ML20148U535
ML20148U535 | |
Person / Time | |
---|---|
Site: | Duane Arnold |
Issue date: | 06/30/1997 |
From: | Kelly G NRC (Affiliation Not Assigned) |
To: | NRC (Affiliation Not Assigned) |
References | |
TAC-M97157, NUDOCS 9707100208 | |
Download: ML20148U535 (39) | |
Text
__ .. . -- . . .. .- ..
w, L
June 30,1997 l
LICENSEE: IES Utilities Inc.
FACILITY: Duane Arnold Energy Center
SUBJECT:
SUMMARY
OF JUNE'I8, 1997, MEETING ON LOOP SELECT LOGIC (TAC NO. M97157)
On June 18, 1997, a public meeting was held between the U.S. Nuclear Regulatory Commission staff and IES Utilities Inc. (the licensee) to discuss the unique aspectp of the Duane Arnold Energy Center's design with regard to
- loop select logic . Enclosure 1 is a list of attendees. The handouts provided by the licensee in the meeting are Enclosures 2, 3, and 4.
During the meeting, the licensee discussed the residual heat removal system '
design, success criteria for design basis loss-of-coolant accidents, low-pressure coolant injection loop select logic (including time delays), and the improved Technical Specification submittal with respect to the loop select logic.
Original signed by:
Glenn B. Kelly, Sr. Project Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation j Docket No. 50-331
Enclosures:
As stated -
See next page cc w/encls: '( !
Distribution w/encls: E-Mail w/ Encl 1 only:
Docket File SCollins/FMiraglia ETomlinson (EBT)
PUBLIC RZimmerman (RPZ) CSchulten (CSSI)
PD3-3 R/F Jiloe -(JWR) NGilles (NVG)
OGC EAdensam (EGA1) TTjader (TRT)
ACRS GMarcus (GHM): MJordan (MJJ)
GKelly . Dross (SLM3) JStrasma (RJS2)
GGrant, RIII BMcCabe (BCM) JDavis (JAD) llll111llllllllllllllllllllllllIl
- '=^'
DOCUMENT NAME: G:\DUANEARN\DUA97157.MTS 0FFICE LA:PDI!!-3 / l/U PM:PDill-3 N ;
NAME CBoyle & D GKelly / M MF ^
DATE (p* QJ/97 ( f/}]/97 h 7
- ;d 'd 0FFICIAL RECORD COPY .
9707100208 970630 1 PDR ADOCK 05000331 P PDR
' Loop select logic.- logic that chooses the loop of the recirculation '
system (1 of <2) into which to pump ECCS water from the residual heat removal system in such a manner that it does not bypass cooling the core.
1 i .
I Oune 30, 1997 1 i LICENSEE: IES Utilities Inc.
f.
I FACILITY: Duane Arnold Energy Center f
SUBJECT:
SUmiARY OF JUNE'18, 1997, MEETING ON LOOP SELECT LOGIC j (TAC NO. M97157) j On June 18,.1997, a public meeting was held between the U.S. Nuclear l
Regulatory Commission staff and IES Utilities Inc. (the licensee) to discuss the unique aspect { of the Duane Arnold Energy Center's design with regard to
- loop select logic . Enclosure 1 is a list of attendees. The handouts i provided by the licensee in the meeting are Enclosures 2, 3, and 4.
i During the meeting, the licensee discussed the residual heat removal system design, success criteria for design basis loss-of-coolant accidents, low-pressure coolant injection loop select logic (including time delays), and the improved Technical Specification submittal with respect to the loop select logic.
Original signed by:
Glenn B. Kelly, Sr. Project Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket No. 50-331
Enclosures:
.As stated cc w/encls: See next page Distribution w/encls: E-Mail w/ Enc 1 1 oniv:
Docket File SCollins/FMiraglia ETomlinson (EBT)
PUBLIC RZimmerman (RPZ) CSchulten (CSSI)
PD3-3 R/F JRoe (JWR) NGilles (NVG)
OGC EAdensam (EGA1) TTjader (TRT)
ACRS GMarcus (GHM) MJordan (HJJ)
GKelly Dross (SLM3) JStrassa (RJS2)
GGrant, RIII BMcCabe (BCM) JDavis (JAD)
DOCUMENT NAME: G:\DUANEARN\DUA97157.MTS OFFICE LA:PD!II 3 j l A/ PM:PDlll*3 /V bl4ME CloyLe & 4 GKeily /sGJL DATE & O f97 ( f/ly91 0FFICIAL RECORD COPY
' Loop select logic - logic that chooses the loop of the recirculation system (1 of 2) into which to pump ECCS water from the residual heat removal system in such a manner that it does not bypass cooling the core.
s
p uru
- t UNITED STATES !
