ML20067B717
| ML20067B717 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 02/14/1994 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20067B708 | List: |
| References | |
| NUDOCS 9402250066 | |
| Download: ML20067B717 (19) | |
Text
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TNDEX LIST OF. TABLES TABLE PAGE 1.1 FREQUENCY N0TATION......................................
1-9
- 1. 2 OPERATIONAL H00ES.......................................
1-10 2.2-1 REACTOR PROTECTIVE INSTRUM LIMITS....................ENTATION TRIP SETPOINT.
2-3 2.2-2 CORE PROTECTION CALCULATOR ADORESSABLE CONSTANTS........
2-5 MONITORING FREQUENCIES FOR BORON OILUTION DETECTION 3.1-1 Kg7 > 0.98.............................................
3/4 1-17 3.1-2 0.98 > Kdf>0.97......................................
3/4 1-17a 3.1-3 0. 9 7 > K, f f > 0. 9 6......................................
3/4 1-17b 3.1-4
- 0. 96 > Kdf>0.95......................................
3/4 1-17c 3.1-5 Kd f < 0.95.............................................
3/4 1-17d 3.3-1 REACTOR PROTECTIVE INSTRUMENTATION......................
3/4 3-3 3.3-2 REACTOR PROTECTIVE INSTRUMENTATION RESPONSE TIMES.......
3/4 3-8 4.3-1
-REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE s
REQUIREMENTS............................................
3/4 3-10 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION.........................................
3/4 3-14 3.3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES.............................
3/4 3-19 3.3-5 ENGINEERED SAFETY FEATURES RESPONSE TIMES...............
3/4 3-22 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS...............
3/4 3-25 3.3-6 RADIATION HONITORING INSTRUMENTATION....................3/4 3-29 4.3-3 RADIATION HONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS...............................
3/4 3-32 3.3-7 SEISMIC HONITORING INSTRUMENTATION......................
3/4 3-36 4.3-4 SEISMIC HONITORING INSTRLHENTATION SURVEILLANCE REQUIRENENTS...............................
3/4 3-37 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION...............
3/4 3-39 WATERFORD - UNIT 3 XX AMEN 0 MENT NO. 9 9402250066 940214 PDR ADOCK 0500 2
P N
7-3 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION LIMITING CONDITION FOR OPERATION t
3.3.1 As a minimum, the reactor protective instrumentation channels and bypasses of Table 3.3-1 shall be OPERABLE with RESPONSE TIMES as shown in Table 3.3-2.
APPLICABILITY:
As shown in Table 3.3-1.
i ACTION:
As snown in Table 3.3-1.
SURVEILLANCE REOUIREMENTS 1
J. 3.1.1 Each reactor protective instrumentation cnannel shall be demonstrated CPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MODES and at tne frequencies snown in Taole 4.3-1.
i 4.3.1.2 The logic for the bypasses shall be demonstrated OPERABLE prior to i
each reactor startup unless performed during the preceding 92 days. The total oypass function-shall be demonstrated CPERABLE at least once per 18 months ouring CHANNEL CALIBRATION testing of each channel affected by bypass operation.
- 1. 3.1. 3 The REACTOR TRIP SYSTEM RESPONSE TIME of each reactor trip function shall be demonstrated to be within its limit at least once per 13 montns.
Each test snall incluoe at least one channel per function such that all cnanne's are tested at least once every N times 18 months where N is the total numoer of redundant channels in a specific reactor trip tunction as shown in the i
" Total No. of Channels" column of Table 3.3-1.
- 4. 3.1. 4 The isolation characteristics of eacn CEA isolation amplifier and eacn optical isolator for CEA Calculator to Core Protection Calculator cata transfer shall be verified at least once per 18 months during the shutdown per the following tests:
a.
For the CEA position isolation amplifiers:
1.
With 120 volts AC (60 Hz) applied for at least 30 seconds across tne output, the reading on the input does not exceed 0.015 volts DC.
WATERFORD - UNIT 3 3/4 3-1 l
r.
I
y TABLE 3.3-2 k
REACTOR PROTECTIVE INSTRUMENTATION RESPONSE TIMES E
ag FUNCTIONAL UNIT RESPONSE TIME
[
1.
Manual Reactor Trip Not Applicable 5
]
2.
Linear Power Level - High 5 0.40 second*
3.
Logarithmic Power Level - High
< 0.40 second*
4.
