ML20078E970

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Proposed Tech Specs,Eliminating Selected Response Time Testing Requirements
ML20078E970
Person / Time
Site: Clinton Constellation icon.png
Issue date: 01/27/1995
From:
ILLINOIS POWER CO.
To:
Shared Package
ML20078E965 List:
References
NUDOCS 9502010226
Download: ML20078E970 (18)
v • d • e


Text

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Attachment 3 to U-602376

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Attached Marked-Up Pages of the Technical Specifications I

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9502010226 950127 PDR ADOCK 05000461 P PDR

Attachment 3 to U-602376 c/ .

ts.94_oo3 Page 2 of 8 RPS Instrumentation 3.3.1.1 L- ,

SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY

.SR 3.3.1.1.16 Verify Turbine Stop Valve Closure and 18 months Turbine Control Valve Fast closure Trip 011 Pressure-Low Functions are not bypassed when THERMAL POWER is 2: 40% RTP.

SR 3.3.1.1.17 ------------------NOTES------------------

1. Neutron detectors are excluded.

I,2. Gf Ed O ^5

  • 3f. The STAGGERED TEST BASIS Frequency 4,ond 5
  • nTee for each Function shall be determined 3,3,g ,g.1, ge, on a per channel basis.

3 L "6 W 'd Verify the RPS RESPONSE TIME is within limits.

18 months on a STAGGERED TEST BASIS s

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i CLINTON 3.3-6 Amendment No. 95

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Attcchmentt3 to U-602376

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Page 3cf8 -

- ECCS Instrumentation 3.3.S.1 SURVEILLANCE REQUIREMENTS

......------------------------.----.-NOTES------------------------------------

1. Refer to Table 3.3.5.1-1 to determine which SRs apply for each ECCS .

function.

2. When a channel is placed in an inoperable status solely for performance of l required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Functions 3.c, 3.f, 3.g, and 3.h; and (b) for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Functions other than 3.c, 3.f, 3.g, and 3.h, provided the associated Function or the redundant Function maintains ECCS initiation capability.

SURVEILLANCE FREQUENCY

' SR 3.3.5.1.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.5.1.2 Perform CHANNEL FUNCTIONAL TEST. . 92 days SR 3.3.5.1.3 Calibrate the analog trip module. 92 days SR 3.3.5.1.4 Perform CHANNEL CALIBRATION. 18 months

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SR 3.3.5.1.5 Perform LOGIC SYSTEM FUNCTIONAL TEST. 18 months y r x 7

(f '3.3 .1.6 - - - - - - - - - - - - - -/- - NOT E - - - - - - - - - - - - 'd- -

The AGGER 4EST BASI requency hall j/

determi d on a p channel ba s for each EC trip sys ms.

..... .......... ........... ........ .. ,i

/' Verify the E S RESPONS IME is w hin 1 months na i limits. ,/ /$ TAGGER

/ BASIS TEST p ,

CLINTON 3.3-38 Amendment No. 95

l Attcchment 3 to U-602376 i LS-94-003

. Paga 4 cf 8 ECCS Instrumentation-3.3.5.1 Tabte 3.3.5.1-1 (pase 1 of 5) -

Emergency Core Cooling system Instrumentation j 1

APPLICABLE COWOITIONS MODES OR- REFERENCED OTNER REQUIRED FROM sPECIFIED CHANNELS PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS f1JetCT10N ACT100f A.1 REQUIREMENTS VALUE l

