ML20087E934
| ML20087E934 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 01/13/1992 |
| From: | DUQUESNE LIGHT CO. |
| To: | |
| Shared Package | |
| ML20087E922 | List: |
| References | |
| NUDOCS 9201220241 | |
| Download: ML20087E934 (17) | |
Text
r i
ATTACHHENT A-1 l
Beaver Valley Power Station, Unit No. 1 Proposed Technical Specification Chango No. 195/60 l
Reviso the Technical Specification ao follows:
EcaQVO Pagn Ingart Pagn i
3/4 4-4a 3/4 4-4a 3/4 4-4b B3/4 4-1 D3/4 4-1 l
i t
s' h'O [ 2 ['O 2'd [
'/'5'l ) } } j V tr' StDOC >: GQGOD3'34 POR P
. _ _. _.. _.. _ _ -. _ _.. -.... _. _ _,.. _ - _. _ _ - _.. _ - ~ _ -
prAcron co4LAul S.YS2EH react 01 CoplAliLfyliP_ STARTUP LIMITIllG CollDITIo!4 FOR OPERATION 3.4.1.6 If both OPPS PORV's are not
- OPERABLE, an idle reactor coolant pump in a non-isolated loop shall not be rtarted, unless:
1.
The acgual pressurizer water level is less than 60 percent (840 ft
),
and temperature
- of each utoar generator 2
The secondary water is less than 25'T above each of the in-service RCS cold leg temperatures.
AEPLICAlllLLTlt When the toinperature of one or more of the non-isolated loop cold legs is 5 the enable temperature setforth in Specification 3.4.9.3.
ACTION:
With the pressurizer water level greater than or equal to 60 percent the ter..parature of the steam generator in the loop associated with or the reactor coolant pump being started greater than or equal to 25*
above the. cold leg ternperature of the other non-isolated loops, suspend the startup of the reactor coolant pump.
SURVEILLANCE REQUIREMENTS u
6.4.1.6.1 The pressurizer water volume and the secondary water
' temperature of the non-isolated steam generators shall be determined within ten minutes prior to starting a reactor coolant pamp.
5 L
The secondary water temperature is to be verified by direct measurement o t' the fluid temperature, or contact temperature:
readings-on -the steam generator secondary, or bJ1oJ*down piping.
af ter purging of stagnant water within the piping. V,f/, cme o,'
ywaM ;,5 s, c)Mo<abe? o>,caraov me.d of /
d pp.,11 ftadW
.gu h u Slcse/p nwo t.
y a[n i,4,.,;.,, 4 s h <A :d d,
/
o
, w a/ tru m/L BEAVER LLEY'- UNIT 1 3/4 4-4a Proposed
, ~. _.. - _ _ _
REACTOR COOLANT SYSTEM R_QCTORCOOLANTPUMPSTARTUP LIMITING COND1110N FOR OPERATION 3.4.1.g An idle reactor coolant pump in a non isolated loop shall not be started, unless the secondary watei temperature
- of each steam generator is less than M T above each of the i m ervice RCS cold leg temperatures.
M APPLICABILITY: When the temperature of one or more of the non-isolated loop cold legs is 1 Jb0*f.
IO"/#'
ACTION:
ec qaajh 6 With the temperature of the steam generator in ther, loop associated with the reactorcoolantpumpbeingstartedgreaterthan30'Fabovethecoldlegtempera-ture of the other non-isolated loops, suspend the startup of the reactor coolant pump.
SURVEILLANCE REOUIREMINTS 4.4.1.
1 The secondary water temperature of the non-isolated steam generators shall be determined within 10 minutes prior to starting a reactor coolant pump,
- The secondary water temperature is to be verified by direct measurement of the fluid temperatu.*e, or contact temperature readings on the steam generator
' secondary, or blowdown piping after purging of stagnant water within the piping.
LUt,W1 orre at s.scem ov.ac}or coc/anf pu,fs ik opwafje.,
measa,vmed of.4 JMf'eren.Na/.h..,ccm/wv h nd repuirv/
wies f6 s}adiy aaWl.hsa/ pa-yri.
y 3/44-f BEAVER VALLEY - UNIT IWOf0SEb
~ leL._HidCMLCO21 Attr liXund u
hW g..,..
-. =.= _ - _ - - - -
=_.-__--
N4 d_i_LJFAMILM.IMLipoPs The plant is designed to operate with all reactor coolant locpc in operation and maintain D!4 BR above the design DNBR limit during all normal operations and anticipatea transients.
