ML20084T978
| ML20084T978 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 06/02/1995 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20084T965 | List: |
| References | |
| NUDOCS 9506130048 | |
| Download: ML20084T978 (12) | |
Text
m:-
ENCLOSURE 2 TENNESSEE VALLEY AUTHORITY BROWNS PERRY NUCLEAR PLANT (BFN)
+
-UNITS 1, 2, AND 3 PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE TS-361 MAR.KED PAGES I.
AFFECTED PAGE LIST Unit 1 Unit 2 Unit 3 3.5/4.5-10 3.5/4.5-10 3.2/4.2-30 3.2/4.2-53 3.5/4.5-10 II.
MARKED PAGES See attached.
9506130048 950602 PDR ADOCK 05000259 P
(
e 3.5/4.5 CORE AND CONTAIEMENT C00LIEG SYSTEMS g
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.5.C RER Servica Water and Emeraancy 4.5.C RER Service Water 4BA Emeraancy Enniement Coolina Water Svatens Eaui--a t cooline Water sveta==
!(EECWS) (Continued)
(EECWS) (Continuadi l2.'DuringREACTORPOWER 2.- No additional surveillance OPERATION, REESW pumps is required.
must be OPEEAptE and assigned'to service as indicated in Table 3.5-l' for the specified time 1
limits.
i 4
I 3.
Dur4= g m CTOR POWER 3.
Routine surveillance for OPERATION, both RERSW these pumps is specified y
pumps D1 and D2;normally in 4.5.C.1.
AsscciAYab or alternately assigned vAcves to the RER heat =wehanger header supplying the standby coolant supply connection must be OPERABLE azeept as specified in 3.5.C.4 and 3.5.C.5 below..g A
N
)
(Mors : 3ccAar.c staud av i
l CoocAuf %"PPLY c.APNB it. Ty is a
Not A SeloRT-TE" Rot REQ u tRCM EMT)
J h
C.cM. ?C N GH T ts Nc7 CDMss%GRGb I M D PER h'%LE IC i
STAwb%Y - c.cotAMT SUPPL Y d A P A % tt_tT Y cAu a s R.G5To RCh rc sG R va c.E Lo n TH M 5~ souns.3 AMENDMENT N0'. I 6 9 BFN 3.5/4.5-10
)
Unit i l
l 1
.t..
m
.-.~.
c, i
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3.5/4.5' CORE Aim C01rPATNMENT COOLING 5 isms AUS of 1989 t
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 1
~3.5.C ime service Water =ad Emerzenev 4.5.C num service Water =ad r==reenev.
,Eaui==at Cooline Water Svata==
Eauinment Cooline Water Syst===
(EECW51 (Continned)
(FiCWS) (Contina-d) 2.
During REACTOR POWER 2.
No additional surveillance OPERATION, RERSW pumps is required.
anst be OPERABLE and assigned to service as i
indicated in Table 3.5-1 for the specified time limits.
3.
During Unit 2 REACTOR 3.
Routine surveillance for l
POWER OPERATION, any two these pumps is specified RER8W pumps (D1, D2, B1,
.in 4.5.C.1.
and B2),normally or Arab alternately assigned to the A ssoc.iMW RER heat== h===er header VAs.vG5 supplying'the standby coolant supply connection must be
. OPERABLE except as specified in 3.5.C.4 and 3.5.C.5 below.
Ny --
(Nets;3ccAuse srAut%y
]
coot.An r suTTLY CATA%LLtTY is Nor A selonv-TERM 17 ecuiRrutor, A couPc4EM T 1% Nor c.cusi> E'P.Cb suoPCRAh.E #F j
OTAMD3Y C. Cot ANT
$4WL y C A"P A~Bl o t TY cAu %g REsToK.sd To scRvice 5 s o uu. ')
tair m u 1
)
4 BFN 3.5/4.5-10 AM M M N NO.1 6 9 Unit 2
TABLE 3.2.F
^
Surveillance Instrumentation c5 Minta m # of EE Operable Instrument Type Indication Channels Instnment #
Instnment and Rance Notes 2
LI-3-46 A Reactor Water Level Indicator - 155" to (1) (2) (3)
LI-3-46 3
+60" 2
PI-3-54 Reactor Pressure Indicator 0-1500 psig (1) (2) (3)
PI-3-61 sfg
$c or 5 o 5
9 f -(,'l-5 2 A3 {II.