- r g NUCLEAR REGULATORY COMMISSION l 2 WASHINGTON, D.C. enana mi 4
'+ ,* * * * * ,o June 30, 1997 i
LICENSEE: IES Utilities Inc. l 1
FACILITY: Duane Arnold Energy Center
SUBJECT:
SUMMARY
OF JUNE 18, 1997, MEETING ON LOOP SELECT LOGIC (TAC NO. M97157) j On June 18, 1997, a public meeting was held between the U.S. Nuclear i
i Regulatory Commission staff and IES Utilities Inc. (the licensee) to discuss the unique aspects,of the Duane Arnold Energy Center's design with regard to loop select logic. Enclosure 1 is a list of attendees. The handouts provided by the licensee in the meeting are Enclosures 2, 3, and 4.
During the meeting, the licensee discussed the residual heat removal system
- design, success criteria for design basis loss-of-coolant accidents, low-pressure coolant injection loop select logic (including time delays), and the improved Technical Specification submittal with respect to the loop select l logic. '
/
/W
/
Glenn B. 11y, Sr. Pr 'ect Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket No. 50-331 l
Enclosures:
As stated cc w/encls: See next page l
i
.i 1
' Loop select logic - logic that chooses the loop of the recirculation system (1 of 2) into which to pump ECCS water from the residual heat removal system in such a manner that it does not bypass cooling the core.
I
l 1
i Duane Arnold Energy Center
, IES Utilities Inc.
, cc:
Jack Newman, Esquire Kathleen H. Shea, Esquire Morgan, Lewis, & Bockius ~
. 1800 M Street, NW.
j Washington, DC 20036-5869 Chairman, Linn County
- . Board of Supervisors
- Cedar Rapids, IA 52406
} IES Utilities Inc. -
! ATTN: Gary Van Middlesworth l Plant Superintendent, Nuclear ,
i Vice President, Nuclear Duane Arnold Energy Center 1
! 3277 DAEC Road i
- Palo, IA 52324 l l Mr. Ken Peveler
- Manager, Nuclear Licensing l
. Duane Arnold Energy Center
- U.S. Nuclear Regulatory Commission Resident Inspector's Office Rural Route #1 Palo, IA 52324 4
! Regional Administrator U.S. NRC, Region III
- 801 Warrenville Road j Lisle, IL 60532-4531 i
Ms. Parween Baig Utilities Division Iowa Department of Commerce Lucas Office Building, 5th Floor Des Moines, IA 50319 Mr. Lee Liu Chairman of the Board and Chief Executive Officer IES Utilities Inc.
- 200 First Street, SE.
P.O. Box 351
- Cedar Rapids, IA 52406-0351 1
1
. . .- .- . . - _ ~ . . - _ - - . - - - . . - - . _ . . . - . - - = .
f
-ATTENDEES OF JUNE 18. 1997. MEETING l
Ellll l IES UTILITIES INC.
Ragg Oraanization Tony Browning IES Greg Whittier IES Glenn Kelly NRC Ed Tomlinson NRC Carl Schulten NRC T.R. Tjader NRC Nanette Gilles NRC l
I 1
i l
l ENCLOSURE I
l l RESIDUAL HEAT REMOVAL 4
r DESIGN BASIS / MODES
- - In conjunction with other ECCS
! Systems to cool the core (LPCI)
- Coolthe Containment:
a Containment Spray n Torus Cooling
- Provide Shutdown Cooling to remove shutdown decay heat i
!' - Provide Reactor and Torus draining l - Supplement Fuel Pool Cooling System 4
s ENCLOSURE 2 4
l J
i
- Major Components
- Two divisions (loops) !
= Note: One division alone
- cannot fulfill the LPCI function i due to pump capacity
> Two logics, each of which can ,
, fulfill the LPCI function 1
- Perloop:
a Two Pumps a One Heat Exchanger i > One inject line to Rx i - Crosstie line to connect the two
- loops to allow sufficient flow for LPCI (i.e. 3 of 4 pumps required)
- Special Power distribution to the valves which are necessary for j proper LPCI function:
> LPCI Inject Valves and l
n Recire Pump Discharge Valves
- Lots of valves 1
i l
- Suction from Torus
- Initiation Signals: I a Drywell Pressure High, or l
- Rx Water Level Lo-Lo-Lo
- Requires 3 of 4 pumps, so:
a LPCI Loop Select to determine which loop is broken and to inject into the non-broken loop a LPCI Swing Bus to ensure that when one division is without power, power is provided to the LPCIInject Valves, and Recirc Pump Discharge Valves from the electrical division which has power
- LPCI Inject Valves open when PJ Pressure < 450 psig LPCI Inject Valves have timers to ensure that they accomplish their functions a 5-Minute timer
> 10-Minute timer
i 4
3 .- 300.
l 9 9.
= :g g _ -_
! a, ,C.3 bh j 1r 9Ps & 2 V.3, .. .V g V.99.(d$
1r j , T-IS-41 A 8 V-19-14F ,
24 29 3 m, m 9d i - -
! ...;. 9 O g' g'- -
v e,.Q e .. ,
- , _a . . e l :q @ (de- = u s)
@g+:
.e ,
O ,M . W,,,,, ,
! = --
X.O. OX hd kg l : Ba*' -@
, o, _ .. ;
l ._._
4L 3 12 ggt 3 4 >
'l\ <
h," l\~
l
' ~
- s "
a: -
Q_ __e= q 4
- s.. a,: -e 1 IDM C fHL
<,p 4 ge w ir 9.F1 m
$ Wassed MW e r LA o ae
} n ,
i .
