ML20125C224
| ML20125C224 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 12/08/1992 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20125C214 | List: |
| References | |
| NUDOCS 9212110101 | |
| Download: ML20125C224 (16) | |
Text
__ _
l i
ENCLOSURE 5 l
BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKET NOS. 50-325 & 50-324 OPERATING LICENSE NOS. DPR 71 & DPR-62 REQUEST FOR LICENSE AMENDMENT NEUTRON MONITORING SURVEILLANCE REQUIREMENTS 1
IECHNICAL SPECIFICATION PAGES UNIT 1
-i 9212110101 921208 PDR ADOCK 05000324
.P pop
TABLE 4.3.1-1 (Continued)_
REACTOR PROTECTION SYSTEH INSTRUMENTATION SURVE1LLANCE REQUIREM NOTES (a) Neutron detectors may be excluded f rom CHAh*NEL CALIBRATION.
(b) Within 44 hours5.092593e-4 days <br />0.0122 hours <br />7.275132e-5 weeks <br />1.6742e-5 months <br /> prior to startup, if not performed within the previous 7 days.
(c) The IRH channels shall be compared to the APRH channels and the SRM instruments for overlap during each startup, if not performed wir.hin the previous 7 days.
(d) When changing from OPERATIONAL CONDITION 1 to OPERATIONAL CONDITION 2, perform the required survelliance within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering OPERATIONAL CONDITION 29 j[d for ggg fgg Mg yfq iYelGyS*
(e) This calibration shall consist of the adjustment of the APEH readout to conform to the power values calculated by a heat balance during OPERATIONAL CONDITION 1 when THERMAL POWER is greater than or equal _ to 25%
of RATED THERMAL POWER.
(f) This calibration shall consist of the adjustment of the APRM flow-biased setpoint to conform to a calibrated flow signal.
(g) The LPRHs shall be calibrated at least once per effective full power month (EFpM) using the TIP system.
(h) This calibration shall consist of a physical inspection and actuation of these position switches.
(i) Instrument alignment using a standard current source.
(j) Calibration using a standard radiation source.
(k) The transmitter channel check is satisfied by the trip unit channel check. A separate transmitter check is not required.
(1) Transmitters are exempted from the monthly Lannel calibration.
(m) Placement of Reactor Mode Switch into the Startup/ Hot Standby position is permitted for the purpose of performing the required surveillance prior to withdrawal of control rods for the purpose of bringing the reactor to criticality.
(n) placement of Reactor Mode Switch into the Shutdown or Refuel position is permitted for the purpose of performing the required surve'111ance provided all control rods are fully inserted and the vesset heau oolts are-tensioned.
(o) Surveillance is not required when THERMAL POWER is less than 30% of RATED THERMAL POWER.
BRUNSWICK - UNIT 1 3/4 3-9 Amendment No.130
s
. ~.
N 5
TABLE 4.3.4-1 n.
' E y
_ CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION SURVEILLANCE REQUIREMENTS i
E OPERATIONAL M
CHANNEL CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN VdICH SURVEILLANCE REQUIRED !
CALIBRATION TRIP FUNCTION CHECK TEST
+
3.
1.
APRM S/U((C}
R(b)(a) y Upscale (Flow Biased)
NA b.
Inoperative NA S/U
,Q(f) a.
C NA 1, 2, 5 c.
Downscale NA S/U N
1 C
k R
2, 5 d.
Upscale (Fixed)
NA S/U
,Q I
2.
ROD BLOCK HONITOR S/U(IC),H R(*)
1((E)
C}
a.
Upscale NA S/U(C},Q NA )
1(8}
b.
Inoperative NA l
E)
E" 1
S/U
,M t'
c.
Downscale NA e
y 3.
SOURCE RANCE MONITORS NA 2, 5 l
I (d)
S/U(C) 3 C},WC)
Detector not full in NA a.
S/U(C),W(d NA 2' 5 S/U b.
Upscale.
NA I
d)
NA 2, 5 C),W(d)
Inoperative' NA c.
S/U
,W NA 2, 5 d.
