ML20210F219
| ML20210F219 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 02/04/1987 |
| From: | WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | |
| Shared Package | |
| ML20210F193 | List: |
| References | |
| E, E-0, NUDOCS 8702110030 | |
| Download: ML20210F219 (3) | |
Text
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E-0 REACTOR TRIP OR SAFETY INJECTION Rev. 3 ENERGENCY OPERATING PROCEDURE E-0 REACTOR TRIP OR SAFETY INJECTION A.
PURPOSE This procedure provides instructions to verify proper response of the automatic protection systems following manual or auto-matic actuation of a reactor trip or safety injection, to assess plant conditions, and to identify the appropriate recovery procedure.
NOTE:
Steps 1 through 14 are IMMEDIATE ACTION steps ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 1.
Verify Reactor Trip 2.
Verify Turbine Trip 3.
Verify Power to NB01/NB02 4.
Check If SI IS Actuated NOTE:
Be aware that ES-0.0, REDIAGNOSIS, is available to help provide direction in determining proper accident analysis.
5.
Ensure Feedwater Isolation 6.
Ensure CISA 7.
Ensure AFW Actuation 8.
Ensure SI Initiation 9.
Ensure One CCW Pump Running in Each Train 10.
Ensure ESW Pumps -
RUNNING 8702110030 870204 PDR ADOCK 05000482 P
PDR ATTACHMENT 3 e
2 -
E-0 REACTOR ~ TRIP OR SAFETY INJECTION Rev. 3 If ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 11.
Ensure Containment' Coolers - RUNNING IN SLOW SPEED 4
12.
Ensure CPIS 4
13.
Check If Main Steam-lines Should Be Isolated 4
14.
Ensure Containment Spray Not Required 15.
Ensure Safety Injection Flow 16.
Ensure AFW Flow -
GREATER THAN 260,000 LBM/HR.
1 77.
Ensure AFW Valve Align-ment - PROPER EMERGENCY-ALIGNMENT 18.
Ensure SI Valve Align-ment - PROPER EMERGENCY ALIGNMENT 19.
Check RCS Average Temp-erature - STABLE AT OR TRENDING TO 557 DEG.
F.
1 20.
Check PZR PORVs And Spray Valves 21.
Check If RCPs Should Be i
Stopped 22.
Check If SGs Are Not Faulted-i i
Y ATTACHMENT 3 -
- E-0 REACTOR TRIP OR SAFETY INJECTION Rev. 3 ACTION / EXPECTED REiPONSE RESPONSE-NOT OBTAINED 23.
Check If SG Tubes Are Not Ruptured a.
Condenser Air a.
Go To E-3, (STEAM Removal Radiation -
GENERATOR TUBE NORMAL RUPTURE), Step 1.
b.
SG Blowdown Radia-b.
Go to_E-3, (STEAM tion - NORMAL GENERATOR TUBE RUPTURE), Step 1.
24.
Check If RCS Is Intact 25.
Check If SI Flow Should Be Reduced c.
RCS Pressure - STABLE c.
DO NOT STOP ECCS OR INCREASING PUMPS.
Go to Step 27.
d.
PZR level - GREATER d.
DO NOT STOP ECCS THAN 5%
PUMPS.
T 27.
Implement CSF-1 (CRITICAL SAFETY FUNCTION STATUS TREES)
CAUTION:
Alternate water sources for AFW pumps will be necessary if CST level decreases to less than 15%.
28.
Check SG Levels b.
IF narrow range level in any SG b.
Control feed flow to continues to maintain narrow range increase in an level between 4% and 50%.
uncontrolled manner, THEN go to E-3, (STEAM GENER-ATOR TUBE RUPTURE), Step 1.
29.
Check Secondary 29.
Go to E-3 (STEAM GENER-Radiation - NORMAL ATOR TUBE RUPTURE),
Step 1.
)
ATTACHMENT 3 1
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