 ,

A t ~ , - . . - . .

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TA!!.E TS.3.5-2 (rege 2 of 2)

INSTRUttENT OPERATING C0tIDITIONS FOR REACTOR TRIP ,

l .

1 2 3 4 HINIIIUM HINIHUN PERilISSIBLE OPERATOR ACTION IF OPERABI.E DECREE OF BYrASS CORIDITIONS OF COI.UllN t

FUNCTIO 0fAL UNIT CIIANNEI.S REDUNDANCY CONDITIONS (I) 1 OR 2 CANNOT BE flET j ,

13. Underveltage 41V RCP Bus 1/ bus 1/ bus italistain hot shutdousi

14. Usederfreguesecy 4KV Bus 1/ bus,, 1/bies Halutnin liot shutilown

15. Contrat Red Hisalignment tionttor

a. Rod posilloes deviattoes 1 -

I.og Jata required by

b. Qisadrant powe- tilt 1 -

TS 3.10 I and TS 3.10 J l 16. RCP Breakers Open 2 1 Itaintain hot aluetdoun

17. Safety injection Actuation Sigital 2 1 Hafeitain hot shutdo'ra--

4

• 18. I.o Feedeater Flow 1/ loop 1/ loop flaintain loot shutdo sis _. w L j

19. Aestosmetic Trip I.ogic includieng Reactor Trip Breakers- 2 1 Notes 3, 4 I i

I.J t".3 J Note It Automatic permissives seat listed h

j Note 2: SAien bypass condition exists, maisitales normal operation ,

Mote 3:

Witle thesleutdova lemet loot numberwithin of operable channels

& hours; however, oneone less thasi cleansiel may bethe minimum bypassed for upoperable to 4 hoeirschannels for siervei registrement, b testing per Specification 4.1, provided time other channel is operable. _. f ;

Note 4: When in the hot shestdown conditiosa wIth the number of operable channels one less thain the minimum op e;

, channels requirement, restore the inoperable chansiel to operable staties witisin 48 lioners or open the reactor h *,a e, trip breakers within the next. hoise. gg F.F. = Fes11 FeJer -

r "ea . "in a = One adet*,fonal channet ma he takens out of e ,o, -

?! ** = this trip may be deleted following installation of the digital feedwater control system

• l incorporating the median signal selector function. "A 1

a o

i

I

. TABLE TS.4.1-1 (Fcga 2 of 5) -C'-

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111HIHitt FREQtlENCIES FOR CllECKS. CALIBRATIONS AND ,

TEST OF INSTRittENT CitAlaNEI.S ,

i.

C' Channel Functional Response .

Description Check Calibrate Test Test Remarks E J 6  :

• 9. Amales Red Positiess 5(1) R T(2) NA 1) With step counters F M(2) 2) Rod Fosition Deviation Honitor I

" Tested by updating computer ban C. 1 2

count and comparing with analog rod position test signal

• W

10. Red Feetties Rank S(1,2) NA T(3) NA 1) Ulth analog rod position Countere M(3) 2) Following rod motion in excess q l six inches when the computer is [d out of service ~ f' ;

3) Control rod banks insertion ilmit__

monitor and control rod position t.,

. deviation monitors

11. Steam Generator Level S R H HA a 12. Steam Generater Flow 5 K H HA

Hiematch

. 13. Charging Flow 5 R NA NA

14. Residmet Neat Removat S(1) R NA NA 1) When in operatiosa

} y Fump Flew j 15. Berle Acid Tank I.evel D R(1) M(1) NA 1) Transfer logic to Refueling Water Storage Tank

16. Refuelleg Meter Storage U- R

~

H(1) NA 1) Functional test can be performed m, Tank inval by bleeding transmitter 73-ao e

, *a

17. Volume Centret Tank 5 R NA NA

• u,a L,

lr 18a. Centainment Fressure S R H(1) NA- Ufde Range Containment Pressure ,y

1) Isolation Valve Signal

• 51 Signal .

ta e f ISb. Ceetatemest Pressure 5 R H MA Narrow Range Containment Pressure " ,s,

/; Eteam Line Isolatlee .

m J

1 r

• Fo11aving installation of the digital feedwater control system, oniv steam flow channels are checked,

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