ML20116K770

Proposed TS 3/4.3.1, RPS Instrumentation & 3/4.3.2.3, Anticipatory RTS Instrumentation

ML20116K770
Person / Time
Site:	Davis Besse
Issue date:	11/13/1992
From:	CENTERIOR ENERGY
To:
Shared Package
ML20116K762	List: ML20116K760 ML20116K766 ML20116K770
References
NUDOCS 9211170367
Download: ML20116K770 (17)

Text

T Dockot Numb 2r bX@-34@ - - ~ ~

j Licenza Numbar NPF-3 3,

Serial Numbsr 2081

', N , '.' OEFINIT**NS _

e

.j

. REPORTABLE EVENT _

.i 1.7 A REPORTABLE EVENT shall be any of those conoitions specified in Section l 50.72 of IC CFR Part 50.

.1 CONTAIN'4ENT INTEGRITY I

1.8 CONTAINMENT INTEGRITY shall exist when:

a. All penetrations required to be closeo during accident conditions are -

either:

1. Capable of being closed by the Safety Features Actuation System.

. or i

2. Closed by manual valves, blind flanges. or deactivrec automatic valves secureo in their closeo cositions. except tnose acprovec 1

' t to De open unoer acministrst1ve controls. l

2. All equipment hatches are closed ano sealed,

c. Each airlock is OPERABLE pursuant to Specification 3.5.1.3.

c. The containment leakage rates are within the limits of Specification-3.6.1.2, and

e. The sealing mechnism associated with each penetration (e.g., welds, bellows or 0-rings) is OPEKABLE.

CHANNEL CALIBRATION _

1.9 A CHANNEL CALIBRATION shall be the adjust = ant, as necessary, of the enannel out:ut suen that it responds with necesseg range and accuracy to known values of tne parameter wnich the channel monitors. The CHANNEL CALIBRATION shall e.. c:::cass the entire channel including the sensor and alarm and/or trip funettons, and shall include the CHANNEL FUNCTIONAL TEST. CHANNEL CALISAATION may on perferinee by any series of secuential, overlapping or total channel steos suen that the entire channel is calibrated.

CHANNEL CHECK l.10 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, wnere possiele, c::mparison of the channel indication and/or status with other L im:ations and/or status derived from indecencent instrument enannels measuring tr.:. same parameter.

l 1-2 knenoment No. 93.135, 147 DAVIS-BESSE. UNIT 1 9211170367 921113 PDR ADOCK 05000346 I P PDR

Docket Numbsr 50-346 y

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L,1 cense Number NPF-3 Serial Number 2081

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COPY 3/4.3 INSTRLHENTAT!CN_

3/4.3.1 DE ACTOR F:0TECTICN SYSTEM IN5i2LS'ENTAT'CN LIMITING CON 0! TION FOR OPERATION 3.3.1.1 As a minimum, the Reactor Protection System instru.entation enannels and bypasses of Table 3.31 shall be OPERABLE with RESPONSE TIMES as snown in Table 3.3 2.

APPL.1CABILITY: As snown in Table 3.3-1.

ACTION:

As shown in Table 3.31.

SURVEILLANCE REQU1FTNTS 4.3.1.1.1 Each Reactor Protection System instruuntation channel shall be demonstrated OPERA 8LE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operattens curing the MODES and at the frequencies shown in Table 4.3-1.

4.3.1.1.2 The total bypass function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing of each channel affected by bypass operation.

4.3.1.1.'3 The REACTOR PROTECTION SYSTEM RESPONSE TIME of each reactor trip function shall be demonstrated to be within its limit at least once per 18 months. Each test shall include at least one enannel per function such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific it actor trip function as shown in the " Total No. of Channels" column of Talle

, 3.3 1.

m N:03VATION COPY DAVIS-BESSE, UNIT 1 3/4 3-1

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. e4 MINIHist TOTAL NO. .CHANNElJi CSANNELS AFrtlCAslE FISICTIONAL ISIIT OF CSAISIELS TO TRIF orEmmet.E N0085 ACTIEM4

' l. Manual Beacter Trly 2 1 2 1, 2 and a 1

-2. Righ' Flux 4 2 3 1, ' 2 r 28,/C l

3. RC Nigh Temperature 4 2 3 I, 2 33,/0 t

4. Fluz - 4 Flux - Flow 4 '2(a)(b) 3 1, 2 28,/d.

)