In Modes 1 and 2, with one reactor coolant loop not in operation, THERMAL POWER in rostricted to 1
31 percent of RATED THERMAL POWER until the overtemperature oT trip is reset.
Either action ensures that the D!lBR will be maintained tiove the design DNBR limit.
A loss of flow in two loops will cause a reactor trip if operating above P 7 (11 porcent of RATED THERMV POWER) while a loss of flow in one loop will cause a
reactor trip if operating above P-8 (31 percent of RATED THEPyJsL POWER).
l In MODE 3,
a single reactor coolant loop provides sufficient heat removal capability for removing decay heat;
- however, due to the initial conditions assumed in the analysis for the control rod bank withdrawal from a suberitical condition, two operating coolant loops are rcquired to meet the DNB design basis for this Condition II event.
In MODES 4
and 5,
a single reactor coolant loop or RHR subsystem provides sufficient heat removal capability for removing decay beat; but single failure considerations require that at least two loops be OPERABLE.
Thus, if the reactor coolant loops are not OPERABLE, this specification requires two RHR loops to be OPERABLE.
The operation of onc.
Feactor Coolant Pump or one RHR pump provides adequate flow to ensure mixing, prevent stratification and produce gradual reactivity changes during boron concentratien reductions in the Reactor coolant System.
The reactivity change rate associated with boron reduction
- will, therefore, be within the capability of operator recognition and contrpl.
ih enable JefraW-gy 4 fbg pgg %
cold legs less than or equa%o 475'r are provided to prevent RCS 1 rectrictions on starting a tor coolant Pump with one or more\\
The lt RCS pressure transients, caused by energy additions from the secondary
- system, which could exceed the limits of Appendix G to 10 CTR Part 50.
The RCS will be progected ggainst overpressure transients and
/
M M/,.ysd Ap vf Aa will not exceed the limits vt 4}w.v/a f 47
& #f N
of eat $ rltah N h'M W""'
eac 4 af A ACS ceb? by It +y%bo'sJ. Tbe /
M'" #
secu claty WoNe** lt q '0 % 44
}; pf en.fh WC3 W!II be
?S*T abo 4 ry}et}d of aNsf eve /pesse et lMiOY U * *
- f M
N"*
WA
} ylt/ 4.1 cxroc/ pk - /hds 4
BEAVER VALLEY - UNIT 1 B 3/4 4-1 hAN'03fD
,.,E,g,7.,_.m....,
n,r-
,,.,...r,,,'..-
-.,, -, ~.....
_--..m.
~,...,,..__,9, w
w 3 e 7,..
y.,,
ATTACHMENT A-2 Beaver Valley Power Sthtion, Unit lio, 2 i
Proposed Technical Specification Change lio. 195/60 a.
/
Reviso the Technical Specification as follows:
Remove Paco Ina_QI_t_f_A931 3/4 4-7 S/4 4-7 9
i b
+
f 7
.. _., ~,v,
.,m,.
m4._,,,,.,.,,,w...
m,...,.,-,,.-..,,ww
.,_,...-,.,,.,,m.,,,..,_....,,=.,.,,,_m....
REACTOR COOLANT PUMP STARTUP l
LIMITING CONDITION FOR OPFRATION 3.4.1.6 An idle reactor coolart pump in a non isolated loop shall not be started, unless the secondary water temperature
- of each steam generator is less than 50'F above each of the inservice RCS cold leg temperatures.
APPLICABILITY:
When the temperature of one or more of the non-isolated loop colo-legs.is 1 350'F.
ACTION:
of e val *$
Withthetemperatureofthesteamgeneratorinh*50'Fa>ovethecoldlegte e 100) associated with the reactor coolant pump being started greater thun 1
ture of the other non isolated loops, suspend the startup of the reactor coolant putr.p.
SURVEILLANCE REQUIREMENTS - 4.4.1.6.1 The secondary water temperature of the non isolated steam generators shall be determined within 10 minutes prior to starting a reactor coolant pump.
l "The secondary water temperature is to be verified by direct sensurement of
- the fluid temperature, or contact temperature readings on the steam generater secondary, or blowdown piping after purging of titagnant water within-the piping.
