ML20069C287
| ML20069C287 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 05/27/1994 |
| From: | BALTIMORE GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20069C283 | List: |
| References | |
| NUDOCS 9406010072 | |
| Download: ML20069C287 (15) | |
Text
1 i
I g
TABLE 4.3-1 G
REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE REQUIREMENTS n
z C
CHANNEL MODES IN WHICH q
CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE E
FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED M
i x
1.
Manual Reactor Trip NA NA S/U )
NA y
II g
2.
Power Level - High y
D ),M ),Q )
(Q 1, 2 I2 I3 I5 a.
Nuclear Power S
D '), R JVQ '
I b.
AT Power S
1 I
3.
Reactor Coolant Flow - Low S
R M'Q 1, 2 4.
Pressurizer Pressure - High S
R g4 1, 2 s
5.
Containment Pressure - High S
R g4 1, 2 w
6.
Steam Generator Pressure - Low S
R
/Q 1, 2 7.
Steam Generator Water Level -
S R
W42 1, 2 Low 8.
Axial Flux Offset S
R ff 4 1
9.
a.
Thermal Margin / Low Pressure S R
JIQ 1, 2 Ngou b.
Steam Generator Pressure S
R ge 1, 2
& gg Difference - High ko 10. Loss of Load NA NA S/UIll NA
$o
- z P 88 mm 0$
88
r
~
g TABLE 4.3-1 (Continued) w G
P g
REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE REQUIREMENTS w
m b
CHANNEL MODES IN WHICH h
a CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE E
FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED E
i
=
R)
S/U )
U U
1, 2
- 11. Wide Range Logarithmic Neutron Flux S
and, 3, 4, 5 y
c
]
Monitor
- 12. Reactor Protection System Logic NA NA and S/U )
1, 2 U
Matrices U
- 13. Reactor Protection System Logic NA NA and S/U )
1, 2 Matrix Relays
- 14. Reactor Trip Breakers NA NA M
1, 2 and
- w w
C ay a,.
O.
2 m
[
i g
TABLE 4.3-2 R
G ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS n
x C
CNANNEL MODES IN WNICN q
CHANNEL CNANNEL FUNCTIONAL SURVEILLANCE E
FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED E
i z
4 C
5 1.
SAFETY INJECTION (SIAS) d E
~
a.
Manual (Trip buttons)
NA NA NA b.
Containment Pressure - High S
R Q
1,2,3 c.
Pressurizer Pressure - Low S
R G
1, 2, 3 d.
Automatic Actuation Logic NA NA MD 3) 1, 2, 3 2.
CONTAINMENT SPRAY (CSAS) a.
Manual (Trip buttons)
NA NA NA
'f b.
Containment Pressure - High S
R a
1,2,3 G
c.
Automatic Actuation Logic NA NA M
1,2,3 3.
CONTAINMENT ISOLATION (CIS)'
a.
Manual CIS (Trip buttons)
NA NA NA b.
Containment Pressure - High S
R 1, 2, 3 c.
Automatic Actuation Logic NA NA M
1, 2, 3 a
n to E. F u
l l
I g
TABLE 4.3-2 (Continued)
R G
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS g
b CNANNEL MODES IN WNICN q
CNANNEL CNANNEL FUNCTIONAL SURVEILLANCE E
FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED M5 C
4.
MAIN STEAM LINE ISOLATION (SGIS) a.
Manual SGIS (MSIV Hand Switches NA NA R
NA and Feed Head Isolation Hand Switches) b.
Steam Generator Pressure - Low S
R 1, 2, 3 c.
Automatic Actuation Logic NA NA M
1, 2, 3 g
5.
CONTAINMENT SUMP RECIRCULATION (RAS) a.
Manual RAS (Trip Buttons)
NA NA NA B
b.
Refueling Watei Tank - Low NA R
S 1,2,3 c.
Automatic Actuation Logic NA NA M
1, 2, 3 6.
CONTAINMENT PURGE VALVES ISOLATION a.
Manual (Purge Valve Control NA NA R
NA Switches) b.
Containment Radiation - High Area S
R
)(&
6**
k Monitor B
c M
I
- - - - - - -i
f g
TABLE 4.3-2 (Continued) w G
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS w
'g b
CHANNEL MODES IN WNICH q
CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE E
FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED i5j
'i c
]
7.
LOSS OF POWER y
~
a.
4.16 kv Emergency Bus Undervoltage NA R
1,2,3 (Loss of Voltage) b.