1. Low Pressure Cootent Injection-A (LPCI) and Low Pressure Core spray (LPCS) sdesystems
a. Reactor vesset Water 1,2,3, 2(b) 8 st 3.3.5.1.1 2 -147.7 Level-Low Low Low, st 3.3.5.1.2 Inches Levet 1 4("I,5(*I st 3.3.5.1.3 st 3.3.5.1.4 st 33.5.'5 Qs5V V5FAA
b. Drywett Pressure-High '1,2,3 2(b) B st 3.3.5.I.1 5 1.68 psis SR 3.3.5.1.2 e st 3.3.5.1.3 st 3.3.5.1.4 st 3.3.5.1.5 l l rsst 4,r.u u I
c. LPCI Pusp A ' 1,2,3, 1 C st 3.3.5.1.2 t 4.5 seconds start-Time Detey sR 3.3.5.1.4 and Logic card 4(a) ,5(a) st 3.3.5.1.5 5 5.5 seconds
d. Reactor Yesset 1,2,3 4 C

! st 3.3.5.1.1 t 452 psig

\

Pressure - Low st 3.3.5.1.2 and (InJaction Permissive) st 3.3.5.1.3 s %78 psis st 3.3.5.1.4  !

st 3.3.5.1.5 4(a) ,$(a) 4 s st 3.3.5.1.1 a 452 psis st 3.3.5.1.2 and . .

st 3J.5.1.3 5 478 psis st 3.3.5.1.4 st 3J.5.1.5

e. LPCs Pump Discharge 1,2,3, 1 E st 3.3.5.1.1 t 750 spa l Flow-Low (sypass) st 3.3.5.1.2 '

4(*I,5("I st 3.3.5.1.3 st 3.3.5.1.4 st 3.3.5.1.5

f. LPCI Pusp A Discharge 1,2,3, , 1 E st 3J.5.1.1 t 900 spa Flow-Low (sypass) st 3.3.5.1.2 i 4(*I,5(*) st 3.3.5.1.3 j st 3.3.5.1.4 -

st 3.3.5.1.5

s. tianual Initiation 1,2,3, 1 C st 3.3.5.1.5 NA 4(a) ,5(a)

(continued)

(a) When associated subsystem (s) are required to be CPERABLE.

(b) Also required to initiate the associated dieset generater.

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I CLINTON 3.3-39 Amendment No. 95 l

Attcchment 3 to U-602376

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Page 5 of 8

  • ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 2 of 5) .

Emergency Core Cooling System Instruuntation APPLICABLE CDICITIONs ,

MODES OR REFEBENCED CINER REQUIRED FROM sPECIFIED CRANNEls PER REQUltED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTIOtt A.1 REQUltEMENTs VALUE

2. LPCI s and LPCI C sthsystems
a. Reactor vesset Vater 1,2,3, 2(b) s st 3.3.5.1.1 t -147.7 Levet -Low Low Low, st 3.3.5.1.2 inches  !

Levet 1 4(*),5(*) st 3.3.5.1.3 -

st 3.3.5.1.4 st 3.3.5.1.5_ l m M.FG

b. Drywett Pressure-Nigh 1,2,3 2(b) s set 3.3.5.1.1 s 1.88 psis st 3.3.5.1.2 st 3.3.5.1.3 st 3.3.5.1.4

, 14 3.3.511.5_

t,w i a.y.2pTW)

c. LPCI' Pump a. 1,2,3, 1 C 'st 3.3.5.1.2 t 4.5 seconds start-Tlee Detey st 3.3.5.1.4 and Logle Card 4(*),5(*) st 3.3.5.1.5 s 5.5 seconds
d. Reactor vesset 1,2,3 4 C st 3.3.5.1.1 t 452 pelg Pressure -Low st 3.3.5.1.2 and (Injection Permissive)  ! st 3.3.5.1.3 5 478 pils st 3.3.5.1.4

/ st 3.3.5.1.5 4(*),5(*) 4 s st 3.3.5.1.1 t 452 psig, .

st 3.3.5.1.2 and SR 3.3.5.1.3 5 478 pels st 3.3.5.1.4 st 3.3.5.1.5

e. LPCI Pimp 8 and I.PCI 1,2,3, 1 per p ap E , st 3.3.5.1.1 t 900 spa i Ptap C Disdarse $t 3.3.5.1.2 l Flow-Low (Bypass) 4(*),5(*) st 3.3.5.1.3 st 3.3.5.1.4 i st 3.3.5.14  ;
f. Manuel Initiation 1,2,3, 1 C. st 3.3.5.1.5 NA )

, 4(a),5(a)

\.