~
i 1
s Figure 2. LPCI Mode ofRHR System i
1
- SD-149 32 Rev.4,10/22/96
.i
'I
i LPCI LOOP SELECT (BREAK DETECTION) 4 DESIGN BASIS
- The minimum break size for which
~
Loop Selection Logic is able to detect an unbroken Recirc Loop is approximately 0.5 ft2 l
i a Any smaller break would not require LPCI i i > Any larger break is more l l easily detectable l
- Logic defaults to inject into the "B" i Recirc Loop ifit does not detect which loop is broken i
I
4 9
LPCI LOOP SELECT LPCI LOOP SELECT DESIRED ACTIONS
- Determine which Recirc Loop is i
Broken and:
a Close Non-Selected LPCI
- Loop's inject Valves Prevents injection into broken Recirc loop l > Open Selected LPCI Loop's Inject Valves l Allows injection into intact Recirc loop
- a Close Selected Recirc Loop's
)
J Pump Discharge Valve
, Prevents bypass of water backwards through Recirc 1
pump, into the core shroud?
and out of the break i - Ensure that the LPCI function
- continues to completion i
a 4
4
.o , - + . . . .
a l
4 i l Major inputs l - Initiation Signals:
- a Drywell Pressure High (2 psig) a Rx Water Level Low-Low j (119") i i > One-out-of-two twice logic )
I 1
- Selection Logic Inputs:
l d
3 Recirc Pump Running i a Recirc Loop Riser Pressure a Rx Pressure
{
1 l
i j
4 4
i I
1 _ _ _ .
l j
- INITIATION
- Drywell Pressure High (2 PSIG)
> LOCAIndicator s One-out-of-two twice logic
- Rx Water Level Low-Low (119")
l
> LOCAindicator
> 119"is above the 64" LPCI initiation Rx Water Level a One-out-of-two twice logic ,
3 f
h
i Selection Logic 1
i
- Recirc Pump Running i n Necessary to trip a recire pump if only one recirc pump
! is running
> Necessary to avoid confusing
. logic due to a running recirc 1
pump affecting Recirc Loop Riser Pressure
> One-out-of-two twice logic l
- Recirc Loop Riser Pressure
- > Necessary to determine which recirc loop is broken (i.e. the pressure in the intact loop will be higher than the pressure in the broken loop by > 1 psid)
> One-out-of-two twice logic j
i
I i
! =
Selection Logic
- Reactor Pressure < 900 psig
- > Necessary to allow a Recire i Pump to coast down (which i reduces reactor pressure)if i only one was initially running l
> Necessary to avoid confusing logic due to a single pump running affecting Recirc Loop Riser Pressure
> One-out-of-two twice logic
- Reactor Pressure < 450 psig
> Necessary to wait until Rx pressure is reduced below pressure rating of LPCI Inject Piping
> One-out-of-two twice logic 4
3 4
Selection Logic
- TIME DELAY RELAYS:
i
> 1/2 Sec (#1): 1 Delays tripping a Recirc Pump (when only one is
! initially running) less than 1/2 sec after initiation signal
! Necessary because it gives the logic a little more j time to sense that both recirc pumps are running ;
because you don't want to trip recirc pumps if you i don't have to I l
n 1/2 Sec (#2):
Delays signal to close Non-selected Loop's LPCI Inject Valves and to close Selected Loop's Recirc Pump Discharge Valves Necessary to give the logic a little more time to ensure that the Recirc Riser Pressures do detect a break n 2 Sec:
Delays looking at Recire Riser dP and initiating above 1/2 see time delay -
l Necessary to allow initial perturbations and !
momentum effects to settle l
4
- Selection Logic
- TIME DELAY RELAYS (Cont.):
m 5 Min:
Keeps Selected Loop's Outboard LPCI Inject Valve from being manually closed for 5 minutes (Note: there is an override handswitch to bypass this timer)
Necessary to ensure that Rx is flooded
- a 10 Min:
Keeps Non-selected Loop's inboard and Outboard inject Valves from being manually
- opened for 10 minutes
. Necessary to ensure Rx is flooded i
i a
l
)
4 i
s
l Page 1 of 1 APPENDIX 1 LPCI LOOP SELECT LOGIC
~
m
- " " aE.CTOR
"'"u"'
.TER tre 2 PSG ,,y W 2-N 1& 2-TWCE nRE BOTH
- =C,RCuT,=
7 PUMP 5 RUNNING T a P .. Pse m ACROu = Ps m i++ = -- '*
vis Y
CJ LT5s*Wsn-T4 RESET tOOp SELECTION 1
$a acc'e'^
DREAK DETECTON RESET
~5*==- t m, "J541 ,m "JlgL7 E =P so==
m.m .m,_ TO =C=CuteN STAsuZATON PUWPS
.te ,N e-~0T 1r
(- SE RESET AFTER 480 PSIG KERLOCK l 2 SECOND1D l gagANoits s-RE CtRCUL ATION ss Pa, pg . gpso SYSTEM RISER 2 Gips
. . ~ ,
t l 14SECOND1D l
- D k
1 NO I I I f
REACTOR PERae55 4 PRf550RE REACTOR PRES &URE jf 1I CLOSE *A*
- 450 es 0 e 460 poi 9 nna'5g4 c CLOSE T FOR t . os.a . i..'s e REORC i .8I-3-4 ** G 4 LOOD 10 WeeJTES O 9tEORC Cr$ CHARGE / Loop v ASE hY h 10 M#4ffE5 Cr$ CHARGE /
vues 1r AES o,,,, . g ,, OPEg' uoP t v=ns cu= , meTo v4WS y4 , mE ..