(Ut W orte o r utset tecciot cooloa,f pumpr As ofeah%,
n1easaMmed of Un aWfe.n*,h'a/.hmpwaha k not rtyuInd peice to. sJadiy aaMhaa/ pa y>s.
i l
BEA'iER VALLEY - UNIT 2 3/4 4-7 P&otosa wMww--
p.p+--
- vp ve 9. y t,.w_g
,-.9'wypMyggwe,-e--
ywgt~
w y',Wwy
+1ePNem"ww+-nd-*-+-w-p>e
+Ca-www-- + -m,w3 y--
r-,qtie'
- 4'r*'grg as-tt*
rq--y-m MN-
~w
ATTACHMENT B Beaver Valley Power Station, Unit Nos. 1 and 2 Proposed Technical Specification Change No. 195/60 REVISION OF SPECIFICATION 3.4.1.6 AND ADDITION OF BV-1 SPECIPICATION 3.4.1.7
- l A.
DESCRIPTION OF AMENDMENT REQUEST The proposed amendment would modify Specification 3.4.1.6 for both units to allow starting additional reactor coolant pumps (RCPs) without measurement of the differential temperature.
BV-1 Specification 3.4.1.7 has been added to provide a differential temperature limit of less than 25*F starting a RCP and allows starting additional RCPs without measurement of the differential temperature.
BV-1 Bases 3/4.4.1 has buon revised to addreen starting critoria with and without two power operated relief valves (PORVs) operable.
H.
BACKGROUND Measurement of the differential temperature in accordance with Specification 3.4.1.6 and the new BV-1 Specification 3.4.1.7 requires a
containment entry by plant operators for each RCP startup.
The RCPs are not normally started in a succession that would allow an-operator to perform the required meauurements in a reasonable period of
- time, therefore, multiple containment entries are required to satisfy this requirement.
The proposed change reduces the number of required containment entries and is consistent with the "as low as reasonably achievable" (ALARA) program which strives to reduce the doses received by plant personnel.
BV-1 Specification 3.4.1.6 was added by Amendment No. 96 to address overpressure protection system (OPPS) concerns related to the heat input event where less than 2 PORVs are operable and heat is transferred = from a
hot steam generator to the' reactor coolant system (RCS) during RCP startup.
The analysis performed as a
basis _ for this change was only performed for BV-1 and does not apply for BV-2.
In reviewing the BV-1-analysis it wao determined that the requirement to limit RCP startup, similar to DV-2 Specification 3.4.1.6, also applies to BV-1 with a
differential temperature of less than 25'F.
Therefore, Specification 3.4.1.7 has been added to provide requirements consistent with BV-2 and reflect the current plant operating procedures.
The change to BV-1 Bases 3/4.4.1 has been revised to separately address ths RCP startup requirements.
Specification 3.4.1.6 applies when starting a RCP with less than 2 PORVs operable and Specification 3.4.1.7 applies at all times when starting a RCP.
C.
JUSTIFICATION Measurement of the secondary to primary water temperature differential prior to starting a
RCP is only required when starting the first pump.
Once one pump is operating this pump 1
ms L.
a w& A s.sa amm xmwwe s-m Mum.e-se-M -m u m a----,te---
om a msm wam mmmu mm m m a mes_+m mmm wrua_wnx.ms.m man u m,,asau ATTACHMENT B, continued Proposed Technical Specification Change Nos. 195/60 Page 2
~
provides the forward flow in the activo loop and creates a roverse flow in the inactive loops to conduct the transfer of heat betwoon the primary system and the shell side of the steam generators until temperaturo equilibrium is established.
The primary to secondary temporsturo differenco will always be loss than the maximum difference prior to the start of the first pump.
Thoroforo, with one pump in operation thoro _is no need to a
measure the temperaturo differenco prior to starting additional pumps.
Specification 3.4.1.7 has been added to the BV-1 technical specifications to reflect the requirements of DV-2 Spevification 3.4.1.6 and ensure the 25'F temperature differential is
)
applicable when starting a
RCP.
This change has boon added to reflect tho analysis assumptions and the current plant operating procedure requirements.
BV-1 Dases 3/4.4.1 has been modified to clarify the differences betwoon-Specifications 3.4.1.6 and 3.4.1.7 to docum9nt the basis for those requirements.
D., SAFETY ANALYSIS r
Specification 3.4.1.6 for both units has been modified and a now BV-1 Specification 3.4.1.7 has been added to require measurement of the secondary to primary water differential temperature only when starting the first RCP.
This is'a change from the current requirements where the temperature difference must be determined prior to starting each pump.
The basis for monsuring the temperature difference is to satisfy the analysis assumption which uses a
maximum temperature differance of 25'F, however, once one RCP is in operation sufficient flow is generated through out all of the locps to bring the steam generators and the RCS temperatures into equilibrium.