. (continued)

(a) When associated otheystem(s) are required to be OPERAsLE.

(b) Also rewired to initiate the associated dieset generator.

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CLINTON 3.3-40 . Amendment No. 95 1

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Attachment 3 to U-602376

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' PacJe 6 of 8 E.CCS Instrum:ntatien 3.3.5.1 Table 3.3.5.1-1 (page 3 of 5)

  • Emergency Core Cooting system Instrtsnentation APPLICABLE CONDIT10Ns MODES OR REFERENCED OTHER REQUIRED FROM

. SPECIFIED CNANNELS PER REQUIRED SURVEILLANCE ALLOWA8LE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE

3. Nigh Pressure Core spray (HPCs) system
a. Reactor vesset 1,2,3, 4(b) s st 3.3.5.1.1 E -47.7 inches Water Level-Low SR 3.3.5.1.2 Low, Level 2 4(*I,5(*) SR 3.3.5;1.3 SR 3.3.5.1.4 st 3.3.5.1.5_ g (stJabap) l
b. orywett 1,2,3 4(b) , sg 3,3,$,g,g g g,gg p g, Pressure - High SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3 1 1.5 (PC' ka.4AfD
c. Reactor vesset 1,'2,3, 2 C st 3.3.5.1.1 5 54.2 inches 64ter SR 3.3.5.1.2 Levet - Nigh, 4(a), 5(*) sR 3.3.5.1.3 Levet 8 SR 3.3.5.1.4 SR 3.3.5.1.5
d. RCIC storage Tank 1,2,3, 2 0 st 3.3.5.1.1 a o inches Levet - Low SR 3.3.5.1.2 4(c) ,5(C) ,,- st 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 l
e. sqpression Poot 1,2,3 2 0 st :3.3.5.1.1 5 12 Inches Water Levet -Nigh SR 3.3.5.1.2 st 3.3.5.1.3 st 3.3.5.1.4 ]

SR 3.3.5.1.5 1

f. NPCs Pump 1,2,3, 1 E st 3.3.5.1.1 t 120 psis I Discharge SR 3.3.5.1.2 l Pressure - High 4(a), 5(*) SR 3.3.5.1.3 (Bypass) st 3.3.5.1.4 SR 3.3.5.1.5
s. HPCs system Flow" 1,2,3,* 1 E st 3.3.5.1.1 t 500 spa i Rete - Low SR 3.3.5.1.2 l 4(*I,5(*) \

(typass) st 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5

h. Manual Initiation 1,2,3, 1 C SR 3.3.5.1.5 NA 4(a),5(a)

(continued)

(a) %Aten associated stasystem(s) are required to be OPERABLE.

(b) Also required to initiate the associated dieset generator.

(c) When NPCs is OPERABLE for compliance with LCo 3.5.2, "ECCs - Shutdown," and aligned to the RCIC storage .

I tank white tank water levet is not within the timits of SR 3.5.2.2.

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l CLINTON 3.3-41 Amendment No. 95

Attachmant 3_to U-602376 LS-94-003 l

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Page'7 of 8 l

.-Primary Containment and Drywell Isolatlon Instrumentation T 3.3.6.1 l SURVEILLANCE REQUIREMENTS f:

...............................-------NOTES------------------------------------ '

1. Refer to Table 3.3.6.1-1 to determine which SRs apply for each Primary l Containment and Drywell Isolation Function.
2. When a channel is placed in an inoperable status solely for perfomance of required Surveillances, entry into associated Conditions and Required j Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, provided the associated Function maintains isolation capability.  ;

