ML20024D590
| ML20024D590 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 06/30/1983 |
| From: | ALABAMA POWER CO. |
| To: | |
| Shared Package | |
| ML20024D582 | List: |
| References | |
| PROC-830630-01, NUDOCS 8308050294 | |
| Download: ML20024D590 (8) | |
Text
.
~
90#
2282022 02:01 S1/20 VOLUME S FNP-1-EOP-5.0 June 30, 1983 Revision 7 h
FARLEY NUCLEAR PLANT EMERGENCY OPERATING PROCEDURE FNP-1-EOP-5.0 S
r.W
^
E T
Y REACTOR TRIP L
A T
E D
Approved:
Operations superintendent I
~
Data Issued:
Diskette EOP-1
'I 8308050294 830726 PDR ADOCK 05000340 i
e F
pyg
90#
2282022 12:01 SI/20 FNP-1-EOP-5.0 VOLUME 5 FARLEY NUCLEAR PLANT UNIT 1 EMERGENCY OPERATING PROCEDURE EOP-5.0 REACTOR TRIP 1.0 Purpose This procedure provides Symptoms, Automatic Actions, Immediate Operator Actions and Subsequent Operator Actions required for a reactor trip.
2.0 Symptoms 2.1 A reactor trip condition on the First-Out Annunciator panel.
OR 2.2 Trip status Light Box bistables meeting the required coincidence for a reactor trip.
OR 2.3 Parameter Indicators having reached a reactor trip setpoint.
3.0 Automatic Actions 3.1 Reactor Trip-Turbine Trip 3.2 Turbine Trip-Generator Trip l
[-W NOTE l
93/
d when a step is completed place I
! "* V the operators initial or the
[3;.
value noted in the space provided in the left hand margin.
.... i
.%'i
.~.,;
k a
'2
~
Rev. 7 1/4
..m-..
~.
4 20#
2282022 12801 C1/20 VOLUME 5 FNP-1-EOP-5.0 4.0 Immediate Operator Actions p,
4.1 Verify all full length rods fully inserted and nuclear power decreasing. IF NOT confirm a valid reactor trip by Trip Status Light Box bistables meeting the required coincidence for a reactor trip OR Parameter Indicators indicating a reactor trip.
IF confirmed,
~
t THEN manually trip.the react 8r.
IF all M
Tu1T length rods NOT fully inserted OR nuclear power NOT decreasing, refer to EOP-1570.
4.2 Verify the main turbine is tripped.
If not, refer to EOP-lS.
k 4.3 Verify RCS temperature is stable or decreasing.
4.4 Verify 4160V buses lA, 1B, 1C, ID and IE energized on the S/U transformers.
5.0 Subsequent Operator Actions 5.1 Indicate the position of the Reactor Trip and S w ass l
Breakers immediately following the trip by circling the a repriate response, and record Date/ time and initi s.
Manually open any breaker which failed
' to automatically open.
-Reactor Trip Breakers Trip Bypass Breakers A-OPEN CLOSED A-OPEN CLOSED B-OPEN CLOSED B-OPEN CLOSED Date/ Time-Initials 5.2 Announce on the plant paging system " Unit 1 Reactor Trip."
5.3 Trip the main feedwater pumps.
5.4 Start or verify started the motor driven Auxiliary Feedwater pumps.
Feed as necessary to recover steam generator levels to 30 to 40 percent in the narrow range and minimize the effect on T of the cold water into the Steam Generators. "#9 S.4.1 If MDAFW pumps started automatically regain control of the FCV's per FNP-1-SOP-22.0.
N 5.4.2 If the TDAFW pump started, regain control of its FCV's and the turbine per L.
FNP-1-SOP-22.0.
^?
i Rev. 7 2/4
80#
2282024 22:01 81/20
, VOLUME 5 FNP-1-EOP-5.0 CAUTION With insufficient decay heat available overfeeding the steam generators will result in excessive cooldown with no apparent increase in Steam Generator level.
AFW flow must be balanced to limit the i
cooldown rate and regain the steam generator level.
~~
5.4.3 If Condensate Storage Tank level decreases 4
to four (4) feet and Auxiliary Feedwater is required to maintain plant conditions shift the Auxiliary Feedwater pumps suctions to Service Water per FNP-1-SOP-22.0.
5.5 Verify proper steam dump operation and if T is less than or equal to 5470F, verify contf8fler PK464 in manual and demand on the steam pressure controller is adjusted to a setpoint of 1005 psig and place the steam dump mode selector switch to the pressure position and place in Auto Manual l
controller PK464 in automatic.
5.5.1 If one or more steam dump valves fail to close and cannot be shut from the MCB prepare to shut the Main Steam Isolation Valves.