- A* RECIRC PUHF TRIP $ h h00' SLOCK OPEN W OPEN WD LOOP MCTION .y. ggesne Mfp " I V"48 pp inspg OLffROARD (ToftOTTLQ uueP uacTum.C cp teHJTES
,g;,g,
,,Pgp.
nuoP uuCTtoo.C e
C 01149 Page 86 of 155 Rev. 51
t 6
DUAXE ARXOLD EXERGY CE:N TER IMPROVED TECHNICAL SPECIFICATIONS I
I LPCI Loop Select Logic Changes to :SUREG-1433 l
i 1 RAB .
6/18/97 ENCLOSURE 3 l
LPCI Loop Select Logic .i
?
OVERVIEW i
+ ECCS Instrumentation (ITS 3.3.5.1)
+ Recirculation Loops Operating (ITS 3.4.1)
+ ECCS - Operating (ITS 3.5.1) i
+ Distribution Systems - Operating (ITS 3.8.7) 1 ,
2 MB 4
6/18/97 t
DAEC ITS LPCI Loop Select Logic ,!
ECCS Instrumentation (ITS 3.3.5.1)
. Add Loop Select Logic Instruments to Table 3.3.5.1-1 i
. Add Required Action C.2 to ACTIONS for Loss of Loop Select Capability .
. Revise Required Actions and Completion Times for Conditions C.1 and E.1 to reflect " triad" of low pressure ECCS subsystems in Loop Select design 3 RAB 6/18/97
~
DAEC ITS LPCI Loop Select Logic ,
Recirculation Loons Onerating (ITS 3.4.11 I
I e Revise LCO from " matched flow" to." matched pump speeds"
- Add Condition C to ACTIONS for pump speeds not matched .
- Revise SR 3.4.1.1 to reflect pump speed mismatch criteria 4 RAB 6/18/97
DAEC ITS LPCI Loop Select Logic ,,
~
ECCS - O.neratin_e (ITS 3.5.11 . ,
. Revise Conditions to account for Loop Select design basis-
LPCI i
e Add Condition C for loss of one CS and one or two R;HR pumps (loss of room coolers) 5 MB 6/18/97 r
'l DAEC ITS i LPCI Loop Select Logic ,!
ECCS - Ooeratine (ITS 3.5.11 - cont.
I
, e Include LPCI " Swing Bus" and Reactor Recirculation valves in ITS SR 3.5.1.7 for the Simulated Automatic Actuation test l e Delete NUREG SRs 3.5.1.4 and 5 - not for Loop
- Select design (Cross-tie valve is Open & no LPCI Inverters) and SR 3.5.1.6 - included in ITS SR 3.5.1.7 and IST Program !
6 MB 6/18/97 t
4
.. ~.-- _ _ _ _ _
LPCI Loop Select Logic .
Distribution Systems - Operating (ITS 3.8.7)
. Add SR 3.8.7.2 to verify LPCI " Swing Bus" breaker coordination 1
1 7 RAB 6/18/97
= .
ECCS Instrumentation i
3.3.5.1
- Table 3.3.5.11 (pose 2 of 5)
, amorgency Care cooling system Instrsmentation t
APPLICABLE IIERITIONS l NtBER tsellRED REFitENCED
] OR OTHER CNANoELS 510N SPECIFIED Pat REEJ1 RED S EVE!LLANCE ALLOWABLE
{ PLAICTION CERSIT!DNS RadCTitEl ACTION A.1 REGU! REPENTS VALAE l
. 2. LPCI System (continued) .,
{ c. Reactor stess Does 1,2,3 4 C a 3.3.5.1.3 a 3E5.3 pois
- . Pressure - Low j (Injection Permissive) a 3.3.5.1.5 ased a m.)
