ML20082R516
| ML20082R516 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 12/08/1983 |
| From: | SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | |
| Shared Package | |
| ML20082R511 | List: |
| References | |
| NUDOCS 8312130198 | |
| Download: ML20082R516 (5) | |
Text
9' E
TABLE 3.3-2 (Continued) 5 REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES I
b FUNCTIONAL UNIT RESPONSE TIME
-4 12.
A.
Loss of Flow - Single Loop (Above P-8)
$ 1.0 seconds B.
Loss of Flow - Two Loops (Above P-7 and below P-8)
$ 1.0 seconds 13.
Steam Generator Water Level--Low-Low 1 2.0 seconds 14.
Steam /Feedwater Flow Mismatch and Low Steam Generator Vater Level Not Applicable R
15.
Undervoltage-Reactor Coolant Pumps
-< l.5 seconds s
Y 16.
Underfrequency-Reactor Coolant Pumps
-< 0.9 seconds g
17.
Turbine Trip A.
Low Fluid Oil Pressure Not Applicable B.
Turbine Stop Valve Closure Not Applicable 18.
Safety Injection Input from ESF Not Applicable 19.
Reactor Trip Systui Interlocks Not Applicable 20.
Reactor Trip Breakers
.-Not-App-1-icaMe- < 0.167 seconds
- 21.
Automatic Trip Logic Not Applicable
- The reactor trip breaker response time shall be the time as initiated by the Undervoltage coil dropout or the auto shunt relay dropout until the breaker opens.
8312130198 831208 PDR ADOCK 05000395 P
9 y
1ABLE 4.3-1 19 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS
!g TRIP c5 ANALOG ACIUAIING MODES FOR CilANNEL DEVICE WilICil 1
i CHANNEL CilANNEL OPERATIONAL OPERATIONAL ACTilATION SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST IEST LOGIC TEST IS REQUIRED i
1.
Manual Reactor Trip N.A.
N.A.
N.A.
R (11)
N.A.
1, 2, 3*, 4*, 5*
1 2.
Power Range, Neutron Flux High Setpoint S
D(2,4),
M N.A.
N.A.
1, 2 M(3, 4),
Q(4, 6),
R(4, 5)
Low Setpoint S
R(4)
H N.A.
N.A.
1###, 2
,s 3.
Power Range, Neutron Flux, N.A.
R(4)
M N.A.
N.A.
1, 2 y
High Positive Rate w
4.
Power Range, Neutron Flux, N.A.
R(4)
M N.A.
N.A.
1, 2 High Negative Rate 5.
Intermediate Range, S
R(4, 5)
S/U(1),M N.A.
N.A.
1###, 2 Neutron Flux 6.
Source Range, Neutron Flux 5
R(4, 5)
S/U(1),M(9)
N.A.
N.A.
2##, 3, 4, 5 7.
Overtemperature AT S
R H
N.A.
N.A.
1, 2 8.
Overpower AT S
R H
N.A.
N.A.
1, 2 9.
Pressurizer Pressure--Low S
R M
N.A.
N.A.
1 10.
Pressurlier Pressure--Illgh S
R H
N.A.
N.A.
1, 2 11.
Pressurizer Water Level--High 5 R
H N.A.
N.A.
1 12.
Loss of Flow S
R M
N.A.
N.A, 1
E TABLE 4.3-1 (Cont.inued)
N$
REACTOR TRIP SYSTEM INSTRUMENTATION SURVElltAffCE REQUIREf1ElliS t
1 RIP c5 ANALOG ACIIIATING MODES FOR CilAfitlEL 11FVICI K'lllCil CilANNEL CilANNEL OPERAT10flAL OPERATI0flAL ACTUATION SURVEILLANCE FUNCTIONAL UNIT CllECK CAllBRATION TESI TEST LOGIC TEST IS REQUIRED D.
Low Setpoint Power Range Neutron Flux, P-10 N.A.
R(4)
H (8)
N.A.
N.A.
1, 2 E.
Turbine Impulse Chamber Pressure, P-13 N.A.
R H (8) ti. A.
N.A.
1 20.
Reactor Trip Breaker N.A.
N.A.
N.A.
H (7, 11)
N.A.
1, 2, 3*, 4*, 5*
21.
Automatic Trip Logic N.A.
N.A.
N.A.
fl. A.
H (7)-
1, 2, $*,
4*, 5*
22.
Reactor Trip Bypass N.A.
N.A.
N.A.
M(7,12)SA(13) N.A.
1, 2, 3*,
4*, 5*
w 4
Breaker w
t 0
m TABLE 4.3-1 (Continued)
TABLE NOTATION With the reactor trip system breakers. closed and the-control rod drive system capable of rod withdrawal.
Belos P-6 (Intermediate Range Neutron Flux Interlock) setpoint.
Below P-10 (Low Setpoint Power Range Neutron Flux Interlock) setpoint.
If not performed in previous 7 days.
(1)
Comparison of calorimetric to excore power indication above 15% of (2)
RATED THERMAL POWER.
Adjust excore channel gains consistent with calorimetric power if absolute difference is greater than 2 percent.
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 15% of RATED THERMAL POWER.
Recalibrate if the absolute difference is greater than or equal to 3 percent.
The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.
(4) -
Neutron detectors may be excluded from CHANNEL CALIBRATION.
Detector plateau curves shall be obtainea', evaluated and comparea (5) 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.
Incore - Excore Calibration, above 75% of RATED THERMAL POWER.
Se (6) provisions of Specification 4.0.4 are not applicable for entry i a MCDE 2 or 1.
(7) -
Each train shall be tested at least every 52 days on a STAGGERED TEST BASIS.
With power greater than'or equal to the interlock setacint the recuired (8)
OPERATIONAL TEST shall consist of verifying that the interlock is in the required state by observing the permissive annunciator window.
(9) -
Monthly Surveillance in MODES 3*, 4* and 5* shall also include verification that permissives P-6 and P-10 are in their required state for existing plant conditions by observation of the permissive annunciator window.
(10) -
Setpoint verification is not required.
(1-14 At lesst once per 10 ;sath3 end fclic,ing sintenance or adic"~ -
of W 76Tci.u. trip breakars. the TRTD ACTUATING utvict OPERATIONAL TEST shalk.iacludc on TnTe~p~e'ndent veriiitat-itn of 'ha undervoltage and shunt-t. rip;.
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r-TABLE 4.3-1 (Continued)
TABLE NOTATION 11 - The TRIP ACTUATING DEVICE OPERATIONAL TEST shall include independent verification that the undervoltage and shunt trip attachments are OPERABLE.
12 - The TRIP ACTUATING DEVICE OPERATIONAL TEST shall verify that the shunt trip attachment is OPERABLE.
13 - The TRIP ACTUATING DEVICE OPERATIONAL TEST for the reactor trip bypass breakers.shall consist of a bench test which independently verifies that the undervoltage and shunt trip attachments are operable.
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