Downscale NA 4
4.
INTERMEDIATE RANCE MONITORS C)(*),W(d)
NA 2
[
Detector not full in NA S
a.
NA W
NA 5
Cd) b.
Upscale' NA S/U(C},W NA 2
NA W
NA 5
g m
E Inoperative NA S/U(C},W(d)
NA
,2 c.
b NA W
NA 5
o S/U(C},W(d)
NA 2
7 d.
Downscale NA NA W
NA 5
H 5.
I, 2, 5(h) a.
Water Level - High NA Q
2 i
.,.. i.
TABLE 4.3.4-1 (Continued)_
CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION SURVEILLANCE REQUIREMENTS I
NOTES (a) CHANNEL CALIBRATIONS are electronic.
(b) This calibration shall consist of the adjustment of'the APRH flow biased setpoint to conform to a calibrated flow signal.
(c) Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to startup, if not performed within the previous 7 days.
(d) When changing from OPERATIONAL CONDITION 1 to OPERATIONAL CONDITION 2, perform the required survelliance within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering OPERATIONAL CONDITION 2,if not pep [or med WIYbin MP freVl045 7 days.
(c) Place:nent of Reactor Mode Switch into Startup/ Hot Standby position is permitted for the purpose of performing the required surveillance prior to withdrawal of control rods for the purpose of bringing the reactor to criticality.
(f) Placement of Reactor dode Switch into the Shutdown or Refuel position is permitted for the purpose of performing the required survelliance provided all control rods are fully inserted and the vessel head bolte are tensioned.
(g) When THERMAL POWER is greater than the preset. power level of the RWH and RSCS.
(h) With any control rod withdrawn. Not applicable co control rods removed per Spccification 3.9.10.1 or 3.9.10.2.
(0 When ahandsM frotn CPE84710NAL C6MbtT76NL le 6PERA7loNAl-a CONomoN 2, febem b rquired surveilhve wldin 12 houn aRer enlerug CPERATl6NAL CoNDITloN2,ilnd f 0f!'WY Wl$0M h lTV/0t]$
kg) f f,
BRUNSWICK - UNIT 1 3/4 3-52 Amendment No. 130
i ENCLOSURE 6 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 l
NRC DOCKET NOS, 50 325 & 50-324 OPERATING LICENSE NOS. DPR 71 & DPR 62 REQUEST FOR LICENSE AMENDMENT NEUTRON MONITORING SURVEILLANCE REQUIREMENTS
- i TECHNICAL SPECIFICATION PAGES UNIT 2 -
e P
T l
L
.o l
r l
..-e.
,,u,._
.-.n.
TABLE 4.3.1-1 (Continued)
REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS NOTES (a) Neutron detectors may be excluded from CHANNEL CALIBRATION.
(b) Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to startup, if not performed within the previous 7 days.
(c) The IRM channels shall be compared to the APRM channels and the SRM instruments for overlap during each startup, if not performed within the previous 7 days.
(d) When changing from OPERATIONAL CONDITION 1 to OPERATIONAL CONDITION 2, perform the required surveillance within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering OPERATIONAL CONDITION 23 (( nof phr'med WidbIn Ybd f FC VlOd3 T c$Rf.s.
(e) This calibration shall consist of the adjustment of the APRM readout to conform to the power values calculated by a heat balance during OPERATIONAL CONDITION 1 when THERMAL POWER greater than or equal to 25% of RATED THERMAL POWER.
(f) This calibration shall consist of the adjustment of the APRM flow-blased setpoint to conform to a calibrated flow signal.
(g) The LPRMs chall be calibrated at 1 cast once per ef fective full power month (EFPM) using the TIP system.
(h) This calibration shall consist of a physical inspection and actuation of these position switches.
(i) Instrument alignment using a standard current source.
(j) Calibration using a standard radiation source.
(k) The transmitter channel check is satisfied by the trip unit channel check. A separate transmitter check is not required.
(1) Transmitters are exempted from the monthly channel calibration.