at 3.3.5.1.9 pois ,,
~
4(a), 5(a) 4- B m 3.3.5.1.3 a 5 0.3 pela j
j m 3.3.5.1.8 and s W .1 st 3J.5.1.9 psis
- d. Reactor Wessel shroud 1,2,3 4 e et 3.3.5.1.1 a -40.89 Level - Low at 3.3.5.1.2 inehes at 3.3.5.1.4 i
st 3.3.5.1.9 i e. Low Pressure cootent 1,2,3, 1 por C at 3.3.5.1.5 i
Injection Ptep pimp at 3 J.5.1.9 i start - Ties Detey 4(e),5(83 Retey l
j Pumps A & B a 4.8 seassues esel
! s 11.2 seconds -
Piegss C & D s 13.8 l essends and s n.5 l **""
! f. Low Prosaure 1,2,3, 2 E sa 3.3.5.1.3 a 471.8 spa Coolant injection Psap
- st 3.3.5.1.8 and j Discherse Flow - Low 4(a),5(e) sa 3.3.5.1.9 s 37F0.2 spe i (Bypass)
! 3 LPCI Leap select - 1,2,3 4 C a 3.3.5.1.1 a 112.65
' Reactor vessel Water at 3.3.5.1.2 inchee Level Lew-Low at 3 J.5.1.6 l st 3J.5.1.9 1
2 I
- h. LPCI Leap select - 1,2,3 4 C. m 3.3.5.1.2 a m r pois i
Reestor steen Dese at 3 J.5.1.4 Pressure - Low at 3.3J.1.9 ,'r, (eentinued)
(a) When assectated subsystee(s) are rossired to be CPsRABLE.
DAEC 3.3-43 Revision A ENCLOSURE.4..
.._...u.
. . ~ .
4' ECCS Instrumentation
- 3.3.5.1 i
i 1 Table 3.3.5.1-1 (pope 3 of 5) 4 Emergency Core Cooting Systee Instrumentatten i APPLICABLE Com!TIGus
) 9EBES OR REmilan REFERENGD i OfMER cuammsts Fagst 1 SPECIFIED PER REGUIRED REVEILLANCE ALLa mBLE j FLAICTION CEIBITIONS MalCTION ACTION A.1 REGUIRBENTS VALug 1 *.
j 2. LPCI System (eentinued) ,~'-
j f. LPCI Loop Select - 1,2,1 4 por C SR 3.3.5.1.1 s T.8 peld .i.
- tecircutetten Pe p pimp a 3.3.5.1.2 Differentist Preneure a 3.3.5.1.8 .. u 2
- a 3.3.5.1.9 " - ~ ~ '
l -
)
I J. LPCI Leap setect - 1,2,3 4 C at 3.3.5.1.1 a 0.5 paid i Recircutatien R1ser a 3.3.5.1.2 and s 2.0
- Differential Pressure sa 3.3.5.1.4 peld j N 3.3.5.1.9
- k. 4.16 kV Emergency tus 1,2,3 2 F st 3.3.5.1.5 s 3500 V 3' Seemntist Leading a 3.3.5.1.6 -
- Relay a 3.3.5.1.9 6(e),5(e) 1 F st 3.3.5.1.5 s 3500 V
{ .
a 3.3.5.1.6 ,
a 3.3.5.1.9 l i
4 3. NiWi Pressure Centent l Injection ( WCI) System 2 8
e, seector vessel Water 1, 4 e a 3.3.5.1.1 a 112.65 Level - Lou Leaf a 3.3.5.1.3 innhoe II83, 3(83 m 3.3.5.1.6 a 3.3.5.1.9 I b. DryueLL Pressure - 1, 4 B m 3.3.5.1.3 s 2.19 pela Nigh at 3.3.5.1.5
'I83,3(c)
I a 3.3.5.1.9 a
! c. Reacter vessel Water 1, 2 C m 3.3.5.1.1 s 214.8
! Level - Nigh sa 3.3.5.1.3 inchee 1 2(83,3(83 at 3.3.5.1.6
- a 3.3.5.1.9 i
- d. Condensate storage 1, 2 D a 3.3.5.1.3 a 11.6 inchee
! Tank Level - Lane a 3.3.5.1.8 i 2(83,3(83 m 3.3.5.1.9 i
(eentinued)
- (e) When the seescleted subsystem (s) are respaired to be OPERABLE.
(c) With reacter stees dame preneure > 150 peig.
t ,
1
)
i i
l DAEC 3.3-44 Revision A 4
a , .. e = w so ..
ECCS Instrumentation
- 3.3.5.1 ACTIONS (continued) J CONDITION REQUIRED ACTION COMPLETION TIME C. As required by C.1 -.....--NOTES-------- I Recuired Action A.1 1. Only applicable I anc referenced in in MODES 1. 2.
Table 3.3.5.1-1. and 3. j
- 2. Only applicable for Functions 1.c.1.e. 2.c and 2.e. ;
Declare supported 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from l discovery of feature (s) inoperable. loss of initiation l capability for i two or more low l pressure ECCS i subsystems a
C.2 --------NOTES--------
- 1. Only applicable ~
l in Modes 1. 2. '
l and 3.
