ML20129A428
| ML20129A428 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 07/01/1985 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20129A323 | List: |
| References | |
| NLS-84-143, NUDOCS 8507150295 | |
| Download: ML20129A428 (12) | |
Text
,.
ENCLOSURE 1 SERIAL: NLS-84-143 Brunswick Steam Electric Plant Proposed Technical Specification Pages - Unit 1 (CP&L Serial: 34TSB14) i l.
8507150295 850701 PDR ADOCK 05000324 P
pg (9786 MAT /ccc)
L
Summary List of Revisions Brunswick Unit 1 -
Page Comment 3/43-7 Item 1.a -
added weekly surveillance requirement to the channel functional test Item 1.b -
added note (d) to channel functional test surveillance requirement Item 2.a -
added note (m) to startup and note (n) to weekly (operational condition 5) surveillance requirements Item 2.d -
added notes (m) and (n) to the channel functional test surveillarice requirements 3/4 3-8a Notes (d) and (e) - changed " CONDITION" to
" OPERATIONAL CONDITION" Note (e) -
">" change to " greater than or equal to" Notes (m) and (n) - new notes added 3/4 3-43 Item 1.b -
added note (e) to startup and (f) to quarterly channel functional test surveillance requ,rement i
Item l.d -
added note (e) to startup and (d) and (f)
~
to quarterly channel functional test surveillance requirement Item 3.a/b/c/d - added note (d) to weekly channel functional test surveillance requirement Item 4.a -
added note (e) to startup and note (f) to weekly (operational condition 5) channel functional test surveillance requirement 3/4 3-43a Note (d) -
" CONDITION" changed to
" OPERATIONAL CONDITION" Notes (e) and (f)- new notes added (9786 MAT /ccc )
(BSEP-1-32)-
TABLE 4.3.1-1 m
so h
REACTOR PROTECTION SYSTEM INSTRUMENTATION ~ SURVEILLANCE REQUIREMENTS s
CHANNEL OPERATIONAL Q
FUNCTIONAL UNIT CHANNEL FUNCTIONAL CHANNEL-CONDITIONS IN WHICH CALIBRATION (a)
SURVEILLANCE REQUIRED i
AND INSTRUMENT NUMBER CHECK TEST g
1.
(C51-IRM-K601A,B,C,D,E,F,C,H)
.a.
Neutron Flux - High D
S/U(b)(c), g(d)
R 2
D W
R 3,4,5 b.
Inoperative NA W(d)
NA 2,3,4,5 2.
Average Power Range Monitor:
(C51-APRM-CH.A,B,C,D,E,F) a.
Neutron Flux - High 15%
S S/II(b)(m), g(d)
Q 2
l W ")
Q 5
I 4
S b.
Flow-Biased Neutron Flux - High S
S/U(b),y g(e)(f),q, y
c.
Fixed Neutron Flux - High, 120%
.S S/U(b),y g(e),q g
W ")I")
NA 1, 2, 5 I
d.
Inoperative NA I
e.
Downscale NA W
NA 1
f.
LPRM D
NA (g) 1, 2, 5 3.
Reactor Vessel Steam Dome Pressure - High II) g (B21-PT-NO23A,B,C,D)
NA(k). NA R
1, 2 e.
E.
(B21-PTM-NO23A-1,B-1,C-1,D-1)
D M
M 1, 2 0
E 4.
z Low, Level 1 II)
(B21-LT-N017A-1,B-1,C-1,D-1)
NA(k) NA R
1, 2 (B21-LTM-N017A-1,B-1,C-1,D-1)
D M
M 1, 2
(BSEP-1-32).
to
' TABLE-4.3.1-1 (Continued)
E!
REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS A
(a) Neutron detectors may be excluded from CHANNEL CALIBRATION.
e
?
(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'esch 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.
(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 is greater than or equal to 25% of RATED THERMAL PC'.22R.
Y (f) This calibration shall consist of the adjustmerit of the APRM flow-biased setpoint to conform to a f
calibrated flow signal.
(g) The LPRMs 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 1 source.
(j) Calibration using a standard radiation source.
(k) The transmitter channel check is satisfied by the trip unit channel check. A separate transmitter y
check is not required.
E I
(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 purpose of performingc 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 surveillance provided all control rods are fully inserted and the vessel head bolts are tensioned.
(BSEP-1-32)
TABLE 4.3.4-1 m
- =
h CONTROL ROD WITHDRAWAL BIACK INSTRUMENTATION SURVEILLANCE REQUIREMENTS s
Q CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL-CONDITIONS IN WHICH, TRIP FUNCTION AND INSTRUMENT. NUMBER CHECK TEST CALIBRATION SURVEILLANCE REQUIRED g
1.
APRM (C51-APRM-CH.A,B,C,D,E,F)
M R(b)(a) y S/U((c) a.
Upscale (Flow Biased)
NA S/U(c)(E),q(f)
NA 1, 2, 5 l
b.
Inoperative NA S/U(c)
,q(d)(f) yR a) 2, 5 l
g c.