(m) Placement of Reactor Mode Switch into the Startup/ Hot Standby position is permitted for the purpore of performing the required surveillance prior to withdrawal of control rods for the purpose of bringing the reactor to criticality.
(n) Placement of Reactor Mode Switch into the Shutdo or Refuel position is permitted for the purpose of performing the required surveillance provided all control rods are fully inserted and the vessel head bolts are tensioned.
(o) Surveillance is not required when THERMAL POWER is less than 30% of RATED THERMAL POWER.
BRUNSWICK - UNIT 2 3/4 3-9 Amendment No. 160
1,
- t f
'E TABLE 4.3.4-1 i
E j
CONTROL ROD WITHDRAWAL BIDCK INS'IllUMENTATION SURVEILLANCE REQUIREMENTS l
E CHANNEL OPERATIONAL W
s CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN VdICH CHECK TEST CALIBRATION SURVEILLANCE REQUIRED
@ TRIP FUNCTION f
G 1
1.
APEM I
R(b)(a) g S/U(C)cMy,q(f) u.
Upscale (Flow tsiased)
NA a.
NA 1, 2, 5 S/U(C) b.
Inoperative NA 1
S/U(C)(
W)(f)Nga) c.
Downscale NA S/U
,Q R
y, 3 d.
Upscale (Fixed)
NA I
i 2.
ROD BLOCK HONITOR R(a) g(g) j S/U((c)M a.
Upscale NA S/U(C),Q 1(8)
I c.
Downscale NA S/U C),M Npa) g(g) b.
Inoperative NA R
j y
3.
SOURCE RANCE MONITORS I
)
S/U(C)
S/U(C),W((dS/U(C),W(d NA 2, 3 Detector not full in NA
)
a.
NA 2' 5 b.
Upscale NA d}
,W NA 2 $
. Inoperative NA S/U C)
Id) c.
,W NA 2, 5 d.
Downscale NA l
4.
INTERMEDIATE RANCE MONITORS c)(e),g(d) a.
Detector not full in NA S
NA 2
NA W
NA l
S/U(C),W(d)
NA 2
b.
Upscale NA E
NA W
NA l
S/U(C),W(d) c.
Inoperative NA NA 2
NA W
NA S/U(c),y(d)
NA 2
d.
Downscale.
NA
.NA W
NA 5.
1, 2, $(h) a.
Water Level - High NA Q
R
=
TABLE 4.3.4-1 (Continued)
CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION SURVEILLANCE REQUIREMENTS NOTES (a) CilANNEL CALIBRATIONS are electronic.
(b) This calibration shall consist of the adjustment of the APRM flow biased setpoint to conform to a calibrated flow signal.
(c) Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to startup, if not performed within the previous 7 days.
(d) When changing from OPERATIONAL CONDITION 1 to OPER'ATIONAL CONDITION 2, perform the required surveillance within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering o E AT OHAL CONDITION 29 if not ppforry& gr}{l tin &
reViellS f
(c) Placement of Reactor Mode Switch into Startup/Ilot Standby position is permitted for the purpose of performing the required surveillance prior to withdrawal of control rods for the purpose of bringing the reactor to criticality.
(f) Placement of Reactor Mode Switch into the Shutdown or Refuel position is permitted for the purpose of performing the required surveillance provided all control rods are fully inserted and the vessel head bolts are tensioned.
(g) When THERMAL POWER is greater than the preset power level of the RWM and RSCS.
(h) With any control rod withdrawn. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.
$) When chan9ng rern MERATl0NAL CONDmot k OPERGIMAL f
CONDITl0N2, prform 4he quired surveillance within i2 hours alder enteriny OPERATioNhL CONblT1oN 2,if na+
perf6rmed gthin 4h y,,% 92 Q.