- 2. Only applicable- -
/
fnr rnnetsn g, 2.g. 2.h. .~.
i
, and2.J. ,9
..................,1 Declare Low Pressure 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from Coolant Injection discovery of (LPCI) subsystem loss of Loop inoperable. Selection capability M
C.3 Restore channel to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> OPERABLE status.
(continued)
DAEC 3.3-35 Revision A
l ECCS Instrumentation 3.3.5.1 ACTIONS (continued) j l
CONDITION REQUIRED ACTION COMPLETION TIME E. As required by E.1 .
NOTES--------
4 Recuired Action A.1 1. Only a>plicable anc referenced in 4
in MODLS 1. 2.
i Table 3.3.5.1-1. and 3.
- 2. Only applicable for Functions 1.d and 2.f.
Declare supported I hour from feature (s) inoperable. discovery of
, loss of
- initiation capability for two or more
, minimum flow valves in the low pressure
- ECCS subsystems g .
! E.2 Restore channel to 7 days
- OPERABLE status.
4 F. As required by F.1 Restore channel to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Required Action A.1 OPERABLE status.
and referenced in Table 3.3.5.1-1.
4 (continued)
DAEC 3.3-37 Revision A
Recirculation Loops Operating j 3.4.1 l
- =
4 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 Recirculation Loops Operating
- LCO 3.4.1 Two recirculation loops with matchM ntunn c shall be in operation with core flow as a Tunc".1on of e i l
- outside the Exclusion Region specified in the COLR.
POWER W
. E L
One recirculation loop may be in operation with core flow as
- a function of THERMAL. POWER outside the Exclusion Region i
s)ecified in the COLR and with the following limits applied j w1en the associated LCO is applicable:
- a. LCO 3.2.1. " AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)." single loop operation limits specified in the l COLR:
i b. LCO 3.2.2. " MINIMUM CRITICAL POWER RATIO (MCPR)." single l loop operation limits specified in the COLR: and {
- c. LCO 3.3.1.1. " Reactor Protection System (RPS) j Instrumentation." Function 2.b (Average Power Range -
- Monitors Flow Biased High Scram). Allowable Value of Table 3.3.1.1-1 is reset for single loop operation.
j APPLICABILITY: MODES 1 and 2.
ACTIONS CONDITION RE0VIRED ACTION COMPLETION TIME A. No recirculation loops A.1 Place the reactor Imediately in operation. mode switch in the i Shutdown position.
(continued) 1 l
l DAEC 3.4-1 Revision A 1
Recirculation Loops Operating 3.4.1 CONDITION REQUIRED ACTION COMPLETION TIME One or two Initiate action to B. B.1 Immediately I recirculation loops in exit the Exclusion !
operation in 'the Region. !
Exclusion Region of '
- the power / flow map described in the Core Operating Limits Report.
, C. Recirculation pump C.1 Trip one 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> speed mismatch not recirculation pump. l within limits. ,
D. Requirements of the D.1 Satisfy requirements 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> LCO not met for of the LCO. 1
- reasons other than
- Conditions A, B or C. -
l i
E. Required Action and E.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> l associated Completion Time of Condition C or
{ D not met.
DAEC 3.4-2 Revision A
Recirculation Loops Operading i 3.4.1 i 1
, SURVEILLANCE RE0VIREMEMTS 1
i SURVEILLANCE FREQUENCY I l
SR 3.4.1.1 --------------------NOTE------------------- l Not required to be performed until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> '
after both recirculation loops are in !
operation.
Verify recirculationgs i
ismatch 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> with both recirculation pumps a steady _
stat _e_ operation _is as follows:
- a. The speed of the faster ) ump shall be I s 135% of the speed of t1e slower pump when operating at < 80% RTP.
- b. The speed of the faster pump shall be
- g. s 122% of the speed of the slower pump j when operating at > 80% RTP.
SR 3.4.1.2 Verify core flow as a function of core 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> THERMAL POWER is outside the Exclusion Region shown in the COLR.
DAEC 3.4-3 Revision A
ECCS-Operating 3.5.1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCST AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.1 ECCS-Operating LCO 3.5.1 Each ECCS injection / spray subsystem and the Automatic >
Depressurization System (ADS) function of four safety / relief valves shall be OPERABLE.
~
APPLICABILITY: MODE 1. -
MODES 2 and 3. except High Pressure Coolant Injection-(HPCI) is not required to be OPERABLE with reactor steam dame
)ressure s 150 psig and ADS valves are not required to
)e OPERABLE with reactor steam dame pressure s 100 psig.
ACTIONS CONDITION RE01) IRED ACTION COMPLETION TIME i
A. One Residual Heat A.1 Restore RHR pump to 30 Days Removal (RHR) pump OPERABLE status.
I B. One low pressure ECCS B.1 Restore low pressure 7 days i subsystem inoperable ECCS subsystem to a sons other than-- OPERABLE status.
1 _on iti _on A.
jC. One Core Spray C.1 Restore Core Soray 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> subsystem inoperable. subsystem to 0)ERABLE status.