5. ac law Fressure 4 2(a) 3 I, 2 3sj/o l

6. RC sigh Pressute 4 2 1

3 1, 2 33,/0 l

7. aC Fressure-Temperatiere 4 2(a) 3 1, 2 31, /0 l  ;

$ 8. sigh Flum/ h r of Beactor Coelant J Peeps'en -

4 2(a)(b) 3 1, 2 13,/(' l la

9. Containeemt Eigh Pressere 4 2 '3 i , i 1, 2 31,/0

10. Intermediate fange, Igestree Fles

• sad Sate. '+'

t

2. ls/A 2(c) I, 2 and a 4 II. Source Bange,.Neutree Flus and sate i A. Startop d 2 N/A 2 288 and a $ l S. Sheldoen 2 N/A I 3, 4 and:3 6:

! I

12. Coasteel Bad pr8ve Triy greadiers 2 per trip system i per - e s ip system 2 pea talp system I. 2 and a Ig, as- +

E .' 13. Reacter Trly IIedule 2 per trip' I per a s A p . 2.per I, 2 and a

g ' system systes' 'tr$p system 73 y>pgg g ggngg n a a e.

14. Shutdown Bypass sigh Fressure 4 C .e 2 3 2**, 3aa 4an,' Sea 63 .C E"$?!

.15. SCR. Relays gp2p 2 2 2 1,2 and a 93 7 5.j g.:l

$ E$f b$

C'

Docket Numb:;r 50-346

. License Nunber NPF-3 l'.* ' . '

! m3LE 3.3-1 ICentinuec)

Serial Number 2081 Attachment Page 14 TABLE NOTATION

'With the control rod drive trip breakers in the closed position ano

te control reo drive system capable of roo withdrawal.

"When Shutdown Bypass is actuated.

TrHe crevisions of Specification 3.0.4 are not applicable, s*High voltage to detector may be de energized above 10-10 amos on botn

ntermeafste Range channuls.

'a) Trip may be manually bypassed when RCS pressure 1 1B20 psig by actuating Shutdown Bypass provided that:

(1) The High Flux Yeip Setpoint is 1 5% of RATED THERMAL POWER, (2) The Shutdown Bypass High Pressure Trip Setpoint of < 1520 ~

psig is imposed, anc (3) The Shutdown Bypass is removed when RCS pressure > 1820 psig.

(b) Trip may be manually bypassed when Specification 3.10.3 is in effect.

i

(:) The minimum channels CPERABLE requirement may be reduced to one wnen Specification 3.10.1 or 3.10.2 is in effect.

ACTION STATENENTS

'CTION 1 - With the number of channels OPERABLE one less than recuired by the Minimum Channels OPERABLE requirement, restore tne inoperable channel to OPERABLE status within 48-hours or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and/or open the control rod drive trip breakers.

ACTION 2 -

With the number of OPERABLE channels one less than the Total Numoer of Channels STARTUP and/or POWER OPERATION may proceed provided AW of the following conditions are satisfied

• both byfmsec) or

a. The inoperable channel is placed in the4tripped condition within one hour.

b. ': udad Ch:n=1; OPEP/EE muir:=n i: =:;

howeve , := :ddition:1 chan=1 =y b: bypatsed f;+

tp tS ? W r for tu veillanc: to: ting per-4pecification 4.3.1.1.1, DAVIS-BESSE, UNIT 1 3/4 3-3

m__ .. .

9 License Number NPF-3:

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. Serial Number 2081 Attachment Page 15 TABLE 3.3-1 (Continued)'

ACTION STATP!ENTS (Continued)

- =d the -12 ;- :ble the- 01 -ber - y b: byte:=d f;r ;; ::-

20 i ::= fr =y 26 h:= ;:: led v5= ===:r; :s ;;;; :h:

i; br 4 r ee eeisted vit h 'he losit ef t't eh--.:1 5-12

-:::::d pr S;::1f!=:10: 6. 2.1.1.1, rd -

b

g. Either. THERMAL POVER is restricted to < 75% of R/ TED THERMAL POVER and the High Flux Trip Setpoint is 'aduced to