The primary to secondary temperature difference will. always be less than the maximum difference observed prior to the start of the first
- pump, therefore,- this change is consistent with the accident analysis assumptions and will not affect the UFSAR.
BV-2 Specification 3.4.1.6 provides RCp startup criteria and limits the temperature difference between the-steam generator and the_ RCS cold legs to 50'F.
A similar requirement is being added to - _ _the - BV-1 technical _. specifications _ in Specification 3.4.1.7 1
which limits the temperature difference to less than 25'F.
This temperature difference-reflects that assumed in the accident analysia and the proposed Limiting condition for operation, Applicability, Action and' Surveillance Requiremente are
. ith the BV-2 requirements.
This specificacion will consistent w
provido-the RCP startup requirements to ensure the accident analysis' assumptions are met and will not affect the UFSAR.
i-1-
9 ATTACHMENT D, continued Proponed Technical Specification Chango Nos. 195/60 Page 3 A
change has been added to BV-1 Basos 3/4.4.1 to describo the differences between the requirements identiflod in Specifications 3.4.1.6 and 3.4.1.7.
Specification 3.4.1.6 provides rostriccions on starting a
RCP when loss thais 2
PORVs are operable by requiring a
pressurizer water lovel less than 60 porcent and the temperaturo difference betwoon the steam generators and the RCS cold lega less than 25'F.
Specification 3.4.1.7 also provides rostrictions on starting a
RCP and is applied when 2 PORVs are operable by limiting thu maximum temperaturo difference between the steau generators and the RCS cold legs to less than 25'F.
These Bases changos are consistent with the specification requirements, the accident analysis assumptions, and the plant RCP startup procedure and will not affect the UFSAR.
Based on the above considerations, the OPPS accident analysis assump*.ons are satisfied with respect to the heat input event from a
- startup, therefore, the proposed changes a re considered to be safe and will not reduce the safety of the plant.
E.
NO SIGNIFICANT HAZARDS EVALUATION The no significant hazard considerations involved with the proposed amendment have been ovaluated, focusing on the three standards set forth in 10 CFR 50.92(c) as quoted below:
The Commission may make a final determination, pursuant to the procedures in paragraph 50.91, that a proposed amendment to. an operating license for a
facility licensed under paragraph 50.21(b) or paragraph 50.22 or for a testing facility involves no significant hazards consideration, if operation of the facility in accordance with the proposed amendment would nots (1)
Involve a 'significant increase in the probability or consequences of an accident previously evaluated; or (2)
Create the possibility of a new or different kind of accident from any accident previously evaluated; or i
(3)
Involve a significant reduction in a margin of safety.
The following evaluation is provided for the no significant hazards consideration standards.
1.
Does the change involve a
significant increase in the probability or consequences of an accident previously i
L evaluated?
Specification 3.4.1.6 for both units has been modified and a new BV-1 Specification 3.4.1.7 has been added to require a l
one time measurement of the secondary to primary water differential temperature prior to starting the reactor l
g.
1._
.. ~.. _.... _....,, _, _ _ _ _. _ _ _ _.,. _.. _ _ _ _
~r.
.__.-__.._,___m,_,_,.
..- - -.~ _._ - - - _ _ - _ _ _
- ATTACl! MENT D, continued Proposed Technical Specification Chango Non. 195/60 Pago 4 I
coolant pumps (RCP).
The requirement to measure the differential temperaturo reflects the accident analysis i
assumption for the overprossure protection system (OPPS) heat input event related to the transfer of heat from the secondary side to the primary side when starting a RCP.
Following the start of one
- pump, sufficient flow
.s generated throughout all of the loops to bring the primary sido end secondary sido into thermal equilibrium.
When starting additional pumps the temperature difference will always be loss than the maximum difference observed prior to thu start of the first pump, therefore, the requirement to determine the differential temperature prior to starting each additional pump is redundant and has boon doloted.
This change remains consistent with the accident analysin assumptions and will not affect the UFSAR, thorofore, this change will not involvo_ r.
significant increase in the probability or consequences of an accident previously evaluated.
A now BV-1 Specification 3.4.1.7 has been added to limit the temperature difference to loss than 25'F when starting a
~
RCP._
This now specification is similar to BV-2 Specification 3.(,1.6 and reficcts the temperaturo difference assumed in the accident analysis.
This specification inco.rorates a RCP startup requirement assumed in the accident analysis, is consistent with current plant operating procedures and will not affect the
- UFSAR, this change will not involvo a
significant thoroforo,in increa,o the probability or consequences of an accident previously ovaluated.