IAND DR One or two RHR pump (s) inoperable. C.2 Restore RHR pump (s) 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to OPERABLE status D. Both Core Spray D.1 Restore one Core 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> subsysteris inoperable. S> ray subsystem to 0)ERABLE status.
1 (continued)
DAEC 3.5-1 Revision A
. Lea . .. . . . -.
. 1 ECCS-Operating 3.5.1 ACTIONS (continued) r-CONDITION REQUIRED ACTION COMPLETION TIME E. Required Action and E.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition A. E _
- q. '
B. C. or D not met.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> E.2 Be in MODE 4. i F. HPCI System F.1 Verify by Imediately '
inoperable. ackninistrative means ,
M -
F.2 Restore HPCI System 14 days to OPERABLE status.
G. HPCI System G.1 Restore HPCI System 7 days inoperable.
to OPERABLE status.
M W One RHR pump G.2 Restore RHR pump to 7 days W inoperable. OPERABLE status.
H. HPCI System H.1 Restore HPCI System 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable. . to OPERABLE status.
M E One low pressure ECCS H.2 Restore low pressure 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> subsystem is ECCS subsystem to inoperable f r r. s,oJn OPERABLE status.
nther than on on I. HPCI System I.1 Restore HPCI System 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable. to OPERABLE status.
M W _
One ADS valve I.2 Restore ADS valve to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable. OPERABLE status.
(ccatinued)
DAEC 3.5-2 Revision A
& O e
ECCS-Operatin j 3.5.
ACTIONS (continued) -
CONDITION REQUIRED ACTION COMPLETION TIME l J. Required Action and J.1 Be in Mode 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition F. E G. M or I not met.
J.2 Reduce reactor steam 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> dome pressure to )
s 150 psig. j i
K. One ADS valve K.1 Restore ADS valve to 30 days (
inoperable. OPERABLE status. '
L. One ADS valve L.1 Restore ADS valve to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> <
inoperable.- OPERABLE status.
l
= m l One low pressure ECCS L.2 Restore low pressure 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> j subsystem inoperable ECCS subsystem to l Br reasons otber thart l pncumn m OPERABLE status. j Q
i I
M. Two or more ADS valves H.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> inoperable.
M E
M.2 Reduce reactor steam 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> ;
Required Action and dome pressure to associated Completion s 100 psig. l Time of Condition K or ;
L not met. l (continued) j DAEC 3.5-3 Revision A
'~
- ECCS-Operating 3.5.1 ACTIONS (continued) -
CONDITION REQUIRED ACTION COMPLETION TIME
subsystems ino:erable
, for reasons otler than '
. Condition C or D.
E ,
^
HPCI System and two or .
i' more ADS valves inoperable.
] E i
HPCI System and two or more low pressure ECCS subsystems inoperable.
- 2 i One ADS valve and two j or more low pressure i ECCS subsystems inoperable.
l m j One ADS valve and HPCI i System and one low pressure ECCS
]
subsystem inoperable.
1 SURVEILLANCE RE0VIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify. for each ECCS injection / spray 31 days subsystem, the piping is filled with water from the pump discharge valve to the injection valve. _
(continued)
DAEC 3.5-4 Revision A
. , ~ - _ _ _ _l
- ECCS-Op6 rating 1
. : 3.5.1 1, . .
SURVEILLANCE RE0VIREMENTS (continued) = >*b '.' ,
l SURVEILLANCE FREQUENCY . l l SR 3.5.1.7 -------------------NOTE--------------------
- p~ 0 p/ : . .r:
[' 1. Vessel injection / spray may be ,
excluded. Mi3%.u.
....,e
- 2.- When an ECCS System / subsystem or -
- '5 % :.7?- g. QJ Diesel Generator (DG) is placed in an iT Aa.
inoperable status' solely for the J
l -8 i
- performance of this Surveillance. .'4 {77;,Y L;far; i . j
- entry into associated Conditions and 2~ i
- : !
Recuired Actions may be delayed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for CS System testing and 6 "h@.g$2.
a s-
.1 n..
~ ,
hours for LPCI and HPCI System -
)
i testi rovided the remaining ECCS. gc. )
the R C bystem if the HPCI System is ~
{
- being tested and the remaining AC :
i Sources if CS is being tested, are .. '.. 1 i OPERABLE. -r l
. .:. 9 -
! Verify each ECCS injection / spray subsystem 24 months !
- actuates on an actual or simulated .
] automatic initiation signal. h< wl?. ' ': ~ ~
! :.M ,. <
k i SR 3.5.1.8 -------------------NOTE--------------------
Valve actuation may be excluded.
8 l 1 Verify the ADS actuates on an actual or 24 months
- simulated automatic initiation signal.
j SR 3.5.1.9 ------------------NOTE--------------------
Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
! after reactor steam pressure and flow are l adequate to perform the test. .
4
- Verify each ADS valve opens when manually 24 months i actuated-i 4
) .
.u .
1
+
} DAEC 3.5-7 .;
Revision A i
~. ,.
