ML20117C392
| ML20117C392 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 05/06/1985 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20117C371 | List: |
| References | |
| NUDOCS 8505090407 | |
| Download: ML20117C392 (6) | |
Text
-._
TABLE 4.3.1-1 (Continued)
N ii REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILI.ANCE REQUIREMENTS E
11 f
CllANNEL OPERATIONAL 5
FUNCTIONAL UNIT CllANNEL FUNCTIONAL CilANNEL CONDITIONS IN WilICll.
CALIBRATION (a)
SURVEILI.ANCE REQUIRED AND INSTRUMENT nut!BER CllECK TEST R(h) 3 E
- 5. Flain' Steam Line Isolation Valve -
NA M
l E
Closure h' (B21-F022A,B,C,D and.
B21-F028A,B,C,D) i
- 6. Main Steam Line Radiation - lii'gh S
tl(I)
R(3) 1, 2;!
i g
( D 12-R!!-K603 A, B, C, D).
fi I
l i
- 7. D'rywell Pressure - liigh' R(1) 1, 2,i
( C71-PT-N002A, B, C,D) i NA(k)
NA D
H M
1, 2 p (C71-PT:t-N002A-1,B-1,C-1,D-1)
'I w
h y
- 8. Scram Discharge Volume Water NA Q
R 1, 2,: 5
,j Level - liigh g
- j ((Cl1-LSil-N013A,B,C,D) g-I. Cl1-LSil-4516A,B,C,D)
R(h) g(m) l 9.
rbine Stop Valve - Closure NA M
' ( EllC-SVOS-1X,2X,3X,4X)
- 10. Turbine Control Valve Fast l
Closure, Control Oil Pressure -
Low NA M
R 1
I
( EllC-PSL-1756,17 57,1758,1759) f NA R
NA 1, 2,' 3, 4, 5 !
(f
- 11. Ibactor Mode Switch in Shutdown R
Position g
(C71A-S1) g
- 12. Manual Scram NA Q.
NA 1,2,3,4,5
,,o (C71A-S3A,B)
[O DN f
P
(BSEP-1-49) en{
TABLE'4.3.1-1 (Continued) m i
M REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS R
g (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 CONDITION 1 to CONDITION 2, perform the required surveillance within 12 hc.ars after entering 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 CONDITION 1 when THERMAL POWER > 25% of RATED THERMAL POWER.
N (f) This calibration shall consist of the adjustment of the APRM flow-biased setpoint to conform to a
[
calibrated flow signal.
sa (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 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.
g, (1) Transmitters are exempted from the monthly channel calibration.
N
- g (m) Surveillance is not required when THERMAL POWER is less than 30% of RATED THERMAL POWER.
E 1
l
ENCLOSURE 2 PROPOSED CHANGE TO BRUNSWICK-2 SPECIFICATION 3/4 3.1 TURBINE STOP VALVES (84TSB24)
(ll21NLU/ccc)
PAGE DESCRIPTION OF CHANGE 3/43-8 Items 9 and 10 - Add footnote (m) to Operational Conditions.
.3/4 3-8a-Insert footnote (m) " Surveillance is not required when THERMAL POWER is less than 30% of RATED THERMAL POWER."
4 (1121NLU/ccc) s-+em,.-e--
-+vi.-
<m-=-
+ wwv.-,--
-r.-w
..ir-.
r
( BSEP-2-45)
TABLE 4.3.1-1 (Continued) i.
en h
REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS b
My CllANNEL OPERATIdhAL PC FUNCTIONAL UNIT
. Cil ANNEL
-FUNCTIONAL CllANNEL CONillTIONS IN WilICll AND INSTRUMENT NUMBER CilECK TEST CALIBRATION (a)
SURVEII.I.ANCE REQUIRED c
NA M
R.( h) g h
- 5. Main Steam Line Isolation Valve -
Closure i!(B21-F022A,B,C,D and B21-F028A,B,C,D) 4
- 6. Main Steam Line Radiation - Ill'gh S
M(I)
I3)
R 1, 2 (012-RM-K603A,B,C,D)
.j
{
n i
- 7. Drywell Pressure - liigh' l
(C72-PT-N002A,B,C,D)
NA(k)
NA R(1)
I, 2) i j (C72-PTM-N002A-1,B-1,C-1,D-1)
D M
M 1, 2 ;
2 i
- 8. Scram Discharge Volume Water i
i 4
Level - liigh NA Q
R 1, 2,. 5
'(Cl2-LSil-N013A,B,C,D) j
( Cl 2-LSil-4516 A, B,C,D) l I
- 9. Turbine Stop Valve - Closure NA M
R(h) g(m)
( EllC-SVOS-I X,2 X,3X,4 X) i t
- 10. Turbine Control Valve Fast Closure, Control Oil Pressure -
Low NA M
R 1
( EllC-PSL-1756,1757 ',1758,1759)
'g i1. Reactor Mode Switch in Shutdown NA R
NA 1,2,l3,4,5' g
Position g
1(C72A-SI) l n
g
- 12. Manual Scram NA
'Q NA 1,2,3,4,5 (C72A-S3A,B)
.4
..e (BSEP-2-45) i-tw g!
a, TABLE 4.3.1-1'(Continued).
vs
- fi ~
REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS-
- Q k
1.
(a) Neutron detectors may be excluded.from CHANNEL CALIBRATION.
- cz ew d
(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.
- w (c) The IRM channels shall be compared to the APRM channels and the SRM instruments for overlap lduring.each startup,'if not performed within the previous 7 days..
(d) When changing from CONDITION 1 to' 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 /> af ter entering 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 CONDITION 1 when THERMAL POWER > 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.
m (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 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.
a h
(m) Surveillance is not required when THERMAL POWER is less than 30%.of RATED THERMAL POWER.
g:'
t
.