ML20213F300
| ML20213F300 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 05/07/1987 |
| From: | WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | |
| Shared Package | |
| ML20213F294 | List: |
| References | |
| ET-87-0180, ET-87-180, TAC-65318, NUDOCS 8705150284 | |
| Download: ML20213F300 (6) | |
Text
- _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . . _ _ _ _ _ _ _ - _ _ _ _ _ _ - _ -
1 '.
ATTACHMENT III =
PROPOSED TECHNICAL SPECIFICATION CHANGES (MARKED UP)
I G705150084 870507 PDH ADOCK 05000482 l' PDR 1
- :' Attachment III to ET 87-0180 Page 1 of 5 May 7, 1987
. .TA8LE 3.3 /( N N ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONOS
- 1. Manual Initiation
- a. Safety Injection (ECCS) N.A.
- b. Containment Spray N.A.
- c. Phase "A" Isolation N.A.
- d. Phase "B" Isolation N.A.
- e. Containment Purge Isolation N.A.
- f. Steam Line Isolation N.A.
- g. Feedwater Isolation N.A.
- h. Auxiliary Feedwater N.A.
- i. Essential Service Water N.A.
j Containment Cooling N.A.
- k. Control Room Isolation N.A.
- 1. Reactor Trip N.A.
- m. Emergency Diesel Generators N.A.
- n. Component Cooling Water N.A.
- o. Turbine Trip N.A.
- 2. Containment Pressure-High-1 7
- a. Safety Injection (ECCS) I4)
$ 29 /
- 1) Reactor Trip 52
- 2) feedwat'r e Isolation <7
- 3) Phase "A" Isolation 1.5(5)
- 4) Auxiliary feedwater $ 60
- 5) Essential Service Water < 60(1)
- 6) Containment Cooling 60(1)
- 7) Component Cooling Water N.A.
- 8) Emergency Diesel Generators $ 14(6)
- 9) Turbine Trip N.A.
WOLF CREEK - UNIT 1 3/4 3-29
~
Page 2 of 5
~
Attachment III to ET 87-180 May 7, 1987 TABLE 3.3-5 (Continued) y ,
ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECON05
- 3. Pressurizer Pressure-Low
- a. Safety Injection (ECCS) $ 29 /k4)
Reactor Trip 27
- 1) i2
- 2) Feedwater Isolation <7
- 3) Phase "A" Isolation 2(5)
- 4) Auxiliary Feedwater 1 60
- 5) Essential Service Water < 60 I1)
II)
- 6) Containment Cooling 60
- 7) Component Cooling Water N.A.
- 8) Emergency Diesel Generators 5 14(6)
- 9) Turbine Trip N.A.
- 4. Steam Line Pressure-Low
- a. Safety Injection (ECCS) $ 3)fg4)
Reactor Trip $2 2 N 1)
- 2) Feedwater Isolation <7
- 3) Phase "A" Isolation $ 2(5)
- 4) Auxiliary Feedwater 1 60 I1)
- 5) Essential Service Water 1 60 II)
- 6) Containment Cooling 1 60
- 7) Component Cooling Water N.A.
- 8) Emergency Diesel Generators 5 14(6)
- 9) Turbine Trip N.A.
- b. Steam Line !wlation 1 2(5) 1 WOLF CREEK - UNIT 1 3/4 3-30
. 1. Attachment III to ET 87-0180 Page 3 of 5 May 7, 1987 TABLE 3.3-5 (Continued)
(. \
TABLE NOTATIONS q
(1) Diesel generator starting and sequence loading delays included.
(2) Diesel generator starting delay not included. Offsite power available. -
(3) Diesel generator star sequence loading delay included. RHR pumps not included. INS _RT_A (4) Diesel generator starting and sequence loading delavLnot luded.
Offsite power available. RHR pumps not included. (liN$fR_
(5) Does not include valve closure time.
(6) Includes time for diesel to reach full speed.
