ML20077E517

Proposed Tech Specs 3/4.3.2 Re Removal of Decay Heat Isolation Valve & Pressurizer Heater Interlock Requirements in Modes 4 & 5

ML20077E517
Person / Time
Site:	Davis Besse
Issue date:	06/04/1991
From:	CENTERIOR ENERGY
To:
Shared Package
ML20077E505	List: ML20077E502 ML20077E511 ML20077E517
References
NUDOCS 9106100433
Download: ML20077E517 (7)

Text

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Docket Number 50-346 License Number NPF-3

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1111SPAGE PROVIDED Page 6 of 1 INSTRUPENTATION 3/a.3.2 ! AFETY SysitM INSTRUMENTATION SAF(TY F(ATUR(5 ACTUATION SYSTEM INSTRUMENTATION t!M1 TING CON 01T10N FOR OPERATION 3.3.2.1 The Safety Features Actuation Systen (SFAS) functional units shown in T:ble 3.3 3 thall be OPERABt.E with their trip setpoints set consistent with the values shown in the Trio Setpoint column of Table 3.3 4 ano with RESPONSE TIMES as shown in Table 3.3 5.

A p pi. !!iB ! t I TY :

As shown in Table 3.3 3..

Aci!ON:

a.

Witn a SFA5 functional unit trip setpoint less conservative than the value shown in the Allowab'e Yalues column of Table 3.3 4. declare the functional unit inoperable and apply the applicable ACTION recuirement of Table 3.3-3. untti the func-tional unit is restored to OPERABLE status with the trip setcoint acjustec consistent with the Trip 5etpoint value.

b.

With a SFAS functional unit inoperable. take the action shown in Ta ble 3.3-3.

SURvtitLANet REOUIREwtNTS 4.3.2.1.1 Each 5FAS functional unit shall be demnstrated OPEP>BLE by tne performance of the CFANNEL CHECK. CHANNEL CAllBRATION and CHANNEL FUtiCTIONAL TEST during the MODES and at the frecuencies shewn in Table 4.3 2.

a.3.2.1.2 The logic for the bypasses shall be demonstrated OPERABLE during the at power CHANNEL FUNCT10rtAL TEST of functional units affected by bypass operation. The total bypass function shall be demonstrated CPERABLE at least once per 18 months during CHANNEL CAtlBRATION testing of each functional unit affected by bypass operation.

4.3.2.1.3 The SAFETT FEATURES RESPONSE TIME of each 5FA3 function shall be demnstrated to be within the limit at least once per 18 months.

Each test shall include at least one functional unit per function such that all functional units are tested at least once every N times 18 months where N is the total number of redundant functional units in a specific $FAS function as shown in the " Total No. of Units

• Colunn of Table 3.3-3.

DAVIS-BESSE. UNIT 1 3/4 3-9

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TABLE 3.3-3 (Continued) ezo ESO enk b$

N SAFETT FEATliRES ACT11ATIOf3 STSTEM_ IflSTRtlHENTATION E

HINIHUM TOTAL NO.

UNITS UNITS APPLICABf.E d)

OF UNITS TO TRIP OPERABIE MODES ACT IOf 3 l FUNCTIONAL UNIT J.

HANUAL ACTUATION SFAS (except Containment a.

l Spray and Emer;;;ency Susp l

Recirculation) 2 2

2 1,2,3,4,6****

12 l

b.

Containment Spray 2

2 2

1,2,3,4 12 l

T 4.

SEQUENCE LOGIC C11ANNELS 4

2***

3 1,2,3,4 10# l Y

a.

Sequencer g

b.

Essential Bus Feeder l

Breaker Trip (90Z) 2 1

2*****

I,2,3,4 151 l k

c.

Diesel Generator Start, Load Shed on Essential E

Bus (59Z) 2 1

2 I,2,3,4 13I l 5.

INTERLDCK CEANNEl_S s.

Decay ticat Isolation Valve I

I 1.2,3 M 137 l O

j, aj!y. g#f r er 14$ j b.

rressurizer sea ers 2

2 2

d v3

• g.

C' L

3:

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- - - ~. - -

Docket Number 50-346 License Numbet tJPF-3 Serial !Jumher 1918 Attachment

(

Page 8 of 12 TABLE 3.3-3 (Continued)

TABLE NOTATION l

Trip function may be bypassed in this MODE vith RCS press.t. belov 1800 psig.

Bypass shall be automatically removed when RCS pressure i

exceeds 1800 psig.

Trip function may be bypassed in this MODE vith RCS pressure belov 600 psig.