oryweil temperature secorder. Indicator (1) (2) (3)
-G'l-50 r
2X 0-400*F i
1
~
XR-64-52 Suppression Chamber Recorder 0-400*F (1) (2) (3) l-Air Temperature P
1 N/A Control Rod Position 6V Indicating
)
Lights
)
wp 1
N/A Neutron Monitoring SRM IRM. LPRM
)
(1) (2) (3) (4)
O to 1001 power
)
0 1 D ~6i-07"E M
Drywell Pressure Alarm at 35 psig
)
o
)
1 5-G4 - 52 A nd orywell Temperature Atar= if temp.
)
nd and Pressure and
> 281*F and
)
(1) (2) (3) (4) l p g q.5gA
%5-64-070
$hN $
$ t$$' 3 delay
)
^
1 LI-84-2A CAD Tank "A" Level Indicator 0 to 1001 (1) 1 LI-84-13A CAD Tank "B" Level Indicator 0 to 1001 (1)
Eli
-P M
N G
c)
IS G3
~.
7,.
TA8LE 4.2.F MINIM 91 TEST AND CALIBRATION FREQUENCY FOR SURVEILLANCE INSTRtMENTATION 4
y Instr
-t re ---I Calibration Freeuency Instrument Check
- 1) Reacter Water Level Oncc/6 months Each Shift
- 2) Reactor Pressure Once/6 months Each Shift
- 3) Drywell Pressure Once/6 months Each Shift
- 4) Drywell Temperature Once/6 months Each Shift
- 5) Suppression Chamber Air Temperature Once/6 months Each Shift
- 8) Control Rod Position M/A Each Shift y
- 9) Neutron Monitoring (2)
Each Shift
- 10) Drywell Pressure (@w -
Once/6 months N/A
- 11) Drywell Pressure (PS-64-588)
Once/6 months N/A sa Onts/6 months N/A
- 12) Drywell Temperature
. 5 5~2A
- g
~*
- 13) i;mer Once/6 months N/A
=-
- 14) CAO Tank Love
~
Once/6 months Once/ day L) Containment Atmosphere Monitors Once/6 months Once/ day n
TT1 to c>
tan
~
~
)
l MB02 M 3.5/4.5 CORE AND CONTAINMENT COOLING SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.5.C
- Service Water and v=arrenev 4.5.C
- Service Water==d w--rannev Eouinment Coolinn Water Syst*==
Eauia==nt Cooline Water Svata==
(ErcWs) (Continned)
(EECWS) (Continued) h,2.
During REACTOR POWER 2.
No additional surveillance OPERATION, RER3W ptmps is required.
I amat be OPERABLE sad j
assigned to service as l
indicated in Table 3.5-1 l
for the specified time limit _s._
j (u~ia)
) 3.
Durinsf(tEACTOR POWER 3.
Routine surveillance for OPERATION, both RER5W these ptamps is specified ptmps B1 and B2,normally in 4.5.C.1.
or alternately assigned to the RER heat exchanger 65"MC ' AT ED header supplying th standby VA AVES Coolant supply Connection must be OPre m.m except as specified in 3.5.C.4 and 3.5.C.5 below. 3 J
OTE. S ctAuss 57^ub LANT SUPPL $r CAPA%iLLW is
- OoM* TERM Rtcut%CMtMT, A
s A c.c spCMCN T 8S McT Ccs"sibERED 34 C PE R A% LC IF
'ub%4 cc o c AMT suPvt.y e AremetTy cA n %E Resroast te senvice 7 e4 cunt.)/
WLTHau arN 3.5/4.5-10 AMENDMENT NG.14 0 Unit 3
__________._______m
ENCLOSURE 3.