WOLF CREEK - UNIT 1 3/4 3-33 1
. : Attachment III to ET 87-0180 Page 4 of 5 May 7,1987
( 3/4.3 INSTRUMENTATION \
BASES 3/4.3.1 and 3/4.3.2 REACTOR TRIP SYSTEM AND ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION The OPERABILITY 'of the Reactor Trip System and the Engineered Safety Features Actuation System instrumentation and interlocks ensure that: (1) the associated ACTION and/or Reactor trip will be initiated when the parameter monitored by each channel or combination thereof reaches its Setpoint, (2) the specified coincidence logic is maintained, (3) sufficient redundancy is main-tained to permit a channel to be out-of-service for testing or maintenance, and (4) sufficient system functional capability is available from diverse parameters.
The OPERABILITY of these systems is required to provide the overall reliability, redundancy, 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 safety analyses. The Surveillance Requirements specified for these systems ensure that the overall system functional capability is maintained comparable 1.o the original design standards. The periodic surveillance tests performed at the minimum frequencies are sufficient to demonstrate this capability.
The Engineered Safety Features Actuation System Instrumentation Trip Setpoints specified in Table 3.3-4 are the nominal values at which the bistables are set for each functional unit. A Setpoint is considered to be adjusted consistent with the nominal value when the "as measured" Setpoint is within the band allowed for calibration accuracy.
Rf o accommodate the instrument drift assumed to occur between operational tests and the accuracy to which Setpoints can be measured and calibrated, Allowable Values for the Setpoints have been specified in Table 3.3-4. Operation with Setpoints less conservative than the Trip Setpoint but within the Allowable Value is acceptable since an allowance has been made in the safety analysis to accommodate this error. An optional provision has been included for determining the OPERABILITY of a channel when its Trip Setpoint is found to exceed the Allowable Value. The methodology of this option utilizes the "as measured" deviation from the specified calibration point for rack and sensor components in conjunction with a statistical combination of the other uncertainties of the instrumentation to measure the process variable and the uncertainties in calibrating the instrumentation. In Equation 3.3-1, 2 + R + S 1 TA, the interactive effects of the errors in the rack and the sensor, and the "as measured" values of the errors are considered. Z, as specified in Table 3.3-4, in percent span, is the statistical summation of errors assumed in the analysis excluding those associated with the sensor and rack drift and the accuracy of their me,surement. TA or Total Allowance is the difference, in percent span, between the Trip Setpoint and the value used in the analysis for the actuation.
R or Rack Error is the "as measured" deviation, in percent span, for the affected channel from the specified Trip Setpoint. S or Sensor Error is either WOLF CREEK - UNIT 1 B 3/4 3-1 ,,
- 't Att:chment III to ET 87-0180 P;ga 5 of 5 May 7,1987 Technical Specification Inserts Insert A Sequential transfer of charging pump suction from the VCT to the RWST (RWST valves open, then VCT valves close) is included.
Insert B (7) Diesel generator starting and sequence loading delays included.
Sequential transfer of charging pump suction from the VCT to the RWST (RWST valves open, then VCT valves close) is not included. Response time assumes only opening of RWST valves.
Insert C ESF response times specified in Table 3.3-5 which include sequential operation of the RWST and VCT valves (Notes 3 and 4) are based on values (
assumed in the non-LOCA safety analysis. These analyses take credit for injection of borated water from the RWST. Injection of borated water is
^
assuued not to occur until the VCT charging pump suction valves are closed following opening of the RWST charging pump suction valves. When the sequential operation of the RWST and VCT valves is not included in the response times (Note 7), the values specified are based on the LOCA analyses. The LOCA analyses take credit for injection flow regardless of the source. Verification of the response times specified in Table 3.3-5 will assure that the assumptions used for the LOCA and non-LOCA analyses with respect to operation of the VCT and RWST valves are valid.
t
_ _ - _ _ _ _ _ _ _ _ - _ .