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SURVEILLANCE FREQUENCY i

SR 3.3.6.1.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> i

SR 3.3.6.1.2 Perform CHANNEL FUNCTIONAL TEST. 92 days 4

i SR 3.3.6.1.3 Calibrate the analog trip modu 1I. 92 days s t

SR 3.3'6.1.4

. Perform CHANNEL CALIBRATION. 92 days i

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SR 3.3.6.1.5 Perform CHANNEL CALIBRATION. 18 months l s

SR 3.3.6.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST. 18 months l

SR 3.3.6.1.7 ------------------NOTES------------------ t r d,TheSTAGGEREDTESTBASISFrequencyfor l 1

I. C6nel sw each Function shall be determined on a 5.5"""..$$I........................

Verify the ISOLATION SYSTEM RESPONSE TIME 18 months on a for the main steam isolation valves is STAGGERED TEST within limits. BASIS I

3.3-54 Amendment No. 95  ;

CLINTON i

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  • Page BE b-Operating -

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3.5.1 i

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! )' SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY I

SR 3.5.1.5- -------------------NOTE--------------------

i Vessel injection / spray may be excluded.

Verify each ECCS injection / spray subsystem 18 months actuates on an actual or simulated automatic initiation signal.  ;

SR 3.5.1.6 -------------------NOTE--------------------

Valve actuation may be excluded.

Verify the ADS actuates on an actual or 18 months.

simulated automatic initiation signal.

SR 3.5.1.7 -------------------NOTE--------------------

Not required to be performed untti 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> i after reactor steam pressure and flow are -

adequate to perform the test.

Verify each ADS valve opens when manually 18 months on a actuated. STAGGERED TEST BASIS for each valve solenoid

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Q 3.5 ),$ . .

_ . NO TE '

Eccs ach&n i74wvroeM00 Cidad

.____ e& _

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,@c the. ECCs Ac4Fbe T/M6 Soc & 6CCS \tQCcVonlGP%

sobr.ptem if w % in U m 'h . 1 CLINTON 3.5-5 Amendment No. 95 l 1

l

Attachment 4 l to U-602376 l LS-94-003 Page 1 of 10 l

Attached Marked-Up Pages of the Technical Specifications Bases i

Attachmsnt 4 to U-602376

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LS-94-003 Page 2 of 10  ;

RPS Instrumentation i B 3.3.1.1 BASES

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i SURVEILLANCE SR 3.3.1.1.16 REQUIREMENTS (continued) This SR ensures that scrams initiated from the Turbine Stop Valve Closure and Turbine Control Valve Fast Closure, Trip 011 Pressure-Low Functions will not be inadvertently bypassed when THERMAL POWER is k 40% RTP. This involves '

calibration of the bypass channels. Adequate margins for the instrument setpoint methodology are incorporated into  :

the actual setpoint. Because main turbine bypass flow can affect this setpoint nonconservatively (THERMAL POWER is derhad from turbine first stage pressure), the main turbine bypau valves must remain closed at THERMAL POWER h 40% RTP .

to ensure that the calibration remains valid.  ;

If any bypass channel setpoint is nonconservative (i.e., the Functions are bypassed at h 40% RTP, either due to open main i

turbine bypass valve (s) or other reasons), then the affected '

Turbine Stop Valve Closure and Turbine Control Valve Fast -

Closure, Trip 011 Pressure-Low Functions are considered inoperable. Alternatively, the bypass channel can be placed in the conservative condition (nonbypass). If placed in the r nonbypass condition, this SR is met and the channel is considered OPERACLE. j I To d'T#% The Frequency of 18 months is based on engisiecring . judgment i 1

Fu m R O M 3.84. e d and reliability of the components. -

C, w e m .soe w el  !

t yes cere not SR 3.3.1.1.17 H ol(ed % be. l This SR ensures that the individual channel response times i U'6P g % e are less than or equal to the maximum values assumed in the  !

te6teS. b h accident analysis. The RPS RESPONSE TIME acceptance behW6 fesWWC criteria are included in plant Surveillance procedures.

