ML20216C823
| ML20216C823 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 06/19/1987 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20216C741 | List: |
| References | |
| GL-83-28, GL-85-09, GL-85-9, TAC-65751, TAC-65752, NUDOCS 8706300372 | |
| Download: ML20216C823 (8) | |
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P TABLE 3.-3-1 (Continued)
ACTION STATEMENTS (Continued) l ACTION'4 - With the number of OPERABLE channels one less than the Minimum l
Channels OPERABLE requirement, suspend all operations ~ involving positive' reactivity changes.
L ACTION 5 - With the number of OPERABLE channels one less than-the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or open the Reactor trip breakers,
. suspend all operations involving positive reactivity changes and j
verify Valves. NV-231, NV-237, NV-241, and NV-244 are closed and 1
secured in position within the next hour.
I ACTION 6 - With the number of OPERABLE channels one less than the Total
=
Number of Channels, STARTUP and/or POWER OPERATION may proceed 4
provided the following conditions are satisfied:
l a.
The inoperable channel is placed in the tripped _ condition
.g.
within 6. hours, and 1
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b.
The Minimum Channels OPERABLE requirement is met;'however,
.the inoperable channel may be bypassed for up-to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
(
L for surveillance testing of other channels per l
{
Specification 4.3.1.1.
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ACTION 7 - Delete-(.
ACTION 8 - With less than the Minimum Number of Channels OPERABLE, within i
T 1.nour determine by observation of the associated permissive N.
status light (s) that the interlock is in its required state-i for the existing plant condition, or apply Specification 3.0.3.
ACTION 9 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY 1
b within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel may be bypassed for up to Q
2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.1.1, provided the other channel is OPERABLE.
g ACTION 10 - With the number of OPERABLE channels one less than the Minimum Channels' OPERABLE requirement, restore the inoperable channel j
to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or open the Reactor trip
'L breakers within the next hour.
ACTION 11 - With the number of OPERABLE channels less than the Total Number
.I of Channels, operation may continue provided the inoperable channels are placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
I i
1 CATAWBA - UNITS 1 & 2 3/4 3-6 AmendmentNo.[(Unit 1)
Amendment No./ (Unit 2)
.I
l
- f Q j' L
_ INSERT FOR PAGE 3/4-3-6 s
' ACTION 12 - With one ofJthe_ diverse trip features-(Undervoltage or shunt trip attachment) inoperable,' restore it to OPERABLE status within'48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or declare the breaker, inoperable and' apply. ACTION 9.
The breaker shall not be bypassed while one of the diverse trip features;is
-inoperable except for the time required for performing maintenance to restore the breaker to OPERABLE status.- With the breaker bypassed, apply ACTION.9.
- ACTION 13 - With
- any reactor trip bypass. breaker inoperable, restore the bypass breaker to OPERABLE status prior to placing it in service.
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i TABLE 4.3-1 (Continued)
TABLE NOTATIONS Only if the Reactor Trip System breakers happen to be closed and the Control Rod Drive System is capable of rod withdrawal.
Above.P-9 (Reactor' Trip on Turbine Trip Interlock) Setpoint.
Below P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.
- Below P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.
1 (1) If not parformed in previous 7 days.
]
(2) Comparison of calorimetric to excore power indication above 15% of RATED THERMAL POWER.
Adjust excore channel gains consistent with calorimetric f
power if absolute cifference is greater than 2%.
The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.
(3) Single point comparison of incore to excore axial flux difference above i
15% of RATED THERMAL POWER.
Recalibrate if the absolute difference is greater than or equal to 3%.
The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.
j (4) Neutron detectors may be excluded from CHANNEL CALIBRATION.
(5), Oetector plateau curves shall be obtained, evaluated and compared to manufacturer's data.
For the Intermediate Range and Power Range Neutron Flux channels the provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.
g (6)
Incore - Excore Calibration, above 75% of RATED THERMAL POWER.
The provisions of Specification 4.0.4 are not applicable for entry into
)
MODE 2 or 1.
1 1
(7) Each train shall be tested at least every 62 days on a STAGGERED TEST 1
Q BASIS.
(8) With power greater than or equal to the interlock setpoint the required b-ANALOG CHANNEL OPERATIONAL TEST shall consist of verifying that the k'
interlock is in the required state by observing the permissive status U
light.