4.16 kv Emergency Bus Undervoltage NA R
1,2,3 (Degraded Voltage) 8.
CVCS ISOLATION wA West Penetration Room / Letdown NA R
1,2,3,4 Heat Exchanger Room Pressure - High 5
9.
Manual (Trip Buttons)
NA NA NA b.
Steam Generator Level - Low S
R 1, 2, 3 c.
Steam Generator AP - High S
R 1,2,3 d.
Automatic Actuation Logic NA NA-M 1,2,3 rt t>
l 3/4.3 INSTRUMENTATION TABLE 4.3-2 (Continued)
TABLE NOTATION Containment isolation of non-essential penetrations is also initiated by SIAS (functional units 1.a and 1.c).
Must be OPERABLE only in MODE 6 when the valves are required OPERABLE and they are open.
(1)
The logic circuits shall be tested manually at least once per 31 days.
(2)'
SIAS logic circuits A-10 and B-10 shall be tested monthly with the l
exception of the Safety Injection Tank isolation valves. The SIAS logic circuits for these valves are exempted from testing during operation; however, these logic cire.uits shall be tested at least once per 18 months during shutdown.
(3)
SIAS logic circuits A-5, and B-5 are exempted from testing.during operation; however, these logic circuits shall be tested at least once per 18 months during shutdown.
(4)
CIS logic circuits A-5 and B-5 are exempted from testing during operation; however, these logic circuits shall be tested at least
)
once per 18 months during shutdown.
(5)
SGIS logic circuits A-1 and B-1 are exempted from testing during operation; however, these logic circuits shall be_ tested at least once per 18 months during shutdown.
(6)
CSAS logic circuits A-3 and B-3 are exempted from testing during l
operation; however, these logic circuits shall be tested at least once per 18 months during shutdown.
1 l
N !)Ed!N5 SNnU N " N "d N!dS Y N [ !Npf!! ) !N N Wara Unit 1 Refuelf :g Outige W"mher 10. -
CALVERT CLIFFS - UNIT 1 3/4 3-22 Amendment No. 494' f
f
j 3/4.3 INSTRUMENTATION f
BASES i
3/4.3.1 and 3/4.3.2 PROTECTIVE AND ENGINEERED SAFETY FEATURES (ESF) j INSTRUMENTATION 1
bypasses ensure that 1) protective and ESF instrumentation systems and The OPERABILITY of the the associated ESF action and/or reactor trip will 1
be initiated when the parameter monitored by each channel or combination thereof exceeds its setpoint, 2).the specified coincidence logic is maintained, 3) sufficient redundancy. is maintained to pennit a channel to l
be out of service for testing or maintenance..and 4) sufficient system functional capability is available for protective and ESF purposes from diverse parameters.
The OPERABILITY of these systems is required to provide the overall reliability, redundance and diversity assumed available in the facility design for the protection and mitigation of accident and_ transient conditions. The integrated operation of each of.these systems is consistent with.the assumptions used in the. accident analyses.
The surveillance requirements.specified for these systems ensure that the overall system functional capability is maintained comparable to the original design standards.. The periodic surveillance tests performed at-the minimum frequencies are sufficient to demonstrate this capability.
The measurement of response time at' the specified frequencies provides assurance that the protective and ESF' action. function associated with each channel is completed within the time limit assumed in the accident analyses. No credit was taken in the analyses for those channels with response times indicated as not applicable. -
Response time nay be demonstrated by any series of sequential, overlapping or total channel test measurements provided that such tests demonstrate the total channel response time as defined. Sensor response time verification may be demonstrated by either 1) in place, onsite or offsite test.
measurements or 2) utilizing replacement sensors with certified response -
1 times. The response time limits are contained in UFSAR Chapter 7, and 5
updatedinaccordancewith10CFR50.71(e).
j 3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 Radiation Monitorina Instrumentation The OPERABILITY of the radiation monitoring channels ensures that 1) the radiation levels are continually measured in the areas served by the individual channels and 2) the alann or automatic action is initiated when the radiation level trip setpoint is exceeded.