Downscale NA S/U c)(d d.
Upscale (Fixed)
NA 2.
ROD BLOCK MONITOR (CSI-RBM-CH.A,B)
S/U((c)
R(*)
1*
S/U(c),H w
a.
Upscale NA y
g, 2
b.
Inoperative NA S/U c),q a)
,M R
g, o
c.
Downscale NA L
3.
SOURCE RANCE MONITORS (C51-SRM-K600A,B,C,D)
S/U(c)
(d) a.
Detector not full in NA NA 2, 5 S/U(c),y(d)
NA 2, 5 S/U(C},y(d) b.
Upscale NA c.
Inoperative NA NA 2, 5 S/U(c),W(d)
,y NA 2, 5 d.
Downscale NA 4.
INTERMEDIATE RANCE MONITORS (C51-IRM-K601A,B,C,D,E,F,G,H) c)(e),y(d)
NA 2
l a.
Detector not full in NA S
NA W
NA 5
g b.
Upscale NA S/U(c),y(d)
NA 2
3 NA W
NA 5
a c.
Inoperative NA S/U(c),y(d)
NA 2
NA W
NA 5
d.
Downscale NA S/U(c),y(d)
NA 2
NA W
NA 5
(BSEP-1-32)'
TABLE 4.3.4-1 (Cont'd)
E E
CONTROL ROD WITHDRAWAL BIDCK INSTRIDGENTATION SURVEILLANCE REQUIREMENTS "c
H CHANNEL OPERATIONAL i
l Q
CHANNEL FUNCTIONAL CHAIRIEL CONDITIONS IN WHICH-CALIBRATION *)
SURVEILLANCE REQUIRED-I j
i TRIP FUNCTION AND INSTRUMENT NIDiBER CHECK TEST i
g m
l H
5.
SCRAM DISCHARCE VOLUME (C11-LSH-N013E) j R
1, 2, 5**
Water Level - High NA Q
a.
When THERMAL POWER is greater than the preset power level of the RWH and RSCS.
With any control rod withdrawn. Not applicable to control rods removed per l
l Specification 3.9.10.1 or 3.9.10.2.
(a) CHANNEL CALIBRATIONS are electronic.
(b) This calibration shall consist of the adjustment of the APRM flow biased setpoint w
to conform to a calibrated flow signal.
j 2
(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.
w l
5-(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.
i E
(e) Placement of Reactor Mode Switch into the Startup/ Hot Standby position is permitted for the purpose of l
performing the required surveillance prior to withdrawal of control rods for the purpose of bringing l'
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 l
bolts are tensioned.
i 4
i
(
i 5
1 s
g, Ra rr j
1 i
I-4 i
_= _
I
=
P ENCLOSURE 2 SERIAL: NLS-84-143
. Brunswick Steam' Electric Plant t
Proposed Technical Specification Pages - Unit 2 (CP&L Serial: 84TSB14) 4 L
1 (9786 MAT /ccc)
I v w ne,e mw,-.
i.
w e v.,+.w..
..w,,.,_.
w,,_,,-%,,,,..~,,-.,w,%,_.w
_-,,.,,,-,,-c,c,,.ww w, rew
-,my -. w w
....-.4-.-..~,,e.-
s..
Summary List of Revisions j
Brunswick Unit 2 Pag Comment 3/43-7 Item 1.a -
added weekly surveillance requirement to the channel functional test Item 1.b -
added note (d) to channel functional test surveillance requirement Item 2.a -
added note (m) to startup and note (n) to weekly (operational condition 5) surveillance requirements Item 2.d -
added notes (m) and (n) to the channel functional test surveillance requirements 3/4 3-8a Notes (d) and (e) - changed " CONDITION" to
" OPERATIONAL CONDITION" Note (e) -
">" change to " greater than or equal to" ~
Notes (m) and (n) - new notes added 3/4 3-43' Item 1.b -
added note (e) to startup and (f) to quarterly channel functional test surveillance requirement Item 1.d -
added note (e) to startup and (d) and (f) to quarterly channel functional test surveillance requirement Item 3.a/b/c/d - added note (d) to weekly channel functional test surveillance requirement Item 4.a -
added note (e) to startup and note (f) to weekly (operational condition 5) channel functional test surveillance requirement 3/4 3-43a Note (d) -
" CONDITION" changed to
" OPERATIONAL CONDITION" Notes (e) and (f) - new notes added (9786 MAT /ccc)
(BSEP-2-32)
IABLE 4.3.1-1
_w REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS s
Q CHANNEL OPERATIONAL FUNCTIONAL UNIT CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH
.i AND INSTRUMENT NUMBER CHECK TEST CALIBRATION (a)
SURVEILLANCE REQUIRED H
1.
(C51-IRM-K601A,B,C,D,E,F,C,H)
N a.
Neutron Flux - High D
S/U(b)(c), g(d)
R 2
D W
R 3,4,5 Id)
NA 2,3,4,5 b.
Inoperative NA W
2.