TENNESSEE VALLEY' AUTHORITY BROWN 8 FERRY NUCLEAR PLANT (BFN)
UNITS.1, 2, AND 3 i
PROPOSED TECHNICAL 8PECIFICATION (TS) CHANGE TS-351 I
REVISED'PAGES 1
i l
I.
hFFECTED.PAGE LIST Unit 1 Unit 2 Unit 3 l
3.5/4.5-10 3.5/4.5-10 3.2/4.2-30 3.2/4.2-53 l
3.5/4.5-10 l
k II.
REVISED PAGES See attached.
I F
F i
l P
i k
t t
I f
v
o i
3.5/4.5 CORE AND CONTATIDGENT COOLING SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEfttAMCE REOUIREhnn15 i';
3.5.C RHR Service Water and Emerrency 4.5 C RHR Service Water and Emerrency Eauiement Coolina Water Systems Eauinment Coolina Water Svsta==
LgECWS) (Continued)
(EECWS)-(Continued) 2.
During REACTOR POWER
- 2. No additional surveillance OPERATION, RHRSW pumps
-is required.
must be OPERABLE and assigned to service as indicated in Table 3.5-1 for the specified time limits.
i l
3.
During Unit 1 REACTOR POWER
- 3. Routine surveillance for OPERATION, both RHRSW these pumps is specified pumps D1 and D2 and in 4.5.C.1.
associated valves normally or alternately assigned-I to the RHR heat exchanger header supplying the standby coolant supply connection j
must be OPERABLE except as specified in 3.5.C.4 and 3.5.C.5 below. (Note Because standby coolant supply capability is not a-4 short-term requirement, a 1
component is not considered inoperable if standby coolant supply espability can be restored to service within 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.)
I i
i BPN 3.5/4.5-10 Unit 1
hd' i
t m-
'7, a
3.5/4.5 CORE AND CONTAIIDIENT COOLING SYSTEFIS
- M TIEC CONDITIONS FOR OPERAv10N
' SURVEff flWL*E RE0111RDMrfS 3.5.C -
RER Service Water and Emermancy 4.5.C RER Service Water and Emarzancy 9.; '
=,
Eauinment Coolina Water Systems Eauir = t cooline Water Syst -
(EECWS) (Continued)
(EECWS) (Continued) 2.-
During REACTOR POWER
- 2. No additional surveillance OPERATION, RERSW pumps is required.
must be OPERABLE and assigned to service as indicated in Table 3.5-1 for the specified time limits.
,3.
During Unit 2 REACTOR
- 3. Routine surveillance for POWER OPERATION,-any two these pumps is specified l
l.;
.RERSW pumps-(D1, D2, B1, in 4.5.C.1.
and 82) and associated y
valves normally or alternately assigned to the RER heat exchanger header supplying the standby coolant supply connection must be OPERABLE except as specified.in 3.5.C.4 and 3.5.C.5 below.
(Notes Because standby coolant supply capability is not a short-term requirement, a component is not' considered inoperable if standby coolant supply capability can be restored to service within 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.)
i 1
l BPR 3.5/4.5-10
' Unit 2 c=
m_j. :- - -
_;p.
~ g
- :4
.e:~
TABLE 3.2.F c to Surveillance Instrumentation Minimum # of
~
Operable Instrument Type Indication Channels Instruenot #
Instrument and Ranee Notes 2
LI-3-46 A Reactor Water Level Indicator - 155" to (1) (2) (3)
LI-3-46 B 40" 2
PI-3-54 Reactor Pressure Indicator 0-1500 psig (1) (2) (3)
PI-3-61 2
XR-64-50 Drywell Pressure Recorder -15 to 45 psig (1) (2) (3)
PI-64-678 Indicator -15 to 45 psig l
2 XR-64-50 Drywell Temperature Recorder. Indicator (1) (2) (3)
TI-64-52A8.