BRUNSWICK - UNIT 2 3/4 3-52 Amendment No.160
S ENCLOSURE 7 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKET NOS. 50 325 & 50 324 i
OPERATING LICENSE NOS. DPR 71 & DPR-62 REQUEST FOR LICENSE AMENDMENT NEUTRON MONITORING SURVEILLANCE REQUIREMENTS i
TYPED TECHNICAL SPECIFICATION PAGES - UNIT 1 l
J.
b i
d l
L j..
l~
l..(
~
-. ~
TABLE 4.3.1-1 (Continued)
REACTOR PROTECTION SYSTEM INSTRUMFNTATION SURVEILIANCE REQUIREMENTS NOTES (a)
Neutron detectors may be excluded from CHANNEL CALIBRATION.
(b)
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to startup, if not. performed within the previous 7 days.
(c)
The IRM channels shall be compared to the APIU4 channels and the SRM instruments for overlap during each startup, if not performed within the previous 7 days.
(d)
When changing from OPERATIONAL CONDITION 1 to OPERATIONAL CONDITION 2,
~
perform the required surveillance within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering OPERATIONAL CONDITION 2, if not performed within the previous 7 days.
l (e)
This calibration shall consist of the adjustment of the APRM readout to a heat balance during conform to the power values calculated by OPERATIONAL CONDITION 1 when THERMAL POWER greater than or equal to 25% of RATED THERMAL POWER.
l (f)
This calibration shall consist of the adjustment of the APRM flow-biased setpoint to conform to a calibrated flow signal.
(g)
The LPRMs shall be calibrated at least once per ef fective full power month (EFPM) using tha TIP system.
(h)
This calibration shall consist of a physical inspection and actuation of these position switches.
(i)
Instrument alignment using a standard current source.
(j)
Calibration using a standard radiation source.
(k)
The transmitter channel check is satisfied by the trip unit channel check.
A separate transmitter check is not required.
(1)
Transmitters are exempted from che monthly channel calibration.
(m)
Placement of Reactor Mode Switch into the Startup/ Hot Standby position is permitted for the purpose of performing the required surveillance prior to withdrawal of control rods for the purpose of bringing the reactor to criticality.
(n)
Placement of Reactor Mode Switch into the Shutdown or Refuel position is l
permitted for the purpose of performing the required surveillance provided all control rods are fully inserted and the vessel head bolts are tensioned.
(o)
Surveillance is not required when THERMAL POWER is less than 30% cf RATED THERMAL POWER.
BRUNSWICK - UNIT 1 3/4 3-9 Amendment No.
I
i P
E TABLE 4.3.4-1 a
E CONTROL ROD WITHDRAWAL SLOCK INSTRUMENTATION SURVEILIANCE REQUIREMENTS j
4
.o i
W CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH I
5 TRIP FUNCTION CHECK TEST CALIBRATION SURVEILIANCE REOUIRED
'[
l D
1
-+:
i
'A S/U(c)
R(b)(a) 1 l
a.
-Upscale (Flow Biased)
NA l
b.
Inoperative NA S/U
,Q NA 1, 2, 5 l
1 c.
Downscale bA S/U Ng d.
Upscale (Fixed)
NA S/U
,Q R
2, 5 1-2.
ROD BLOCK MONITOR a.-
. Upscale NA S/U
,M R("}'
1 E 5.'
j b.
. Inoperative.
.NA S/U
,Q Ng 1
)
c.
Downscale NA S/U
,M R
1
.w i,
D j.
3.
SOURCE RANGE MONITORS
.u S/U(c),W(d)
. 6, a.
Detector not full in
' NA.
NA 2, 5 S/U(
,W(g).
r b.
Upscale NA NA 2, 5 I-c.
~. nope ra tive NA S/U
,W NA 2, 5 d
j-d.
,Ocenscale NA-S/U
,W NA 2, 5 i;
4 INTERMEDIATE RANGE MONITORS Sg)(}(*},W( }
a.
Detector not full'in NA NA 2
i NA W
NA 5
4 f
S/U("},W( )
b.
Upscale NA NA 2
NA W
NA 5
S/U(#
,W NA 2
c.
Inoperative NA NA W
NA 5
l
,n-i 4
4 S/U(c),W(d) t d.
.Downscale-NA NA 2
[
NA V
NA 5
.5.
SCRAM DISCHARGE VOLUME-i 1,'2, 5( }
~
a.