Hrre ted'nj k -

As noted, neutron detectors are excluded from RPS RESPONSE Waln s oj TIME testing because the principles of detector operation i

%gq virtuallyensureaninstantaneousresponsetime.ft in d RPS RESPONSE TIME tests ar conducted on an 18 month STAGGERED TEST BASIS. G$.e/ofSR 3.3.1.1.17 requires l l p)

  • 6 reg olfd. STAGGERED TEST BASIS Frequency for each Function to be M 08## detemined separately based on the four channels as M SvP%ek / specified in Table 3.3.1.1-1. This Frequency is based on i R j the logic interrelationships of the various channels  ;

C eQegeoce 10.

  1. required to produce an RPS scram signal. ,

, (continued) i l

CLINTON B 3.3-29 Revisica No. 0 ,

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I Attachment 4 to U-602376  ;

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  • LS-94-003 l

- Pag 3}nSfrumkatation' f 8 3.3.1.1 i i

BASES SURVEILLANCE SR 3.3.1.1.17 (continued)

REQUIREMENTS Therefore, staggered testing results in response time verification of these devices every 18 months. This frequency is consistent with the typical industry refueling cycle and is based upon plant operating experience, which .

shows that random failures of instrumentation components I causing serious time degradation, but not channel failure,  !

are infrequent.

REFERENCES 1. USAR, Section' 7.2, l i

2. USAR, Section 5.2.2.
3. USAR, Section 6.3.3.
4. USAR, Chapter 15.
5. USAR, Section 15.4.1.2.
6. NED0-23842, " Continuous Control Rod Withdrawal in the Startup Range," April 18, 1978. l
7. USAR, Section 15.4.9.
8. Letter, P. Check (NRC) to G. Lainas (NRC), "BWR Scram  !

Discharge System Safety Evaluation," December 1,1980, as attached to NRC Generic Letter dated December 9, 1980.

NED0-30851-P4, " Technical Specification Improvement l 9.

Analyses for BWR Reactor Protection System,"

,. March 1988. )

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NI:t -31241- R," ggg, 4 ,gg g[gg,.m,upn ] I 4 MdCd lespovyfrc T'mc Tesb'g "Rqulvementg" l

Janvu3 R%.

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I Cf..INTON B 3.3-30 Revision No. 0

', LS-94-003 o

T[85InSkrumentation f B 3.3.5.1 l

' i BASES t

SURVEILLANCE SR 3.3.5.1.5 (continued) ,

l REQUIREMENTS Frequency. The frequencies recommended by the manufacturer l are based on mean time between failure analysis for the -

components in the associated circuits.-

The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for unplanned transients if the Surveillance were performed with the reactor at power.

0)erating experience has shown these components.usually pass tie Surveillance when performed at the 18 month Frequency. ,

SR 3 . 3 . 5 . 1 . 15 This SR ensur that the indivi 1 channel response times are less th or equal to the ximum values assume n the  :

accident alysis. Respons ire testing'accepta e i

criteri are included in ference' 5.

ECC RESPONSE TIME te s are conducted on 18 month 5 GGERED TEST BASI . This Frequency is nsistent with the ypical industry fueling cycle and is ased upon plant operating exper nee, which shows tha random failures of instrumentati components causing rious response time degradation but not channel fail e, are infrequent.

This SR s modified by a Note hat requires the STAGGE TEST SIS Frequency for ea Function in each trip stem determined separate based on the number of edundant  !

to c nnels for that Funct n specified on Table 3. 5.1-1.

Ttis Frequency is bas on the logic interrela onships of l the various channels required to produce an E Sinitiation) i (signal. J REFERENCES 1. USAR, Section 5.2.2.  ;

2. USAR, Section 6.3. ,
3. USAR, Chapter 15.

(continued) a CLINTON B 3.3-121 Revision No. O i

7 - wp -.-m-*- , . . . , - - -,

-.-m.-- . - - - _ - - _ _ - - - -- - - -

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Attechment 4 to U-602376

LS-94-003

- Page 5 of 10 ECCS Instrementation B 3.3.5.1 O1 BASES REFERENCES 4. NEDC-30936-P-A, "BWR Owners' Group Technical (continued) Specification Improvement Analyses for ECCS Actuation

- Instrumentation, Part 2," December 1988.