< 85% of RATED THERMAL POVER vithin 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or ' , QUADRA!C POVER TILT is monitored at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

ACIION 3 - Vith the number of OPERABLE channels one less than the Total Number of Channels STARTUP and POVER OPERATION any proceed provided t::t f--th fell:=; :=diti:r: =: = :i:fi:d; f bypansM or

-a,- i

,'The inoperable channel is placed in the4t ripped condition  :

vithin one hour. 8

-b. The y.inies Channels 0?::RAF.1.7. sequires ; 12 ee;, hv.e.eg, a e -dd!!!c- ' h-- el - y be by;r:d f= e; :: 2h==

f= ==:illrr: t:::1 ; ;= S;;;ifice:i= 1.2.1.1.1, r-f th e i= ;: 2ble ak-- el 25e e r; 5: by r: M != up :: 20

-1 u:= in =y 24 her ; :ird th= :=:::: y t: :::: th:

tri; b : '--- -- eeisted vith t he le;ie ef- th e ak-- e) b4 t=::d ;= Sp=ifi= tic 4.3.1.1.1.

ACTION 4 - Vith the number.of-channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POVER levels

a. < 5% of' RATED THERMAL POWER restore the inoperable channel-to OPERABLE status prior to increasing THERMAL POVER above 5% of RATED THERMAL POVER.

b. > 5% of RATED THERMAL POVER, POVER OPERATION may continue.

DAVIS-BESSE, UNIT 1 3/4 3-4 Amencment No.135

Schot RumLMr 50-346- 7 m' t Licenas Numb:r NPF-3

. L . m a' Serial Numbar 2001

.k l W l I Attachment

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COPY TABLE 3.3-1 (Continued)

ACTION STATEMENTS (Continueo)

AC ::!!'5 - Vith the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requireaant and with the THERMAL POVER levels

a. < 10-10 amps on the Inte. mediate Range (IR) instru-mentation, restore the inoperable channel to OPERA 3LE status prior to increasing THERMAL POVER above 10~ " amps on tna IR instrumentation.

b. > 10-10 amps on the IR instrumentation, creration may continue.

AC-~:'i 6 - Vith tne numoer of channels OPERABLE one less tnan reoutred by the Mininum Channels OPERABLE requiressat. verify compliance vith the SHITICOVN MARGIN requirements of Specification 3.1.1.1 vithin one hour 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.

ACT!0N 7 - Vith the number of OPER&BLE channels one less than (Na Total Number of Channels STARTUP and/or POVER OPERATION may proceed provided all of the following :enditions ar2 satisfied

a. Vithin 1 hour:

1. Place the inoperable channel in tne tripped condition, or

2. Remove power supplied to the control roc trip dev2ce associated with thi inoperative channel.

b. One additional channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.1.1.1 sad the inoperacia channel above may be. bypassed for up to 30 minutes in any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> paried when necessary to test she trip breaker associated'vith the logic of the channel being tested per Specificataan 4.3.1.1.1. The inoperable channel above may not be bypassed to test the logic of a channel of the trip system associated with the inopersole channel.

IN C RIV Aha COPY OAVIS-BESSE. UNIT 1 3/4 3-5 Amancment No. AOS.123 (Next :: age is 3/4 3-5a.)

WocL%t wu3scr blAJJG Licensa Numb 2r NPF-3

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' * *-C Serial Numbar-2081

• - Attachment-Page~17 7A31.E 2.3-1 (Continueo)

ACCON STATEMENTS (Continuse)

Ar:b 8 - Vith one of the Reactor Trip Breater diverse trip features.

(undervoltage or snunt trip devices) inoraraole. restore it to OPERABLE status in 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or place the ;ressar in trip in the next hour.

- ;C: N 9 - Vith one or both channels of SCR Relays inopersole. restore the channels to OPERABLE status during the next COLD SHUTDOVN exceeding 24' hours.

one less hCTI0d 10 - W,lh +ke- number o F - clunnds CPnRMLE Haan ths M;nomum Channeh Cr'iKMAE reau.rement) r A w < th in o n e. ho v.q p la ce. o n e , n o,,e,a s te Ll) anne [ in frop and the ~%ewad inopen<ble-channeI in bypass, anct cesfore one oF 1he..

nnc,puable. channels ft 67Ee Ar3t.& . sin f05 w dhon +6 hours ar be. in HOT sTM0ay w, thin rhe. ne.x t G> hours and of" *'

raattor trip i rsakers ,

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- AVIS-BESSE. UNIT 1 3/4 3-Sa Amancasst No. ,10,8,135

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• P,; IinitiIoriAI. utiIi

• (seconas) '

M Manual Reactor Trip tiot Applicable c 1.