Pressurizer Pressure - High
< 0.90 second S.
Pressurizer Pressure - Low
< 0.90 second 6.
Containment Pressure - High
< 1.70 seconds 7.
Steam Generator Pressure - Low
< 0.90 second w1 8.
Steam Generator Level - Low i 0.90 second w
9.
Local Power Density - High a.
Neutron Flux Power from Excore Neutron Detectors
< 0.429 second*
b.
CEA Positions 7 0.424 second**
c.
CEA Positions:
CEAC Penalty bctor 50.379second 10.
DNBR - Low a.
Neutron Flux Power from Excore Neutica Oetectors
< 0.429 second*
b.
CEA Positions 7 0.424 second**
h c.
Cold Leg Temperature 50.258second#
d.
Hot Leg Temperature
< 0.429 second#
e.
Primary Coolant Pump Shaft Speed 30.237second**
f.
Reactor Coolant Pressure from Pressurizer
< 0.429 second##
g.
CEA Positions:
CEAC Penalty Factor
{0.379second P
N
=
i TABLE 3.3-2 (Continued)
REACTOR PROTECTIVE INSTRUMENTATION RESPONSE TIMES E3 E3 FUNCTIONAL UNIT RESPONSE TIME 11.
Steam Generator Level - High Not Applicable 5
12.
Reactor Protection System logic Not Applicable
{
13.
Reactor Trip Breakers Not Applicable 14.
Core Protection Calculators Not Applicable 15.
CEA Calculators Not Applicable 16.
Reactor Coolant Flow - Low 0.70 second M
s Y
- Neutron detectors are exempt from response time testing.
Response time of the neutron flux signal portion of the channel shall be measured from detector output or input of first electronic component in channel.
u'
- Response time shall be measured from the time the CPC/CEAC receives an input signal until the electrical power is interrupted to the CEA drive mechanism.
- Response time shall be measured from the output of the sensor.
RTD response time for all the RTDs shall be measured at least once per 18 months.
The measured P of the slowest RIO shall be less than I
or equal to 8 seconds (P, assumed in the safety analysis).
- Response time shall be measured from the output of the pressure transmitter.
The transmitter response E
ti.ne shall be less than or equal to 0.70 second.
m E.
fl
-)
i INSTRUMENTATION
'j 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION t
LIMITING CONDITION FOR OPERATION i
3.3.2 The Engineered Safety Features Actuation System (ESFAS) instrumentation' channels and bypasses shown in Table 3.3-3 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-4 and with RESPONSE TIMES as shown in Table 3.3-5.
APPLICABILITY:
As shown in Table 3.3-3.
ACTION:
a.
With an ESFAS instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3-4, i
declare the cnannel inoperable and apply the applicable ACTION l
requirement of Table 3.3-3 until the channel is restored to OPERABLE status with the trip setpoint adjusted consistent with the Trio Setpoint value.
b.
With an ESFAS instrumentation channel inoperable, take tne ACTION shown in Table 3.3-3.
i
^l SURVEILLANCE REQUIREMENTS 4.3.2.1 Eacn ESFAS instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MODES and at the frecuencies shown in Table 4.3-2.
4.3.2.2 The logic for the bypasses shall be demonstrated OPERABLE ouring the l
at power CHANNEL FUNCTIONAL TEST of channels affected by bypass operation.
The total bypass function shall be demonstrated OPERABLE at least once per 15 months during CHANNEL CALIBRATION testing of each channel affected by oypass operation.
4.3.2.3 The ENGINEERED SAFETY FEATURES RESPONSE TIME of each ESFAS function shall be demonstrated to be witnin the limit at least once per 18 months.
Eacn test shall include at least one channel per function such that all cnannels
.i are tested at least once every N times 18 months where N is the total number
]
of redundant cnannels in a specific ESFAS function as shown in the " Total No.
)
of Channels" Column of Table 3.3-3.
WATERFORD - UNIT 3 3/4 3-13 l
TABLE 3.3-5 ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONOS 1.
Manual a.
Not Applicable Shield Building Filtration System Not Applicable
.j b.
CSAS Containment Spray Not Applicable c.
CIAS Containment Isolation Not Applicable d.
MSIS Main Steam Isolation Not Applicable e
RAS Safety Injection System Sump Recirculation Not Applicable f.