Tl7c pat laly Segwxy Q de ekNNel hethNa/ksh k, ffeu sys/ ems is basedoMbe avkl sis peseMedig de &c. appaed kp;atdepat y
CobM1,9?s/GFAs hieded T~b+ TalethlEh/uafo4" as Stypkmen/cd.
e w
CALVERT CLIFFS - UNIT 1 B 3/4 3-1 AmendmentNo.2Sp
-. ~
--l
d ATTACllMENT (2)
UNIT 2 TECHNICAL SPECIFICATION i
REVISED PAGES 3/43-6 3/43-7 3/4 3-19 t
'3/4 3-20 3/4 3-21 3/4 3-22 Il 3/4 3-1 1
g TABLE 4.3-1 R
G REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE REQUIREMENTS g
E n
C CHANNEL MODES IN WHICN 5
4 CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE E
FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED R
R lM:
1.
Manual Reactor Trip NA NA S/UN NA y
g Z
2.
Power Level - High j
m a.
Nuclear Power S
AT Power S
DN.R tt' Q 1
3.
Reactor Coolant Flow - Low S
R Jt' Q
)
1, 2 R
4.
Pressurizer Pressure - High S
R lt' Q 1, 2 h
5.
Containment Pressure - High S
R Jt'Q 1, 2 6.
Steam Generator Pressure - Low S
R
/G 1, 2 7.
Steam Generator Water Level -
S R
J( Q 1, 2 Low 8.
A: el Flux Offset S
R ff Q <
1 9.
a.
Thermal Margin / Low Pressure S R
/Q 1, 2 E
's b.
Steam Generator Pressure S
R frG 1, 2 Difference - High k
- 10. Loss of Load NA NA S/UIll NA
.E e
g TABLE 4.3-1 (Continued) w Gg REACTOR PROTECTIVE INSTRUNENTATION SURVEILLANCE REQUIRENENTS w
b CHANNEL MODES IN WHICH q
CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE E
FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED 1, 2 h
b
- 11. Wide Range Logarithmic Neutron Flux S
R(5)
S/U(1) and, 3, 4, 5 y
Monitor
- 12. Reactor Protection System Logic NA NA O
and S/U(1) 1, 2 m
Matrices III
- 13. Reactor Protection System Logic NA NA Q. and S/U 1, 2 Matrix Relays
- 14. Reactor Trip Breakers NA NA M
1, 2 and
- a
~
a fit n
et I
9 TABLE 4.3-2 R
c; ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS g
b CHANNEL MODES IN WNICN Q
CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE E
FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED i5i
- i C
1.
SAFETY INJECTION (SIAS) y
=
a.
Manual (Trip buttons)
NA NA NA b.
Containment Pressure - High S
R ff'Q 1,2,3 c.
Pressurizer Pressure - Low S
R G
1,2,3 d.
Automatic Actuation Logic NA NA MD 3) 1, 2, 3 2.
CONTAINMENT SPRAY (CSAS) a.
Manual (Trip buttons)
NA NA NA b.
Containment Pressure - High S
R 1, 2, 3 c.
Automatic Actuation Logic NA NA MI 1, 2, 3 3.
CONTAINMENT ISOLATION (CIS)'
a.
Manual CIS (Trip buttons)
NA NA NA b.
Containment Pressure - High S
R 1,2,3 c.
Automatic Actuation Logic NA NA M
1, 2, 3 F
n:s R
a E
w
9 TABLE 4.3-2 (Continued)
G P
ENGINEERED SAFETY FEATURE ACTUATU N SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS g
b CHANNEL MODES IN WHICH q
CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE E
FUNCTIONAL UNIT CHECK CALIBRATIOC TEST REQUIRED.
i5i
'i C
4.
MAIN STEAM LINE ISOLATION (SGIS) a.
Manual SGIS (MSIV Hand Switches NA NA R
NA and Feed Head Isolation Hand Switches) b.
Steam Generator Pressure - Low S
R 1,2,3 c.
Automatic Actuation Logic NA NA 1, 2, 3 g
5.
CONTAINMENT SUMP RECIRCULATION (RAS) a.
Manual RAS (Trip Buttons)
NA NA NA b.
Refueling Water Tank - Low NA R
O 1,2,3 c.
Automatic Actuation Logic NA NA M
1,2,3 6.
CONTAINMENT PURGE VALVES ISOLATION a.
Manual (P4rge Valve Control NA NA NA Swi tche >.j G
6**
b.
Contairxtet Radiation - High S
R k
Area ibnitor E
2a
g TABLE 4.3-2 (Continued)
R G
P g
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS w
b CHANNEL MODES IN WHICH q
CNANNEL CHANNEL FUNCTIONAL SURVEILLANCE E
FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED E
'i C
7.
LOSS OF POWER y
a.