S s ection/.3, Table /.3-8}

USAR,j i

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I CLINTON B 3.3-122 Revision No. O  !

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  • Attachment 4 to U-602.$76 LS-94-003 Page 6 of 10 Primary Containment and Drywell Isolation Instrumentation 8 3.3.6.1 BASES 1

SURVEILLANCE SR 3.3.6.1._4 and SR 3.3.6.1.5 (continued) adjusted to account for instrument drifts between successive calibrations consistent with the plant specific setpoint >

methodo1'ogy.  ;

The Frequency of SR 3.3.6.1.4 and SR 3.3.6.1.6 is based on ,

i the assumption of the magnitude of equipment drift in the setpoint ana1ysis.

SR 3.3.6.1.6 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required isolation logic for a specific channel. The system functional testing performed on PCIVs in LC0 3.6.1.3 and on drywell isolation valves in LCO 3.6.5.3 overlaps this Surveillance to provide complete testing of the assumed safety function. The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power. Operating experience has shown these components usually pass the Surveillance when performed at the 18 month Frequency.

The Self Test System may be utilized to perform this testwg for those com>onents that it is designed to monitor. Those portions of tie solid-state logic not monitored by the Self Test System may be tested at the frequency recommered by.

the manufacturer, rather than at the specified 18-month Frequency. The frequencies recommended by the manufacturer are based on mean time between failure analysis for the components in the associated circuits...

SR 3.3.6.I.7 This SR ensures that the individual channel response times are less than or equal to the maximum values assumed in the accident analysis. Testing is performed only on channels where the assumed response time doas not correspond to the diesel generator (DG) start time. For channels assumed to respond within the DG start time, sufficient margin exists in the 12 second start time when compared to the typical channel response time (milliseconds) so as to assure The adequate response without a specific measurement test.

(continued)

B 3.3-172 Revision No. O CLINTON

  • Attachment 4 to U-6023/b

- LS-94-003

REQUIREMENTS instrument response times must be added to the MSIV closure r b d "k M times to obtain the ISOLATION SYSTEM RESPONSE TIME.

ISOLATION SYSTfM RESPONSE TIME acceptance criteria are OsSoc M ed S N M osy t n o t (ctj' V fe A included applicable plant procedures.

% bc O'6PWM .%e Note SR 3.3.6.1;7 requires the STAGGERED TEST BASIS gg M UC[g

' gg fernairo%

Frequency for each function to be determined seperately based on the number of channels as specified on Table n$ q# 3.3.6.1-1. This frequency is based on the logic interrelationships of the various channels required to Mnnel Cornfneni$> produce an isolation signal.

incl @ @ n c

)S Y ISOLATION SYSTEM RESPONSE TIME tests are conducted on an Th M M 9990' 18 month STAGGERED TEST BASIS. This Frequency is consistent with the typical industry refueling cycle and is based upon i N geQvecce 7.

i plant operating experience that shows that random failures of instrumentation components causing serious response time i degradation, but not channel failure, are infrequent.

REFERENCES 1. USAR, Section 6.2. I

2. USAR, Chapter 15.
3. NED0-31466, " Technical Specification Screening Criteria Application and Risk f.ssessment,"

November 1987.

4. USAR, Section 9.3.5.
5. NEDC-31677-P-A, " Technical Specification Improvement Analysis for BWR Isolation Actuation Instrumentation,"

June 1989.

6. NEDC-30851-P-A, Supplement 2, " Technical Specifications Improvement Analysis for BWR Isolation Instrumentation Common to RPS and ECCS Instrun ntation," March 1989.