5.6 If the condenser is not available verify proper operation of the atmosphere relief valves.
5.7 The following should be done as rapidly as l
possible and not necessarily in order.
5.7.1 Transfer NR-45 to intermediate range and insure proper power decay.
5.7.2 Isolate main steam drain pots by closing NIN11V555 A, 3, C and D.
5.7.3 If the second stage of the MSR's are in operation push Reset on the Reheat Control Panel.
5.7.4 Secure Auxiliary Steam to Unit 2.
Evaluate the need for isolating steam to
' )4 t
the Auxiliary Building, and if necessary
~ '
secure steam to the Auxiliary Building.
Rev. 6 3/4
60 JO 60#
22C2022 22:01 C1/20 s
VOLUME 5 FNP-1-EOP-5.0 5.7.5 Secure Heater Drain Pumps lA and 1B.
5.7.6 Secure all but one Condensate pump.
0 5.7.7 If T decreases to 543 F block the stea8Yfne low pressure safety injection.
5.7.8 Maintain Pressurizer prassure and level at the no-load values.
5.7.9 Secure one steam jet air ejector.
j 5.7.10 Verify Steam Generator Blowdown is isolated.
CAUTION The intent of closing 'che MSIV's in Step 5.7 is to regain control of the cool-down rate and ensure against 0
exceeding 100 F cooldown in one hour.
If cooldown rate is under control, but tempera-1 ture is decreasing the Shift Supervisor may decide not to shut the MSIV's until a lower temperature is reached.
5.8 If T rapidly decreases to 500 F close the 0
MSIV'57as follows:
5.8.1 Break condenser vacuum.
5.8.2 Isolate gland sealing steam.
5.8.3 Close the MSIV's.
5.9 P.efer to FNP-1-SOP-28.1 to complete Turbine Generator shutdown.
5.10 Complete plant shutdown to Hot Standby per FNP-1-UOP-2.1.
5.11 Start up Auxiliary Boiler using FNP-1-SOP-55.0 if required.
1 Y%A
~
i
~
Rev. 6 4/4
20#
2382022 61:01 81/20
-b.
FNP-1-EOP-15.0 June 30, 1983 Revision 8
~
FARLEY NUCLEAR PLANT EMERGENCY OPERATING PROCEDURE FNP-1-EOP-15.0
/
F E
T s
Y ANTICIPATED TRANSIENTS WITHOUT TRIP (ATWT)
R E
L A
T E
D l
Approved:
1 Operations Superintendent Date Issued:
i Disketta EOP-3 l
r --
e
-,,,---re--v,~r a
--..n. -. -.
80#
22C2022 61801 81/20
~
FNP-1-EOP-15.0
~
9 FARLEY NUCLEAR PLANT UNIT 1 EMERGENCY OPERATING PROCEDURE EOP-15.0 ANTICIPATED TRANSIENTS WITHOUT TRIP (ATWT) 1.0 Purpose This procedure provides guidelines for operator action in the event a reactor trip and/or turbine trip does not occur automatically if either trip is required.
2.0 symptoms 2.1 Entry from E0P-5.0 2.2 Failure to obtain a turbine trip following a turbine trip signal as indicated by the turbine throttle valves NOT closed.
3.0 Automatic Actions None t
NOTE When a step is completed place the operators initial or the value noted in the space provided in the left hand margin.
fem 4.0 Immediate Operator Actions hN*
4.1 Reactor does not trip:
m 4.1.1 Open the supply breakers for the MG sets with main control board handswitches.
If not successful, then:
Emergency Borate 4
and Drive Rods in, t
4.1.2 Go to local panel and manually open and rack out Reactor trip breakers and Reactor trip bypass breaker.
4.2 Turbine does not trip:
4.2.1 Attempt to manually trip the turbine from the Main Control Board.
IF the turbine does not trip, then:
]
Rev. 8 r
- 0#
2282022 02:01 S1/20 FNP-1-EOP-15.0 4.2.2 De-energize the E.H. Pumps lA & 1B from the Main Control Board.
Start all available auxiliary feed pumps and throttle as necessary to maintain S/G level in the narrow range.
IF a turbine trip has not occurred, then:
4.2.3 Close the MSIV's.
5.0 Subsequent Operator Actions 5.1 IF following an automatic turbine trip signal, the turbine does not trip and causes an uncontrolled cooldown, amergency borate in accordance with EOP-6.0.
5.2 When a reactor trip does occur, refer to EOP-S.O.
5.3 When a turbine trip does occur, refer to AOP-3.0.
5.4 IF a safety injection signal occurs, refer to EOP-0.
s 4
i Rev. 7 2/2
__