Average Power Range Monitor:
(C51-APRM-CH.A,B,C,D,E,F) w w
a.
Neutrou Flux - High 15%
S S/U(b)(m), g(d)
Q 2
W ")
Q 5
I S
b.
Flow-Biased Neutron Flux - High S
S/U(b),y g(e)(f),q, y
c.
Fixed Neutron Flux - High, 120%
S S/U(b),y g(e),Q l
W ")I")
NA 1, 2, 5 I
d.
Inoperative NA e.
Downscale NA W
NA 1
f.
LPRM D
NA (g) 1, 2, 5 3.
Reactor Vessel Steam Dome g
Pressure - High (B21-PT-NO23A,B,C,D)
NA(k) NA R
1, 2 II) v.
h (B21-PTM-NO23A-1,B-1,C-1,D-1)
D M
M 1, 2 En 4.
z Low, Level 1 (B21-LT-NOl7A-1,B-1,C-1,D-1)
NA(k) NA R
1, 2 II)
(B21-LTM-NOl7A-1,B-1,C-1,D-1)
D M
M 1, 2
(BSEP-2-32) a TABLE-4.3.1-1 (Continued) g E
REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS g
s S
, I (a) Neutron detectors may be excluded from CHANNEL CALIBRATION.
Ey (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 2.
(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 is greater than or equal u
to 25% of RATED THERMAL POWER.
N (f) This calibration shall consist of the adjustment of the APRM flow-biased setpoint to conform to a u
h calibrated flow signal.
(g) The LPRMs shall be calibrated at least once per effective full power month (EFPM) using the TIP system.
(L) 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 g
check is not required.
E g
(1) Transmitters are exempted from the monthly channel calibration.
E (m) Placement of Reactor Mode Swich into the Startup/ Hot Standby position is permitted for the purpose of performing n
g 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 surveillance provided all control rods are fully inserted and the vessel head bolts are tensioned.
i (BSEP-2-32) 1 TABLE 4.3.4-1 CONTROL ROD WITHDRAWAL BIDCK INSTRUMENTATION SURVEILLANCE REQUIREMENTS s
Q CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH, TRIP FUNCTION AND INSTRUMENT NUMBER CHECK TEST CALIBRATION SURVEILLANCE REQUIRED e
d 1.
APRM (CSI-APRM-CH.A,B,C,D,E,F)
S/U(C)
R(b)(a) y I
Upscale (Flow Biased)
NA a.
S/U(c)(E,q(f)
NA 1, 2, 5 b.
Inoperative NA S/U c) y S/U(c)(E
,q(d)(f) y c.
Downscale NA
)
R 2, 5 l
d.
Upscale (Fixed)
NA 2.
ROD BLOCK MONITOR (CSI-RBM-CH.A,B) w a.
Upscale NA S/U(c) M R(a) g, S/U((c),Q Npa)
D b.
Inoperative NA 1*
S/U c),M R
y, w
c.
Downscale NA E
3.
SOURCE RANCE MONITORS (C51-SRM-K600A,B,C,D)
S/U(c)
S/U(C),y(d) a.
Detector not full in NA NA 2, 5 S/U(C),W(d)
I NA 2, 5 b.
Upscale NA c),W(d)
NA 2, 5 c.
Inoperative NA
,y(d)
S/U NA 2, 5 d.
Downscale NA 4.
INTERMEDIATE RANCE MONITORS (C51-IRM-K601A,B,C,D,E,F,C,H)
(c)(e),y(d) a.
Detector not full in NA S
NA 2
NA W
NA 5
b.
Upscale NA S/U(c),y(d)
NA 2
~
{
NA W
NA 5
o c.
Inoperative NA S/UIC)
Id)
,W NA 2
NA W
NA 5
,o d.
Downscale NA S/UIC)
Id)
,W NA 2
NA W
NA 5
-(BSEP-2-32)
.~
TABLE 4.3.4-1 (Cont'd) ss h
CONTROL ROD WITHDRAWAL BIDCK INSTR 12tENTATION SURVEILIANCE REQUIREMENTS s
Q CHANNEL OPERATIONAL.
CHANNEL FUNCTIONAL CHANNEL CONDITIONS TN NHICH I
TRIP FUNCTION AND INSTRUMENT Nt2tBER CHECK TEST CALIBRATION *)
SURVEILLANCE REQUIRED E
E 5.
SCRAM DISCHARGE VOLUNE (Cl2-LSH-N013E) w a.
Water Level - High NA Q
R 1, 2, 5**
When THERMAL POWER is greater than the preset power level of the RWM and RSCS.
With any control rod withdrawn. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.
(a) CHANNEL CALIBRATIONS are electronic.
(b) This calibration shall consist of'the adjustment of the APRM flow biased setpoint us 30 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.
un E
(d) When changing from OPERATIONAL CONDITION 1 to OPERATIONAL CONDITION 2, perform the y
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.
(e) Placement of Reactor Mode Switch into -Startup/ Hot Standby position tis 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.
sn e