(9) Monthly surveillance in MODES 3*,
4*, and 5* shall also include verifi-cation that permissives P-6 and P-10 are in their required state for Q
existing plant conditions by ob;ervation of the permissive status light.
O.
For Unit 2 only, monthly surveillance shall include verification of the j.
]
y Boron Dilution Alarm Setpoint of less than or equal to one-half decade
{
4 Q
(square root of 10) above background.
]
(10) Setpoint verification is not applicable.
1 (11) At least once per'18 months and following maintenance or adjustment of the Reactor trip breakers, the TRIP ACTUATING DEVICE OPERATIONAL TEST i
y shall include independent verification of the Undervoltage and Shunt g
trips.
y H.
(12) CHANNEL CALIBRATION shall include the RTD bypass loops flow rate.
(13) For Unit 1, CHANNEL CALIBRATION shall ensure that the filter time constant associated with Steam Generator Water Level Low-Low is adjusted to a value less than or equal to 1.5 seconds.
CATAWBA - UNITS 1 & 2 3/4 3-12 Amendment No.
(Unit 1)
Amendment No.
(Unit 2)
I
. INSERT FOR'PAGE 3/4 3-12.
~ (14) The TRIP.ACTUATINC. DEVICE OPERATIONAL TEST shall. independently verify the.
OPERABILITY of_the undervoltage and shunt. trip circuits for the Manual Reactor, Trip Function.
. (15). A local' manual shunt trip on the bypass breakers shall be performed on a j
monthly STAGGERED TEST basis..
. (16)- The automatic.undervoltage trip capability shall be verified OPERABLE.
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4 INSTRUMENTATION
,h N
BASES
+
REACTOR TRIP SYSTEM and ENGINEERED SAFETY FEATURES ACTUATION
} V)*
INSTRUMENTATION (Continued)-
O k spray puinps start and automatic valves position, (6) containment isolation, i
(9) auxiliary feedwater pumps 4 ~Q.a(7) steam line isolation,-(8) Turoine tr p, D '.
start and automatic valves position, (10) nuclear service water pumps start ara t' '
utomatic valves position, and (11) component cooling pumps start and automatic h
valves position.
fN-The Engineered Safety Features Actuation System interlocks perform the l
3 -
following functions:
Reactor tripped - Actuat's Turbine trip, closes main feedwater e
- ( -f P-4 g-valves on T,yg below Setpoint, prevents the opening af tne main feedwater valves which were closed by a' Safety Injection or High p%?g Steam Generator Water Level signal, allows safety injection block so that components can be reset or tripped.
Reactor not tripped - prevents manual block of Safety Injection.
Defeats the manual block of Safety Injection actuation on low ;>res-4 P-11 surizer pressure and low steam line pressure and defeats steam line isolation on negative steam line pressure rate.
Defeats the manual y
1 O
block of the motor-driven auxiliary.feedwater pumps on trip of main g $'
feedwater pumps and low-low steam generator water level.
I
' On decreasing reactor coolant loop temperature, P-12 automatically Y w P-12 j
blocks steam dump and allows manual bypass of steam dump block for g-the cooldown valves only.
On increasing reactor coolant loco temper-ature, P-12 automatically defeats the manual bypass of the steam dump
._$.-Q block.
On increasing steam generator level, P-la automatically tri::s all
' d y P-14 feedwater isolation valves, pumps and turoine and innibits feecwater control valve modulation.
r 3/4.3.
MONITORING INSTRUMENTATION 3/A.3.3.1 RADIATION MONITORING FOR PLANT OPERATIONS The 0PERABI_LITY of the radiation monitorino instrumentation for plant
~
(1) the associated action will be initiated wnen :ne operations ensures that:
radiation level monitored by each channel or combination thereof reaches its Setpoint, (2)'the specified coincidence logic is maintained, and (3) suffi-cient redundancy is maintained to permit a channel to be out-of-service for testing or maintenance.
The radiation monitors for plant operations senses raoiation levels in selected plant systems and locations ano determines onetner If tney are, tne' signals are or not predetermined limits are being exceeded.
combined into logic matrices sensitive to comoinations indicative of various accidents and abnormal conditions.
Once the required logic comoination is completed, the system sends actuation signals to initiate alarms or automatic isolation action and actuation of Emergency Exhaust or Ventilation Systems.
\\
CATAWBA - UNITS 1 & 2 B 3/4 3-3