/

, NEbo - 32251- Y Sgpem And tes' 4 Ellmitvfo g

c4 Seieded Response,he. Test $ %o1(ements," l

( Janmq 1"4 J CLINTON B 3.3-173 Revision No. O  ;

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. .. -- .- . - -- . - - . . ~,. - . = . - .- ..

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Attachmer.t 4 to U-602376

. , LS-94g0gj 10 y,, Page ECCS-Operating .

  • B 3.5.1 J v

BASES SURVEILLANCE SR 3.5.1.7 (continued) .

REQUIREMENTS performing this test because valve OPERABILITY and the setpoints for overpressurc protection are verified, per ASME j requirements, prior to valve installation. Therefore, this  ;

SR is modified by a Note that states the Surveillance is not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam j pressure and flow are adequate to perform the test.

SR 3.5.1.6 and the LOGIC SYSTEM FUNCTIONAL TEST performed in .

LCO 3.3.5.1 overlap this Surveillance to provide complete  :'

testing of the assumed safety function. .

The Frequency of 18 months on a STAGGERED TEST BASIS ensures '

that both solenoids for each ADS valve are alternately tested. The Frequency is based on the need to perform this i Surveillance under the conditions that apply just prior to or during a startup from a plant outage and the potential ,

for unplanned transients. Operating experience has shown  :

, that these components usually pass the SR when performed at the 18 month Frequency, which is based on the refueling ,

1

-I cycle. Therefore, the Frequency was concluded to be l

{7g3 g[

acceptable from a reliability standpoint. l l

REFERENCES 1. USAR, Section 6.3.2.2.3.

2. USAR, Section 6.3.2.2.4. .
3. USAR, Section 6.3.2.2.1.
4. USAR, Section 6.3.2.2.2.
5. USAR, Section 15.2.8. i
6. USAR, Section 15.6.4.
7. USAR, Section 15.6.5. i
8. 10 CFR 50, Appendix K.
9. USAR, Section 6.3.3.
10. 10 CFR 50.46.
11. USAR, Section 6.3.3.3.

(continued)

CLINTON B 3.5-13 Revision No. 0

_ _ _ ._ _ ._ _ . - _ _ . _ . , _ ,_ _ . _ , , _ _ _ _ l

Attachment 4 to U-602376 ,

... . LS-94-003

, Page 9 of 10 t

INSERT B13-  !

SR 3.5.1.8  ;

i This.SR ensures that the ECCS RESPONSE TIMES are within limits for each of the ECCS injection and spray subsystems. This SR is modified by a note which identifies that the associated ECCS  !

actuation instrumentation is not required to be response time tested. Response time testing of the remaining subsystem components is required. This is supported by Reference 15.  !'

Response time testing acceptance criteria are included in Reference 13. l ECCS RESPONSE TIME tests are conducted every 18 months. The i 18 month Frequency is based on the need to perform this l Surveillance under the conditions that apply during a plant  !

outage and the potential for an unplanned transient if the i Surveillance were performed with the reactor at power. Operating experience has shown that these components usually pass the SR  ;

when performed at the 18 month Frequency, which is based on the

  • refueling cycle. Therefore, the Frequency was concluded to be acceptable from a reliability standpoint.

+

i k

1 e

i F

5

'i t

5 i

l Tc6egr CLmwr3 8 35 - ss .  % ;ge,o yo,\

  • Attachment 4 to U-602S/b

..* LS-94-003

- Page 10 of 10

.' .- ECCS-Operating i B 3.5.1 ,

.q BASES -y REFERENCES 12. Memorandum from R.L. Baer (NRC) to V. Stello, Jr.

(continued) (NRC), " Recommended Interim Revisions to LCO's for ~

ECCS Components," December 1, 1975.

I

13. USAR, Table 6.3-2.

l

14. USAR, Section 7.3.1.1.1.4.  !
15. NEbo - 32291 - A, " systtm bly6es %< M; mhd'd  ;

of SeAeckeA Tesponse Tme.Tesug Requiremt ..

r L ua .3 r W l. U CLINTON B 3.5-14 Revision No. 0 1

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