Water Level - High NA _
Q R'
m 4
..... ~.,,
m
e' T
TABLE 4.3.4-1 (continuedl
~
CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION
_ g.-
[ M" y
SURVEILIMiCE REQUIREMENTS
.)[
_ 2 NOTES 2 ^"
'a)
CHANNEL CALIBRATIOF' are electronic.
1:..
D This calioration shall consist of the adjustment of the APkM flow biased setpoint to conform to a calibrated f?ow signal.
<*w g$
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to startup, if not parformed within the previous
,.N 7 days-4 3
When changing from OPERATIONAL CONDITION 1 to OPERATIONAL CONDITION 2, pcrform he required surveillance within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> af ter entering OPERATIONAL O
C0"DITIL:
2, if nnt crformed within the previot.s 7 days.
l 9
tt, (e)
Placement of Reactor Mc de Switch into Startup/P.ot Standby position t
N' permitted for the pt pise of performing the required surveillance p to 4J withdrawal of control rods for the purpose of bringing the reactor l*
criticality.
7; s
- D
( f)
Placement of Reactor Mode Switch into the h ~own or Refuel position is permitted for the purpose of perfor
.'!, th. 1 pired surveillance proviCed all control rods are fully inserte d
.a e 7:
31 head bolts are tensioned.
i (g)
Whe t.
POWER is greater that..ae preset pover level of the RWM and RSCS.
i (h,
With any control red withdrawn.
Not applicable to control rods removed per Speci.1 cation 3.9.10.1 or 3.9.10.2.
(i)
When char.ging from OPERATIONAL CONDITION 1 to OPERATIONAL CONb1 TION 2, perfora the required surveillance withis. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> af ter entering OPEPJ.TIONAL CONDITION 2, if nct performed within the previous 92 days.
4 Nrj;.
E e>
r
?At 1,$
N m,
BRUNSWICK - UNIT 1 3/4 3-52
.Wendment No.
g m.. ;
z
a ENCLOSURE 8 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKET NOS. 50-325 & 50-324 OPERATING LICENSE NOS. DPR 71 & DPR 62 REQUEST FOR LICENSE AMENDMENT NEUTRON MONITORING SURVEILLANCE REQUIREMENTS TYPED ]ECHNICAL SPECIFICATION PAGES - QML2
- s b;
?"
TABLE 4. 3.1 - 1 (Continued) r REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS NOTES I
(a)
Neutron detectors may be excluded from CHANNEL CALIBRATION.
(V Uit hin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to startup, if not performed within the pu vious 7 days.
r-(c)
The IRM channels shall be c ompa re c' to the A.
channels and the SRM instruments for overlap during each startup, i#
t performed withu. t%
previous 7 days.
(d)
V en changing f rom OPERATIONAL CONDITION 1 to OPERATIONAL CONDITION 2,
^
perform the required surveillance within 1.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> after e nt e ri ng OPERATIONAL CONDITION 2, if not performed within the previous 7 days.
(e)
This calibration shall consist of the adj us tmant of the APRM readout to conform to the power values calcule ed by a heat balance during
[
OPERATIONAL CONDITION 1 when THERMAL PNER greater than or equal to 2% of RATED THERMAL POWER.
(
This calibration shall consist of the adjustment of the APRM flow-biased
- etpoint to conform to a calibrated flow signal.
(g)
The LIJMs shall be calibrated at least once per ef fective full power month (EFPM) using the TIP system.
(h)
This calibration shall consist of a physical inspection arc actuation of these position switches.
~
(i)
Instrument alig u nt using a standard current tource.
(j )
Calibration using a standar, radiation source.
(k)
The transmitter channel check is satisfied by the trip unit channel check A separate transmitter check i.s not required.
(1)
Transmitters are exempted from the monthly channel calibration.
(m)
Placement of Reactor Mode Swl tch into the Startup/ dot Standby positi m is permitted tor the purpose of perfcrming the required surveillance prior to withdrawal of control rods for the purpose of bringing the reactor to p-crit icality.