EFAS s
Emergency Feedwater Pumps Not Applicable 1
i I
l I
WATERFORD - UNIT 3 3/4 3-22
TABLE 3.3-5 (Continued)
ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONOS i
2.
Pressurizer Pressure-Low a.
Safety Injection (ECCS)
(1) High Pressure Safety Injection
< 30.0*/18.5**
(2) Low Pressure Safety Injection 545.5*/34.0**
b.
Containment Isolation i 23.5*/12.0**
c.
Containment Cooling 1 31.0*/19.5**
3.
Containment Pressure-High a.
Safety Injection (ECCS)
I (1) High Pressure Safety Injection
< 30.0*/18.5**
(2) Low Pressure Safety Injection 345.5*/34.0**
b.
Containment Isolation
< 23.5*/12.0**
c.
Main Steam Isolation I 5.0*/5.0**
l d.
Main Feedwater Isolation 56.0*/6.0**
i e.
Containment Cooling i 31.0*/19.5**
4.
Containment Pressure--High-High a.
Containment Spray Pump i 15.2*/2.7**
b.
Containment Spray Valves
< 11.0*/11.0**
c.
CCW to RCP Valves 323.5*/12.0**
5.
Containment Area Radiation-High#
Containment Purge Valves Isolation i 6.2*/6.2**
6.
Steam Generator Pressure-Low a.
Main Steam Isolation
< 5.0*/5.0**
(
b.
Main Feedwater Isolation 7 6.0*/6.0**
j 7.
Refueling Water Storage Pool-Low l
Containment Sump Recirculation i 120.0*/108.5**
8.
4.16 kV Emergency Bus Undervoltage (Loss of Voltage)
Loss of Poder (0 volts)
~
$ 2***
9.
480V Emergency Bus Undervoltage (Less of Voltage)
Loss of Power (0 volts)
N.A.
10.
4.16 kV Emergency Bus Undervoltage (Degraded Voltage)
Loss of Power i 14***
WATERFORD - UNIT 3 3/4 3-23 Amendment No.
74, 76 L
A R
TABLE 3.3-5 (Continued)
ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECON05 11.
Steam Generator Level-Low Emergency Feedwater Pump and
< 54.0*/42.0**
Block Valves 12.
Wide Range Steam Generator Level-Low Emergency Feedwater Control Valves
< 25.0*/25.0**
l NOTE:
Response time for all Motor-Driven
-< 54.0 and Steam-Driven Emergency Feedwater Pumps on all ESF signal starts.
TABLE NOTATIONS
- Diesel generator starting and sequence loading delays included.
Response
time limit includes movement of valves and attainment of pump or blower discharge pressure.
- Diesel generator starting and sequence loading delays not included.
Offsite power available.
Response time limit includes movement of valves and attainment of pump or blower discharge pressure.
- Response time measured from the sensing relay to the channel output only.
- Response time does not include the detector.
WATERFORD - UNIT 3 3/4 3-24
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INDEX LIST OF TABLES TABLE PAGE 1.1 FREQUENCY N0TATION......................................
1-9
- 1. 2 OPERATIONAL M00ES.......................................
1-10 2.2-1 REACTOR PROTECTIVE INSTRUMENTAT LIMITS.......................... ION TRIP SETPOINT.
2-3 2.2-2 CORE PROTECTION CALCULATOR ADDRESSA8LE CONSTANTS........
2-5 MONITORING FREQUENCIES FOR BORON DILUTION DETECTION 3.1-1 K,7f > 0.98.............................................
3/4 1-17 3.1-2
- 0. 98 > K, f f > 0. 9 7......................................
3/4 1-17a 3.1-3 0. 9 7 > K, f f > 0. 9 6......................................
3/4 1-17b 3.1-4 0. 9 6 > K, f f > 0. 9 5......................................
3/4 1-17c 3.1-5 K,ff < 0.95.............................................
3/4 1-17d 3.3-1 REACTOR PROTECTIVE INSTRUMENTATION...................... 3/4 3-3 N
3.3-2 REACTOR PROTECTIVE INSTRUMENTATION RESPONSE TIMES.......
3/4 3-8 4.3-1 REACTOR PROTECTIVE INSTRUMENTATION SU REQUIREMENTS.........................RVE LLANC 3/4 3-10
).3-3
[)E LElrt ENGINEERED SAFETY FEATURES ACTUATION SYSTEM l
INSTRUMENTATION.........................................