Bypass shall be automatically removed when RCS pressure exceeds 600 psig.

One must be in STAS Channels el or 83, the other must be in Channels 82 or #4 This instrumentation must be OPERABLE during CORE ALTERATIONS or l

movement of irradiated fuel vithin the containment to meet the requirements of Tech. Spec 3.9.4 All functional units may be bypassed for up to one minute when starting each Reactor Coolant Pump or Circulating Vater Pump.

LObw elt/.er OMJHeat Ebe4t/0A OIve' n of'ehe r r r e e.tThe provisions of specification 3.0.4 are not applicable.

ACTION STATEMENTS ACTION 10 -

Vith the number of OPERABLE functional units one less than the g

Total Number of Units, STARTUP and/or POVER OPERATION may l \\

proceed provided both of the following conditions are satisfied:

a.

The inoperable functional unit is placed in the tripped condition within one hour. For functional unit 4a the sequencer channel shall be placed in the tripped condition by physical removal of the sequencer module.

b.

The Minimum Units OPERABLE requirement is met however, one additional f unctional unit any 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 4.3.2.1.1.

ACTION 11 -

Vith any componant in the Output Logic inoperable, trip the I

associated components within one hour or be in at least BUT STANOSY vithin the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOVN vithin the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

ACTION 12 -

Vith the number of OPERABLE Units one less than the Total Number I

of Units, restore the inoperable functional unit to OPERABl2 status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least BOT STANDBT vithin the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SEUTDOVN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

ACTION 13 -

a.

Vith less than the Minicus Units OPERABLE and reactor l

coolant pressure > 438 psig, both Decay Beat Isolation Valves (DH11 and 0812) shall be verified closed.

DAVIS-BESSE. UNIT 1 3/4 3-12 Amendment No. 28, 37.

22. 207. 135 ac

h hlhh Docket Number 50-346

' License Number Ni'F-3 HMh I HU W lph Serial Number 1918 m:t:rm FORINFORMAT.ON ONLY TABLE 3.3-3 (Continued)

ACTION STATEMENTS b.

Vith Less than the Minimus Units OPERABLE and reactor coolant pressure < 438 psig operation may continues however, the functional unit shall be OPERABLE prior to increasing reactor coolant pressure above 438 psig.

ACTION 14 -

Vith less than the Minimun Units OPERABLE and reactor coolant i

pressure < 438 psig, operation may continues however, the functional unit shall be OPERABLE prior to increasing reactor coolant pressure above 438 psig, or the inoperable functional unit shall be placed in the tripped state.

ACTICN 15 -

Vith the numDer of OPERABLE functional units one less than the Total Numoer of Units operation may proceed provided both of the follovi.sg conditions are satisfiedi a.

The inoperable section of a functional unit is placed in the tripped condition within one hour.

b.

The Minimum Units OPERABLE requiraeant is mets however, the inoperable section of a functional unit 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 4.3.2.1.1.

DAVIS-BESSE. UNIT 1 3/4 3-12a Amenoment No. 28. 52.,144,135

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TABl.E 4.3-2 (con inued) y g

y SAFETY FEATifRES ACTilATION SYSTEH Irl5TRIIMI!frATinti stravEII.t_Af4CE REQllIREMEtiTS

• 7U i

m w cn

.t'1 cy CilANNEL H0 DES IN U111C11 CilAHHEL CilANNEL FIDICTIONAL SIIRVEILLANCE

• e FIRK~TIONAL l#4IT CHECK CALIBRATION TEST RE0llIRED o

5.

INTERIDCK CHANNELS a.

Decay Beat Isolation Valve S

R b.

Pressurfrer Beater 1, 2. J M S

R 3Qg ad M

e.

• • See Specification 4.5.2.d.1 n

TABLE NOTATION g

(1) Hanual actuation switchen shall be tested at least once per 18 months dur ing sleut down.

At! other g

circuitry associated with manual saf eguards actuation shall receive a CI8 ANNE!. FtJNCTIONAL TEST at r

a least once per 31 days.

I (2) The Cll ANNEL FUNCTIONAL TEST ahnll include exercising the transmit ter by applying cither vacuum or i.

?

pressure to the appropriate side of the transmitter.

o i

The surveillance requirements of Section 4.9.4 apply during core alterations or movement of Irtadiated fut? within the cnntainment.

