ML20236D559
| ML20236D559 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 03/10/1989 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20236D507 | List: |
| References | |
| TAC-65751, TAC-65752, NUDOCS 8903230162 | |
| Download: ML20236D559 (8) | |
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i TABLE 3.3-1 (Continued)
ACTION STATEMENTS (Continued)
ACTION 4 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, suspend all operations involving positive reactivity changes.
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i ACTION 5 pelete p
ACTION 6 - With the number of OPERABLE channels one.less than the Total
-Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:
j The inoperable channel is placed in the tripped condition a.
within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and
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b.
The Minik,um 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 /> for surveillance testing of other channels per Specification 4.3.1.1.
ACTION 7 - Delete g
ACTION 8 - With less than the Minimum Number of Channels OPERABLE, within I hour determine by observation of the associated permissive h.
status light (s) that the interlock is in its required state J
X for the existing plant condition, or apply Specification 3.0.3.
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~R ACTION 9 - With the number of OPERABLE channels one less'than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY 1
within 6 houts; however,'one channel may be bypassed for up to 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,
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provided the other channel is OPERABLE.
b ACTION 10 - With the number of OPERABLE channels one less than the Minimum Q
Channels OPERABLE requirement, restore the inoperable channel
\\d 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 h
breakers within the next hour.
ACTION 11 - With the number of OPERABLE channels less than the Total Number 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 />.
-,,,j CATAWBA - UNITS 1 & 2 3/4 3-6 Amendment No.
(Unit 1)
Amendment No.
(Unit 2)
INSERT FOR PAGE 3/4 3-6 ACTION 12 - With one of the 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 foriperforming 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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J 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.
M Below P-6 (Intermediate Range Neutron Flux Interlock) Setpoint, M# Below P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.
)
(1) If not performed 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 power if absolute difference is greater than 2%.
The provisions of g
Specification 4.0.4 are not applicable for entry into MODE 2 or 1.
s 4M (3) Single point comparison of incore to excore axial flux difference above i g 15% of RATED THERMAL POWER.
Recalibrates if the absolute difference is l
greater than or equal to 3%.
The provisions of Specification 4.0.4 are
!g not applicable for entry into MODE 2 or 1.
f O
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Neutron detectors may be excluded from CHANNEL CALIBRATION.
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( 5,. Detector plateau curves shall be obtained, evaluated and compared to g
manufacturer's data.
For the Intermediate Range and Power Range Neutron g
Flux channels the provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.
,y (6)
Incore - Excore Calibration, above 75% of RATED THERMAL POWER.
The l
q provisions of Specification 4.0.4 are not applicable for entry into
(
MODE 2 or 1.
l d
(7) Each train shall be tested at least every 62 days on a STAGGERED TEST l
BASIS.
(8) With power greater than or. equal to the interlock setpoint the required ANALOG CHANNEL OPERATIONAL TEST shall consist of verifying that the
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interlock is in the required state by observing the permissive status
,i 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 g
existing plant conditions by observation of the permissive status light.
lQ (10) Setpoint verification is not applicable.
(11) At leest ence per 10 eenth-,d f;110 ing = int=== ;r ;dj= tert of g
^the R;;;ter trip br = k;r; h TRIP ACTUATING DEVICE OPERATIONAL TEST gy shall include independent verification of the Undervoltage and Shunt i
trips.
^
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H (12) celeted N8WoM b
(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.
1 i
CATAWBA - UNITS 1 & 2 3/4 3-12 Amendment No. jd (Unit 1)
Amendment No. yf(Unit 2)
E
4.
.w,
-INSERT FOR PAGE 3/4 3-12 (14)
The., TRIP ACTUATING. DEVICE OPERATIONAL TEST shall independently verify'the.
. OPERABILITY of the undervoltage and shunt trip circ 6its for.the Manual Reactor Trip' Function. The test shall also verify the OPERABILITY of the
. Bypass. Breaker' trip circuit (s).
.(15) A local manual shunt trip on the. bypass breakers shall be performed-prior to placing breaker in service.
(16) The automatic'undervoltage trip capability shall be verified OPERABLE.
1
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INSTRUMENTATION 0
BASES'
=N REACTOR TRIP SYSTEM and ENGINEERED SAFETY FEATUR
. )' yf INSTRUMENTATION (Continued) f N spray puinos start and automatic valves position, (6) containment isolation, D k (7) steam line isolation, (8) Turoine trip (9) auxiliary fee N
start and automatic. valves. position, (10) nuclear service w 4
5 valves position.
The Engineered Safety Features Actuation System interlocks perform the g
y d following functions: Reactor tripped - Actuates Turcine' trip,' closes main f below Setpoint, prevents the opening of the main
@(g( P-4 valves on T,yg feedwater valves which were closed by a Safety Injection or High Steam Generator Water t.evel signal allows safety injection block so
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%g 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 p.res-surizer pressure and low steam line pressure and defeats steam line i
4 P-11 Defeats tne manual q
isolation on negative steam line pressure cate.
block of the motor-driven auxiliary feedwater pumps.on trip of main t
J feedwater pumps and low-low steam generator water level.
,4 On decreasing reactor coolant loco temperature, P-12 automatically 9w P-12 blocks steam dump and allows manual bypass of steam dumo block for g
the cooldown valves only.
On increasing reactor coolant-loco temoer-j d
ature, P-12 automatically defeats the manual 9ypass of tne steam demo block.
j On increasing steam generator level, P-14 automatically tri:s all feedwater isolation valves, pumos and turoine and innioits feecwater d1 P-14 controt valve modulation.
3/4.3.
MONITORING INSTRUMENTATION RA0!ATION MONITORING FOR PLANT OPERATIONS 3/4.3.3.1 The OPERA 81,LITY of the radiation monitoring instrumentation for plant (1) the associated action will be initiated wnen tre ocerations ensurts that: radiation level monitored by each channel or combination Setooint, (2) the specified coincidence logic is maintained, and (3) suffi-cient redundancy is maintained to permit a channel to be.out-of-service for The radiation monitors for plant operations senses testing or maintenance. radiation levels in selected plant systems and locations a If tney are, tne signal.s are or not predetermined limits are being exceeded.
comoined into logic matrices sensitive to combinations indicative of various Once the required logic combination is accidents and abnormal conditions.comoleted, the system sends actuatio isolation action and actuation of Emergency Exhaust or Ventilation Systems.
'N-B 3/4 3-3