• 2. liigh Flux * - 0.266

3. RC liigh Temperature r Applw able y T 4. Flux - a Flux - Flow * - Variable Flow  : 1.71 7

)y - Cor.stant Flow 1 0.266 Q

[g 5. RC Low Pressure

. 0.341 O g

( -a -

Y 6. RC liigh Pressure 0.341 4p ,

e

- 7. RC Pressure - Temperature - Constant Temperature riot Applicatise

8. Iligh Flux / Number of Reactor Coolant Pumps On* 1 0.631*** C

< 9. Containment High Pressure flot Applicable 3I E

g k

• Neutron detectors are exempt from response time testing. Response time of the 2

. neutron flux signal portion of the chan.sel sh_el be measured from detector P output or input of first electronic component in channel.

** Including sensor (except a, noted) HI's instrument delay and the bred er ilelay.

• • • A 0.24 sec delay time has been assumed f or pistp monitor. gym

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l DAiris-18551,1: NIT 1 3!4 3-7 A"-t No. /,Af eh8.AfJ. I U

Licensa Numbar NPF-3

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• Scrial Numbar 2081 e , ,

Attechment Page 20 TABLE 4.31 (Continued)

NOTATION .

(1) - If not performed in previous 7 days.

(2) - Heat balance only, above 13% of RATED TEIRMAL POVER.

(3) - Vhan THERMAL F0YER 1T?] is above 50% of RATED TIERMAL POVE1 (RTF),

and at steady state, coerare out-of-core sensured AIIAL F0VER' IMSA! M CE {AFI,) to incore sensured ArTAt. F0VER IMBALANCE { APIg ] as follovst RTF (AFI' - AFI;) . Offset Error TP Recalibrate if the absolute value of the Offsst Error is 2, 2,3%

(4) - AIIAL F0V G, IM1ALANCE and loop flow indicatinas only.

'5) - Verify at least one decade overlap if not verified in previous 7 days.

(6) - Neutron detectors may be excluded from CEDetEL c1LT121 TION.

(7) - Flow rate sensurement sensors may be excluded free CIMetEL CAtTaeATION. Dovever, each flow naasurescat sensor shall be calibrated at least once per 18 sooths.

(8) - The CHANNEL TUNCTIONAL TEST shall indspendently verify the OPERASILITT of both the undervoltage and shunt trip devir.as of the Reactor Trip Arnakers.

t' e

• - Vith any control rod drive trip breaker closed.

~

• • - When Shutdown typass 1s actuated.

- - ~ ~ - 7e.r f'orme d o r) cA DM NdD YM MD' F

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l DAVIS-RESSR, UNIT 1 3/4 3 4 Aasedmont Me. 43, AQS.MA W

Docbot Wu$cr M-SM 7 Licenso 11urbar NPF-3 9 N F,i y, t

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j Sarial Numbar 2081 Attachm:nt Page 21 I!IST7UME! NATION Cf s ANTIC!PATORY REACTOR TRIP SYSTEM I!ISTRUME! NATION

' LIMIT!NG CONDITIO!1 FOR OPERATION

, 3. , - -

3.3.2.3 The Anticipatory Reactor Trip System instrumentation channels of

Table 3.3 17 shall be OPERABLE. l 1

, APPLICABILITT As shown in Table 3.3-17 I d

] ACTIO!!: As shovn in Table 3.3-17 I ii i

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1

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' SURVEILLANCE REQUIRIMEffrS II

!4.3.2.3 The Anticipatory Reactor Trip System shall be demonstrated OPERABLE by

the performance of the CHANNEL CHECK. CIIANNEL CALIBRATION and CHANNEL FUNCTIONAL