- 0 .
ECCS-Operatin$
BG.5.
4 BASES 7 7~
SURVEILLANCE SR M17 (continued) ;?
RE0VIREMENTS e y.e. G . .
LPCI will cause the systems or subsystems to operate as ;S designed. including actuation of the system throughout its f emergency actuation ofoperating sequence, all automatic valvesautomatic pump startup and76 %@E to their required positions. As part of this SR for the LPCI subsystem, a'r 9.. .
verification of the " power-seeking" logic for the LPCI: T 1,
" Swing Bus" (IB34A and 1B44A). i.e. the ability to tra'sfer n -
power sources from either AC Essential Bus upon loss oft .gc '
, power (either AC or 125 VDC). is included. This M~ $. _ __ '
verification, when coupled with the verification of the /
" break-before-make" coordination of the breakers in SR " -
3.8.7.2. demonstrate the ability of the Swing Bus to perform its intended safety function in support of the Loop Select design of the LPCI subsystem without compromising the independence of the AC Distribution System (Reference 16).
This SR also ensures that the HPCI System will automatically restart on an RPV low water level signal received subsequent to an RPV high water level trip and that the suction 1s- ~
automatically transferred from the CST to the suparession .
pool on a CST Low Water Level Signal or Torus Hig1 Water .
Level Signal. The LOGIC SYST&i FUNCTIONAL TEST performed LCO 3.3.5.1 overlaps this Surveillance to provide complete )
3 testing of the assumed safety function. .c
- Operating experience has shown that these components usually i pass the SR when performed at the 24 month Frequency, which i is based on the refueling cycle. Therefore the Frequency
- was concluded to be acceptable from a reliability standpoint.
This SR is modified by two Notes. The first Note excludes
. vessel injection / spray during the Surveillance. Since all active components are testable and full flow can be ~
demonstrated by recirculation through the test line. coolant injection into the RPV is not required during the Surveillance. The second Note allows delaying the entry into associated Conditions and Required Actions for up to six -
hours. This note is necessary because the various subsystems are prevented from injecting or initiating, making the '
subsystems inoperable. The HPCI injection valve is deenergized in the closed position to prevent iiijection into the RPV. The LPCI subsystem logic is overridden to prevent RHR pump starts. LPCI Loo) Select Logic from closing the Recirculation System Dist1arge valves and the LPCI inject (continued)
DAEC B 3.5-18 Revision A
-
- i 1
1 i Distribution Systems-Operal'ing 1 3.8.7
)
SURVEILLANCE REQUIREMENTS -..
SURVEILLANCE FREQUENCY Il.j.i
+
- SR 3.8.7.1 Verify correct breaker alignments and 7 days s"
- . '7e / .?
j indicated power availability to required AC .).,;.k.q,.. ...
- and DC electrical power distribution . .o. p, f subsystems. x,
% .?, ..,,: a. .: Chii
.v.e. A',:p
,a
!#. ..c.:5. *
~
- SR 3.8.7.2 Verify proper coordination of the LPCI 24 months s 7-i Swing Bus circuit breakers. la.'" ~W.s f#l'."
f k .
i
- w j .
4
. 4:r..+
2, i . . -
- ~
i i
-g' f
f i
4 4
1 ;.
a DAEC 3.8-29 Revision A J
j . -
e .
3 ,
Distribution Systems-Operating B-3.8.7
~
BASES (continued) = -
.'.}
. n; SURVEILLANCE SR 3 8.7.2 /
REQUIREMENTS . ._t 1 This Surveillance verifies the " break-before-make" cN..
coordination of the circuit breakers for the LPI Swing Bus l (1834A and IB44A). This SR, when coupled witt SR 3.5.1.7. I demonstrates the ability of the LPCI Swing Bus '.o' perform its intended safety function in support of the LiCI. Loop 3 Select design without compromising the independence of'the AC Electrical Power Distribution System (Reference 3)i l Consequently. failure to satisfy this SR requires that both 1B34 and IB44 buses be declared inoperable, and Condition G be entered until either IB34 or 1B44 can be isolated from the Swing Bus, as a loss of all low pressure ECCS has l potentially occurred. If the Swing Bus can be isolated from l IB34 or 1B44. then this SR is met, and the AC electrical power distribution subsystems are not inoperable. However, this will result in a failure to meet SR 3.5.1.7 (and
- Condition B of LCO 3.5.1 will be required to be entered since the LPCI system will be inoperable). +s
- a: .
( _
a !.? JQ .
- REFERENCES 1. UFSAR, Chapter 6. ,
2.
UFSAR. Chapter 15. -
- 3. J. Hall (NRC) to L. Liu (IELP). "LPCI Swing Bus ' Design
- Modification (TAC No. 69556)." dated January 19, 1989
.W *R$
. . . #,6 *
~
, ( (,
A
-r 4
W ob
. .. .z. .
C'-
4 DAEC - B';3.8-72 #Re ksion A
?.4 1 * -2p .*2
-.