(n)
Placement of Reactor Mode Sw;tch into the Shutdown or Refuel position is permitted for the purpose of pel forming the requirad surveillance provided ali control rods are fully inserted and the vessel head bolts are tensioned.
(o).
Surveillance is not required when THERMAL POWER ir less than 30% of RATED THERMAL POWER.
L BRUNSWICK - I' NIT 2 3/4 3-9 Amendment No.
7,... - - _
.,, ; y, r.
TABLE 4.3.4.,
si y
CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION SURVEILLANCE REQUIREMENTS
-- X -
CHAN'IEL OPERATIONAL CHANNEL FUNCTIONAL-CHANNEL CONDITIONS IN WHICH TRIP FUNCTION
_ CHECK TEST CALIBRATION SURVEILIANCE ' REC 11 RED 1.
APRM y
}("}
'a.
Upscale (Flow Biased)
NA S/U R
l I
b.
' Inoperative NA S/U
,Q NA-1,2,5 c.
-Downscale-NA S/U y
Ng 1
d.
--Upscale (Fixed)
NA S/U
,Q R
2 5-2.
-ROD BLOCK MONITOR
. l' S/U( }
-R(" -
1(E a.
Upscale NA
,M S/U(#},Q T'
.1(E)
.b.
Inoperative
.NA S/U( }
,M R'"
1(E w
c.
.Downscale-NA
'E -
- 3.
SOURCE RANGE MONITORS u
S/U(#},W( }
Detectcr not ful'1 in NA Y
NA 2, 5 a.
S/U(
,W NA 2, 5 b.
. Upscale.
NA c.
Inoperative NA S/U
,W NA 2, 5 d.
Downscale NA S/U
,W NA 2
-5
.f
'4.
INTERMEDI ATE PANGE MONITORS
. }(*},U(d)
NA
'2 Det5etor not full in NA S
a.
NA W
NA 5
S/U(#},W(d) b.
Upscale NA NA 2-NA W-NA 5
i S/U'c),W(d)
I c,
Inoperative.
NA NA 2
g.
NA
.W.
NA 5
- s Sfd(c),W(d)
NA 2
. 'd.
'Downscale NA
. R..
.NA'
.W-NA -
5 5.
- i a.
Water Level
.High-NA
.Q
'R
'l', ' 2, : 5 (h)
[5 2..
.., ~. -
- '*~' -*
TABLE 4.3;4-1 iContinued)-
CONTROL ROD WITH9RAVAL BIDCK INSTRUMENTATION SURVEILLANCE REQUIREMENTS NOTES (a)
CHANNEL' CALIBRATIONS are electronic.
(b)
This calibration shall consist of the adjustment of the APRM flow biased setpoint to conform to a calibrcted flow signal.
(c)
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to startup, if not performed within the previous 7 days.
(d)
When changing from uPERATIONAL CONDITION.1 to OPERATIONAL CONDITION 2, perform the required surveillance within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering OPERATIONAL CONDITION 2, if not performed within ti,e previous 7 days.
l-(e)
Placement of-Reactor Mode Switch into Startup/ Hot Standby _ position is permitted for the purpose of performing the require'd surveillarce prior to?
withdrawal of control reds for the purpose of bringing the reactor to criticality, (f)
Placement of Reactor Mode Switch into the Shutdown or Refuel position is permitted for the purpose of performing the required surveillance provided all control rods Arc fully iaserted and the vessel head bolts are' tensioned.
(g)
When THERMAL POWER in greater than the preset power level of the RWM and:
RSCS.
i th)
Vith any control rod withdrawn.
Not applicable to control rods removed per-Specifi cation 3. 9 - 10.1 or 3. 9.10.2, (1)
When changing from OPERATIONAL CONDITION 1 to OPERATIONAL CONDIT10'N 2,
.l perform the required surveillance within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ' af ter entering OPERATIONAL CONDITION 2, if w t performed within the previous 92 days.
L
- \\
l BRUNSWICK - UNIT 2.
3/4 3-52 Amendment No.
e
.m
&,, v.
.c
.~An.,0.-
a
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