3/4 3-14 i'
3.3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES.............................
3/4 3-19 3.3-5 ENGINEERED SAFETY FEATURES RESPONSE TIMES...............
3/4 3-22 4.3-2 ENGINEERED SAFETY FEATURES ACTU ION 5 EM INSTRUMENTATION SURVEILLANCE REQUIREMENTS...............
3/4 3-25 3.3-6 RADIATION MONITORING INSTRUMENTATION.................... 3/4 3-29 4.3-3 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS...............................
3/4 3-32 3.3-7 SEISMIC MONITORING INSTRUMENTATION......................
3/4 3-36 4.3-4 SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS...............................
3/4 3-37 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION...............3/4 3-39 WATERFORD - UNIT 3 XX AMENOMENT NO. 9 I-
,. -.- ~ _. - -. -. - ~
-. - - - -. _.. - ~..... -..-. -
2 3/4.3 INSTRUMENTATION r
)
3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION LIMITINGCONDITIONFOROPERATION l
3.3.1 As a minimum, the reactor protective instrumentation channels and bypasses of Table 3.3-1 shall be OPERABLE.-**@ RES"SE TIMES as shown to T4b' : 1 3 2.
l e
l APPLICABILITY-As shown in Table 3.3-1.
r ACTION:
)
As shown in Table 3.3-1.
l SURVEILLANCE REQUIREMENTS i
i 4.3.1.1 Each reactor protective instrumentation channel shall be demonstratea j
l OPERABLE by the performance of the CHANNEL CHECK. CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MODES and at the frequencies shown in Table 4.3-1.
I j
4.31.2.The logic for the bypasses shall be demonstrated OPERABLE prior to s
each reactor startup unless performed during the preceding 92 days. The total bypass function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing of each Channel affected by bypass operation.
i 4.3.1.3 The REACTOR TRIP SYSTEM RESPONSE TIME of each reactor trip function shall be demonstrated to be within its limit at least once per 18 months.
l Neutron detectors are exempt from response time testing. Each test shall l
include at least one channel per function such that all channels are tested at least once every N tines 18 months where N is the total number of redundant j
channels in a specific reactor trip function as shown in the " Total No, of j-Channels" column of Table 3.31.
i 4.3.1.4 The isolation characteristics of each CEA isolation amplifier and l
each optical isolator for CEA Calculator to Core Protection Calculator data 4
transfer shall be verified at least once per 18 months during the shutdown per t
the following tests:
]
a.
For the CEA position isolation amplifiers:
i 1.
With 120 volts AC (60 Hz) applied for at least 30 seconds across the output the reading on the input does not exceed 0.015 volts DC.
1 I
i t
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l WATERFORD - UNIT 3 3/4 3-8 b-
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ns INSTRUMENTATION 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION i
LIMITING CONDITION FOR OPERATION I
3.3.2 The Engineered Safety Features Actuation System (ESFAS) instrumentation channels and bypasses shown in Table 3.3-3 snall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-4. -s"3
't4 ;f5;0NSE TIMES es s"-
^
4" Table 3.3 E l
APPLICABILITY: As shown in Table 3.3-3.
i ACTION:
a.
With an ESFAS instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3-4 declare the channel inoperable and apply the applicable ACTION requirement of Table 3.3-3 until the channel is restored to OPERABLE status with the trip setpoint adjusted consistent with the Trip Setpoint value.
b.
With an ESFAS instrumentation channel inoperable, take the ACTION shown in Table 3.3-3.
SURVEILLANCE REQUIREMENTS 4.3.2.1 Each ESFAS instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MODES and at the frequencies shown in Table 4.3-2.
i 1
4.3.2.2 The logic for the bypasses shall be demonstrated OPERABLE during the at power CHANNEL FUNCTIONAL TEST of channels affected by bypass operation.
The total bypass function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing of each channel affected by i
Dypass operation.
4.3.2.3 The ENGINEERED SAFETY FEATURES RESPONSE TIME of each ESFAS function j
snall be demonstrated to be within the limit at least once per 18 months.
I Each test shall include at least one Channel per function such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific ESFAS function as shown in the " Total No.
of Channels' Column of Table 3.3-3.
j
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h Pages 3/4 3-23 and 3/4 3-24 have been deleted.
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WATERFORD - UNIT 3 3/4 3-22 l
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