BV-1 Bases 3/4.4.1 has boon revised to describe the differences between Specification 3.4.1.6 and Specification 3.4.1.7.
Specification 3.4.1.6 providos restrictions on starting a
RCP when less than 2
PORVs are operable and Specification 3.4.1.7 providos restrictions when 2 PORVs are operable.
These Bases changes are consistent with the specification requiromonto, the accident-analysis assumptions, and the plant RCP startup procedures and will not affect the
- UFSAR, thole f oro, - this change will not involve a
significant increase in the probability or consequences of an accident previously evaluated.
2.
Does -the change create the possibility of a new or different kind of accident from any accident previously evaluated?
The proposed changes are consistent with the accident analysis assumptions and the plant RCP startup procedures and reflect those requirements provided in the BV-2 specifications.
These changes will not adversely affect the reliability of the RCPs or the RCP startup procedures, therefore, these changos will not create the possibility of a
new or different kind of accident from any accident previously evaluated.
ATTACHMEti; B,
continued g
Proposed Technical Specification Change Nos. 195/60 lage 5
_x Does the change involve a significant reduction in a margin i,
of reen'yt
.i k
Tr
<P startup requirements have been modified to allow g
- p. a it operating flexibility by reducing redundant
';.gairements and incorporating changes in accordance with
?
the accident analysis assumptions to ensure the reactor
' a " t.
system will not be subjected to an overpressure
.1
.m 'on when a
RCP is started.
Plan: operation will be
' nu ned v:- th i n squired limits to cne re that the plant
'g, a%
basis in mu therefore, the proposed changes do not
[
.ve'
. a sig; it! / snt reduc *. ion in a margin of safety.
.JNIFIC..NT llAZARDS CONSIDERATION DETERMINATION
.s v
on the considerations expressed above, it is concluded that chs
.ctivitios assortattd with this license amendment request Attia,les the no i?.gnificant hazards consideration standards of
,.;4 -
- and, accordingly, a
no significant hazards X
consideration finding is justified.
a r
W D
E
_ a.
n
~
...- ~---...
ATTACHMENT C-1 1
Beaver Valley Power Station, Unit No. 1 Proposed Technical Specification Change No. 195/60 Typed Page:
3/4 4-4a 3/4 4-4b B 3/4 4-1 i
4 1
t.
ELaglOR CQDLANT SYSTEM SEACTOR COOLANT PUMP STARTUP LIMITING CONDITION FOR OPERATION 3.4.1.6 If both OPPS PORV's are not
- OPERABLE, an idle reactor coolant. pump in a non-isolated loop shall not be started, unless:
The ac pressurizer water level is less than 60 percent (840ftgual 1.
), and 2.
The secondary water temperature
- of each steam generator is less than 25'F above cach of the in-service RCS cold leg temperatures.
APPLICABILITY:
When the temperature of one er more of tha non-isolated loop cold legs is s the enable temperature Jet forth-in Specification 3.4.9.3.
ACTIQH:
With the pressurizer water level greater than or equal to 60 percent or the temperature of the steam generator in the loop asacciated with the reactor coolant pump being started greater than or equal to 25' above tha cold jeg tempe rat',.re of the other non-isolated loops, suspend ths startup of the reactor coolant pump.
SURVEILLANCE REQUIREMENTS 4.4.1 6.1 The pressurizer water volume and the secondary water temperature of the non-isolated steam generators shall be determined within ten minutes prior to starting a reactor coolant _ pump.
The secondary water temperature is tc be verified by direct measurement of the fluid temperature, or_ contact' temperature readings on the steam generator secondary, er blowdown piping after purging of stagnant water within the piping.
With ene or more reactor coolant pumps in -operation measurement.ca.
the differential _
temperature is not required prior to starting additional pumps.
l
- BEAVER VALLEY - UNIT 1 3/4 4-4a Propoced
_ ~_
4
- REACTOR _ COOLANT SYSTEM
-REACTOR COOLANT _ PUMP-STARTUP LIMITING CONDITION FOR OPERATION
-m 3.4.1.7 An idle reactor coolant pump in a non-isolated Igop shall not _be
- started, unicar the secondary water temperature of each steam generator is less than 25'F above each of the inservice RCS cold leg temperatures.
APPLICABILITY:
When the temperature of one or more of the non-isolated loop cold legs is 5 the enable temperature.
ACTION:
with the temperature of the steam generator in the loop associated with the reactor coolant pump being started greater than or equal to 25'F above the cold leg temperature of the other non-isolated loops, suspend the startup of the reactor coolant pump.