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Docket thimber 50 346 Lidnse f;omber fiPF-3

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Serial thonber 1918

=n THIS PAGE Pf!0EDED REACTOR COOLANT STS*EM S AFETT VALVES - SEUT'JOVN LIMITING CONDITION FOR OPERATION

'3.4.2 Decay Best Removal Systes relief valve 08-4849 shall be OPERABLE vith a l lift setting of 1330 psig* and isolation valves 08-11 and DB-12 open and

!' control pover to their valve operators removed.

'!APPLICA3ILI*T:

MODES 4 and 1.

I CIIONt

,1

lA.

Vith DB 4849 not OPERABLE:

ll l

1.

Make the valve OPERABLE vitbin eight hours or ll,l a.

Vithin next one hour, disable the capability of both high pressure injection (HPI) pumps to inject vater into the reactor coolant l

systems and I

i b.

Vithit.1ax t eight hours:

I 1.

Disable the automatic transfer of makeup pump suction to the borated vater storage tari on lov makeup tank levels and l

2.

Reduce makeup tank level to f 73 inches and reduce reactor coolant system pressure and pressurizer 1 vel within the j

acceptable region on Figures 3.4-2a (in n0DE 4) and 3.4-2b l

(in MODE 5).

!'l.

Vith DJ-11 or 08-12 closed, open DH-21 and D8-23 vithin one hour.

B I

lC.

Vith the control power not removed from DE-.11 and DE-12, remove the power to the valve operators at the Motor Control Canters within one hour.

{ SURVIIL'E CE REQUIREMENTS 4.4.2 Decay Heat Removal System relief valve DB-4849 shall be determined OPERABLE:

a.

per the surveillance requireaants of Specification 4.0.5.

b.

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 verifying either:

1.

isolation valves DB-11 and DH-12 open with control power removed from threir valve operators: or 2.

valves DB-21 and 08-23 open i*

The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.

DAVIS-BESSE, UNIT 1 3/4 a-3 Amendment No. 37,J3f 135

Docket flumber 50-346 License Number NPF-3 L

Serial Number 1918 Attachment l

' ~ '"

FOR WORK 3N DN 4.3

'NSTRUMENTATION

!ASES

'4. 3.1 ano 3/4. 3.

?EAC" R FROTIO"'ON SYSTEM AND S ATI-* !!!*EM lMSTRUMENTATICH The OPERARII.!TT of the EPS. STAS anc STRCS instrumentation systems ensure that

• ) the associated action ana/or trip vill be initiateo vnen the parameter tonitorea by esca c.nannel or co'scination thereof exceecs its setpoint. :) the specified coincidence logic is maintained. 3) sufficient renunaancy is

?.aintained to permit a enannel to be out of service for testing or t.aln t anance, and 4) sufficient system functional capso111ty is available for RPS. STAS and STRCS purposes tres diverse parameters.

The OPERABILI T of these systems is reautrea to provice tne overall reliacility, renuncance ano diversity assuaea available in tne f acility design f or tne protection ans antigation of accident and transient concitions.

The l

integrated operation of eacn of these systems is consistent vith tne assumptions used in tne accident analyses.

i The surveillance requirements specified for these systems ensure that the i

overall system functional capability is maintained comparacle to the original I.

design standards. The periodic surveillance tests perforneo at the minimum

, ' ' f requencies are suf ficient to demonstrate this capability.

l The measurement of response time at the specified frecuencies orovides l

assurance that the RPS. ITAS, and STRCS action function associated with each enannel is completed within the time limit assumed in the safety analyses.

No

recit vas taken in tne analyses for those channels vita resconse times

ndicates as not applicaole.

Eesoonse time may oe oesonstrated by any series of secuential. overlapping or total channel test mes.surements provided that such tests comonstrate the total enannel response time as definee.

Sensor response time verification any be cemonstrated by either 1) in place, onsite or of fsite test measurements or 2) utilizing replacement sensors vith certified response ti es.

i l

An STRCS channel consists of 1) the sensing device (s). :) associated logic and output relays (including Isolation of Main Feeovater Hon Essential Valves and Turbine Trip), and 3) power sources.

The STRCS response time for the tureine stop valve closure as caseo on the

,l conoined response times of =ain steam line low pressure sensors. logic cabinet

.j delay for main steam line low pressure signals and closure t1:e of the turbine

'{

stop valves.

This STRCS response time ensuresthat the auxiliar/ f eeovater to the unaf f ected steam generator vill not be isolateo due to a STRCS lov pressure trip during a atn steam line breax accident.

CAVIS-BESSE. 1: NIT 1 S 3i4 3-1 e.senoment No. 73.125

( %s t eage is B 3/4 3-la)

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