! TEST for the modes and at the frequencies shown in Table 4.3-17. j INFCHAli0$

CCPY DAVIS-BESSE. UNIT 1 3/4 3-30a Amendment No. 77,135

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TABLE 3.3-11 d -

I Oy

AIGICIPATORY REACTOR TRIP SYSTEM lil5TittIMEIRATIUt_l c

~

TOTAL 110. C11ANNELS HIllIHilH g 0F TO CBANNELS APPLICABLE g "

CilANNElS TRIP OPERABLE MODES ACTIori FUNCTIONAL UNIT 2 3 1 IB l 8

1. Turbine Trip 4

2. Trip of Both Main Feed Puep 1 l'3 l 4 2 3 Turbines 3 1 20 g 4 2

% 3. Output Logic e-5 2 m

O l= O og W I* Trip autostically bypessed belov 45 percent of RATED TIIERHAL FOVEH g (b) Applicable only above 45 percent of BATED Ti!ERMAL POVER

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Serici Numb 3r 2081

• Attechm:nt Page 23 TABLE 3.3-17 (C0!TTINUED) i ACTION STATEMENTS ACTION 18 - Vith the number of channels OPERABLE one less than required by the Minimus channels OPERABLE requirements. restore the inoperablu channel to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or reduce reactrer power to less than 45 percent of RATED THERMAL POVER vithin the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

ACIION 19 - Vith the number of channels OPERABLE one less than required by the Minir _k OFJ' v4 0?'3ABLE requirements. restore the inoperable etse n ' W

• status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least L i STd W T . the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

ACTION 20 - Vith the number of om3 I channels one less than the Total Number of Channels. I.TARTUP and/or POVER OPEPJLTION may.

procird provided bot). ci the folloving conditions ars satisfied a) The control red drive trip breaker associated with the inoperable channel is placed in the tripped condition within one hour.

b) The Minimum Channels OPERABLE r*;uirement is mett however, one additional control rod drive trip breaker associated with another chaanel may be tripped for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.2.3, after reclosing the control rod drive trip breaker opened in a) above.-

n..

s 3-30c, DAVIS-BESSE, UNIT'l 3/44Ne- ' Amendment No. 73,128.125

ed

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'E TABtE 4 3-11 d

E ANTICIPATORY , REACTOR TRIP SYSTEM 1,11*ITEllHEfffATity SURVEII.IANCE REtll11HEHEffr5 sa C11 ANNE 1. HODES lt! UNICll CHAIG4EL CHA898EL FINICTIONAL SURVEILLAIICE IS CEECK CALIBRATION TEST REQUIRED _

. FiniCTIONAL INilT

1. Turbine Tripk " S Not Applicable f SA I 1

2. . Main Feed Pump Turbine Trip S Not Applicable E'SA(c) 1 l

Not Applicable - Not Applicable H I

3. Output loc i c u

t w b

l N i

t Trip automatically bypassed below 45 percent of RATED THERNAL FOUEM Applicable only above 45 percent of RATED TessaAL POWER

. tc) ke form on a ' ST~AG6 6 AE D TEST SA315 E 2rscW 7 s c an

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stiMdV WuRIor foCT476 License Number !1PT-3 i

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SPECIAE TIST EXCEPTIONS i p

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Attachment Page 25 l

l' PHYSICS *TSTS M[

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, 1 LIMITING CONDITION FOR OPERATION

~

I!3.10.2'ThelimitationsofSpecifications 3.1.1.3. 3.1.3.1, 3.1.3.2, l

l 3.1.3.5, 3.1.3.6, 3.1.3.7, and 3.1.3.9 may be suspended during the per- l l

for=ance of PHYSICS TESTS provided: )

a. The TERMAL P0kT.R does not exceed 5% of RATED THEPJiAL POWER, and l

t b. The reactor trip setpoints on the OPERABLE High flux channels

, are set. at i 25* of RATED TERMAL POWER.

. The nuclear instru=entation Source Range and Intermediate Range bigh startup rate control red withdrawai ir.hibit are OPERABLE.

APPEICABIEITY

MODE 2.

ACTION:

With the TERMAL P0kT.R > 5% of RATID TERMAL POWER, imediately open the control red drive trip breakers.

SURVE7LIANCE REOUIREMENTS i

1 4.10.2.1 The TERMAL P0kT.R shall be deter =ined to be 15* of RATED THERFJd.

. P0kT.R at least once per hour during PHYSICS TESTS.