SURVEILLANCE REQUIREMENTS 4.4.1.7.1 The secondary water temperature of the non-isolated steam generators shall be-determined within 10 minutes prior to starting a reactor coolant pump.
The _ secondary water temperature is to be verified by direct measurement of the fluid-temperature, or contact temperature rer. dings on the steam generator secondary, or blowdown piping after purging-of stagnant water within the piping.
With one or more reactor coolant pumps in operation measurement of the differential temperature is not required prior to starting additional pumps.
l l
l L
1:
BEAVER VALLEY - UNIT-1 3/4 4-4b Proposed l
1/4.4 -REACTpR COOLANT SYSTEM BASES
__w n
3/4.4.1 REACTOR COOLANT LOOER The plant is designed to operate with all reactor coolant loops in operation and maintain DNBR above the design DNBR limit during all normal operations and anticipated transients.
In Modes 1 and 2, with one reactor coolant loop not in operation, THERMAL POWER is restricted to s
31 percent of RATED THERMAL POWER until the Overtemperature AT trip is reset.
Either action ensures that the DNBR will be maintained above the design DNBR limit.
A loss of flow in two loops will cause a reactor trip if operating above P-7 (11 percent of RATED THERMAL POVER) while a loss of flow in one loop will cause a
reactor trip if operating above P-8 (31 percent of RATED THERMAL POWER).
In MODE 3,
a single reactor coolant loop provides sufficient heat removal capability for removing decay heat; however, due to the initial conditions assumed in the analysis for the control rod bank withdrawal from a subcritical condition, two operating coolant loops are required to meet the DNB design basis for this Condition II event.
In MODES 4
and 5,
a single reactor coolant loop or RHR subsystem provides sufficiant heat removal capability for removing decay heat; but single failure considerations require that at least two loops be OPERABLE.
Thus, if the reactor coolant loops are not OPERABLE, this specification requires two RHR loops to be OPERABLE.
The operation of one Reactor Coolant Pump or one RHR pump provides adequate flow to ensure mixing, prevent stratification and produce gradual reactivity changes during boron concentration reductions in the Reactor Coolant System.
The reactivity change rame associated with boron reduction
- will, therefore, be within the capability of operator recognition and control.
The restrictions on starting a Reactor Coolant Pump with one or more RCS cold legs less than or equal to the enable temperature are provided to prevent RCS pressure transients, caused by energy additions from the secondary system, which could exceed the limits of Appendix G to 10 CFR Part 50.
The RCS will be protected against overpressure transients with two PORV's OPERABLE and will not exceed the limits of Appendix G
by restricting starting of the RCP's to when the secondary water temperature of each steam generator is less than 25'F above each of the RCS cold leg temperatures.
The RCS will be protected against overpressure transients with one or no PORV'e OPERABLE and will not exceed the limits 1
l BEAVER VALLEY - UNIT 1 B 3/4 4-1 Proposcd
= - -
-.... -.... ~.
ATTACHMENT C-2 Beaver Valley-Power Station, Unit No. 2 Proposed Technical Specification Change No. 195/60 Typed Page:
3/4 4-7
~
t L
V l.'
t
.~ - -. -...
REACTOR COOLANT SYSTEM EE KTOR COOLANT PUMP-STARTME LIMITING CONDITION FOR OPERATION a<>
3.4.1.6 An idle reactor coolant pump in a non-isolated Igop shall not be
- started, unless the secondary water temperature of each steam generator is less than 50*F above each of the inservice RCS cold leg temperatures.
APPLICARLLIIY:
When the temperature of one or more of the non-isolated loop cold legs is s 330*F.
ACTION:
With the temperature of the steam generator in the loop ansociated with the reactor coolant pump being started greater than or equal to l 50*F above the cold leg temperature of the other non-isolated loops, suspend the startup of the reactor coolant pump.
SURVEILLANCE REQUIREMENTS um,
4.4.1.6.1 The c.uccadary-water temperature af the non-isolated steam generators shall be determined within 10 minutes prior to-starting a reactor coolant pump.
The secondary water temperature is to be verified by direct
-measurement of the fluid temperature, or contact temperature readings on _the steam generator secondary, or blowdown piping after purging of stagnant water within the piping.
With one or more reactor coolant pumps in operation measurement of the differential temperature is not required prior to starting additional pumps.
l
[
l BEAVER VALLEY - UNIT 2 3/4 4-7 Proposed t