0-400*F l
1 XR-64-52' Suppression Chamber Recorder 0-400"F (1) (2) (3)
Air Temperature w
- w 1
N/A Control Rod Position 6V Indicating
)
)
Lights
)
(1) (2) (3) (4) 1~
N/A Neutron Monitoring SRM, IRM, LPRM
)
.y 0 to 100% power
)
w O
1 PS-64-678 Drywell Pressure
- Alarm at 35 psig
)
l.
)
1 TS-64-52A &
Drywell Temperature Alarm if temp.
)
PIS-64-58A &
and Pressure and
> 281"F and
)
(1) (2) (3) (4)
IS-64-67A Timer pressure >2.5 psig )
after 30 minute
)
delay
)
1 LI-84-2A CAD Tank "A" Level Indicator 0 to 1001 (1) 1 LI-84-13A CAO Tank "B" Level Indicator 0 to 1001 (1) m s- -
.- m m
- v..m
. =
- m. -
+
4 y-
'..U, m
..y.-
m
.,,5 y
-...m.
e.,.
.,-.c
"-~
y 7:3..
?
.. }
t TABLE 4.2.F MINIPRJM TEST AND CALIBRATION FREQUENCY FOR SURVEILLANCE INSTRUMENTATION e es D@
Instrument Channel Calibration Freauency Instrument Check r
- 1) Reactor Water Level Once/6 months Each Shift.
u
- 2) Reactor Pressure Once/6 months Each Shift
- 3) Drywell Pressure Once/6 months Each Shift
- 4) Drywell Temperature Once/6 months Each Shift
- 5) Suppression Chamber Air Temrature Once/6 months' Each Shift
- 8) Control Rod Position N/A~
Each Shift Each Shift
- 9) Neutron Monitoring (2) l
- 10) Drywell Pressure (PS-64-678)
Once/6 months N/A
- 11) Drywell Pressure (PS-64-588)
Once/6 months N/A l
- 12) Drywell Temperature (TS-64-52A)
Once/6 months N/A P'
- 13) Timer (IS-64-67A)
Once/6 months N/A
'l' u
[
- 14) CAD Tank Level
'Once/6 months Once/ day Y
- 15) Containment Atmosphere Monitors Once/6 months Once/ day Y
.h
-t-a a m1 u.h-w e
be-s weeya
-we-.-
-w--.
m w
e
. sis.
e
..v.--e-immy y-imp r1
.....w.
w~
---g,myi-.we.g.-gg-me v
u.
-+re e,t g,.
p
---gng w
- ~.
3'5/4.5 ' CORE AND ColtrATEMENT COOLING SYSTEM.4-f t
. LIMITING CONDITIONS FOR OPERATION-SURVETT.t.anCE REOUIREMENTS
.3.5.C
- n Service Water mad Emerzenev 4.5.C RHR Service Water and Emeraency Eaui= ant Coolina Water Svata==
Eauinment Coolina Water Synta==
(EECWS) (Continued)
,(EECWS) (Continued)
[
-2.
During' REACTOR' POWER 2.
No additional surve111ance-OPERATION, RER3W pumps
.is required.
must be OPERABLE and i
assigned to service as L
. indicated in Table 3.5-1 for the specified time r
f limits.-
1 5
5 l
3.
During Unit 3 REACTOR POWER 3.
Routine surveillance for OPERATION, both RHRSW these pumps is specified.
i pumpa B1 and B2 and associated in 4.5.C.1.
valves normally or alternately assigned to the RER heat exchanger header supplying i
the standby coolant supply connection must be OPERABLE except as specified in 3.5.C.4 and 3.5.C.5 below.
(Notes Because standby coolant supply capability is not a short-term requirement, a l
component.is not considered inoperable if standby coolant supply. capability can be j
restored to service within j
5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.)
g
-I l
BFN 3.5/4.5-10 Unit 3
. l
.1