4.16 kv Emergency Bus Undervoltage NA R
1,2,3 (Loss of Voltage) b.
4.16 ky Emergency Bus Undervoltage NA R
1, 2, 3 (Degraded Voltage) 8.
CVCS ISOLATION West Penetration Room / Letdown NA R
Q 1,2,3,4
'f Heat Exchanger Room Pressure - High U
9.
Manual (Trip Buttons)
NA NA NA b.
Steam Generator Level - Low S
R
)(
1,.2, 3 c.
Steam Generator AP - High S
R 1,2,3 d.
Automatic Actuation Logic NA NA M
1,2,3 8-E n
3/4.3 INSTRUMENTATION TABLE 4.3-2 (Continued)
TABLE NOTATION Containment isolation of non-essential penetrations is also initiated by SIAS (functional units 1.a and 1.c).
Must be 0PERABLE only in MODE 6 when the valves are required OPERABLE and they are open.
(1)
The logic circuits shall be tested manually at least once per 31 days.
(2h SIAS logic circuits A-10 and B-10 shall be tested monthly with the exception of the Safety Injection Tank isolation valves. The SIAS logic circuits for these valves are exempted from testing during operation; however, these logic circuits shall be tested at least once per 18 months during shutdown.
(3)
SIAS logic circuits A-5 and B-5 are exempted from testing during operation; however, these logic circuits shall be tested at least once per 18 months during shutdown.
b)
CIS logic circuits A-5 and B-5 are exempted from testing during operation; however, these logic circuits shall be tested at least once per 18 months during shutdown.
(5)
SGIS logic circuits A-1 and B-1 are exempted from testing during operation; however, these logic circuits shall be tested at least once per 18 months during shutdown.
(6)
CSAS logic circuits A-3 and B-3 are exempted from testing during operation; however, these logic circuits shall be tested at least once per 18 months during shutdown.
[
XM O
- onthly test: net required en,^A0 and B 10 ur.til 500 logic circuit--
modi ficetivus vei,leted. Mcdificaticn: to be enmniatad dur4n; cr-befer: "r.it 2 Refueling Ontege Nuirier 0.--
CALVERT CLIFFS - UNIT 2 3/4 3-22 Amendment No. 161 I
d 3/4.3 INSTRUMENTATION l
BASES 3/4.3.1 and 3/4.3.2 PROTECTIVE AND ENGINEERED SAFETY FEATURES (ESF)
INSTRUMENTAlION The OPERABILITY of the protective and ESF instrumentation systems and j
bypasses ensure that 1) the associated ESF action and/or reactor trip will be initiated when the parameter monitored by each channel or combihation thereof exceeds its setpoint, 2) the specified coincidence logic is maintained 3) sufficient redundancy is maintained to permit a channel to be out of service for testing or maintenance, and 4) sufficient system functional capability is available for protective and ESF purposes from diverse parameters.
The OPERABILITY of these systems is required to provide the overall reliability, redundance and diversity assumed available in the facility design for the protection and mitigation of accident and transient conditions. The integrated operation of each of these systems is consistent with the assumptions used in the accident analyses.
The surveillance requirements specified for these systems ensure that the overall system functional capability is maintained comparable to the original design standards. The periodic surveillance tests performed at the minimum frequencies are sufficient to demonstrate this capability.
F The measurement of response time at the specified frequencies provides assurance that the protective and ESF action function associated with each channel is completed within the time limit assumed in the accident analyses. No credit was taken in the analyses for those channels with response times indicated as not applicable.
Response time may be demonstrated by any series of sequential, overlapping or total channel test measurements provided that such tests demonstrate the total channel response time as defined. Sensor response time verification may be demonstrated by either 1) in place, onsite or offsite test measurements or 2) utilizing replacement sensors with certified response times. The response time limits are contained in UFSAR Chapter 7, and A
updated in accordance with 10 CFR 50.71(e).
p 3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 Radiation Monitorino Instrumentation The OPERABILITY of the radiation monitoring channels ensures that 1) the radiation levels are continually measured in the areas served by the individual channels and 2) the alann or automatic action is initiated when the radiation level tripytpoint isydh-The ynth y tytuey & be Oll$MMel Subko'd'I ESS W#NS is based oMk walyds pae.se&A la h NEC appACwl NA'PAl CEd -3G, "R?s/ESFM EXkaded Ted 1M+e& Balua%M "a3 MO CALVERT CLIFFS - UNIT 2 B 3/4 3-1 Amendment No. 161
-