4.10.2.2 Each Source and Intermediate Range and High Flux channel shall be subjected to a CHANNEL FUNCTIONAL TEST within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> prior to initi-ating PHYSICS TESTS.

l ENAT09 COPY l

DAVIS-EESSE,. UNIT 1 3/4.10-2 Amendment No. 33

- ~ - . - - . .- .. _. .

Echot liuxb:r 50-346 g% " J ) Licenso Numb 3r HPF-3 o ./ . . I r l ISorial Number 2081 t

Attachmsnt Page 26 QF. %

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.3 7tsratmErrrAT:en jASES UI. 3.1 ano 3/4.3.0 ?EAC;;R TECTECT!CN SYSTEM AND SAtc.. !Tn c.i

lSTRtTHENTATICH The OPEP1BILITT of the EPS. STAS and STRCS instrumentation systems ensure tnat

1) the associated action ano/or trip vill be initiatto vnen tne parameter onttored by eacn enannel or comoination thereof exceees its setpoint. ) the specified coincidance logic is maintained. 3) sufficiant reouncancy is

.alntained to permit a enannel to be out of service for testing or

.alntenance, and 4) sufficient r' stas functional capacility is available for EPS. IFAS and STRCS purposes iros diverse parameters.

The OPERABILT:7 of these systess is requireo to provice tne overall reliacility, recuncance ano oiversity assuaea available in tne f acility design f or tne protection ano mitigation of accident ano transtant conoitions. The integrated operation of esen of these systems is consistant vith the assumptions used in the accident analyses.

The surveillance requirements specified for thase systems ensure that the ,

overall system functional capacility is maintained comparacle to the original

' design standards. The periodic surveillance tests perferseo at the minimum frequencies are sufficient to demonstrate this capability.

The measurement of response ti=e at the specified frecuencies provides assurance that the RPS. ITAS. and STRCS action function associaten with each channel is completeo vithin :ne ti== limit assused in :ne safety analyses. No crecit vas taken in tne analyses for those channels vita resconse times

ndicated as not applicaele.

Response time any be canonstrateo by any series of secuential. overlapping or total channel test measurements provided that such tests oemonstrate the total enannel response time as definen. Sensor response ti=a verification may be l

demonstrated by either 1) in place, onsite or offsite test ::asurtsents or 2) i utili:ing replacement sensors vith certified response ti:ss.

.a STRCS channel consists of 1) the sensing devicosa). :) associated logic and output ruays (including 1 solation of Main feeovater Hon Essential Valycs and Turbine Trip), and 3) power sources.

The STRCS response ti:e for the turbine stop valve closure is based on the conoined response ti=es of =ain steam line lov pressure sensors logic cabinet delay for main steam line lov pressure signals and closure ti:e of the turbine j stop valves. This SF7.CS response time ensuresthat the auxiliary feedvater to j the unaffected stama generator vill not be isolated due to a SFRCS lov 1

pressure trip during a =ain steam line breax accident.

l 1

B 2/4 3-1 Asanc=ent No. 73.125

AVIS-BTR U F"gy *R H M A.,Gt " "" -

__ fADV .

~

r Dockot Nukbar 50-346

" License Humbar t&F-3 N. $.

{y{,pd I Serial Number 2081 Attachment 1

j Vage 27.

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' 3/4. 3 lNSTRtTMENTATION BASES REACTOR PROTECTION SYSTEM AND SATETY SYSTEM

,INSTEUMENTATION 3/4.3.1 and 1/4.3.2 (Continueo) 4

/ Saistty-grade anticipatory reactor trip is initiated by a turbine trip (above 45

!!percentofRATEDTHERMALPOVER)ortripofbothmainfeedvaterpumpturbines.

d This anticipatory trip vill operate in advance of the reactor coolant system

]highpressurereactortriptoreducethepeakreactorcoolantsystespressure L and thus reduce challenges to the pilot operated relief valve. This l

antici::atory reactor trip system vas installed to satisfy Item II.K.2.10 of

" NUREG-0737. The justification fut the ARTS turbine trip arming level of 45% is given in BAV-1893. October, 1985.

0 ll i

V I

l EORMTION -

ll CCPY 8 3/4 3-la Amenomant No. 73.

DAVIS-BESSE, UNIT 1 125,125, 135

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