ML20237H430

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Rev 5 to Abnormal Operating Instruction AOI-25.1, Loss of 120-Volt AC Vital Instrument Power Board 1-I
ML20237H430
Person / Time
Site: Sequoyah Tennessee Valley Authority icon.png
Issue date: 05/15/1987
From: Anthony J, Epperson J
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20237H133 List: ... further results
References
AOI-25.1, NUDOCS 8708170209
Download: ML20237H430 (7)
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I TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT ABNORMAL OPERATING INSTRUCTION h

A0I-25.1 LOSS OF 120V AC VITAL INSTRUMENT POWER BOARD 1-I Unit 1

.j Revision 5 PREPARED BY:

J. M. Anthony RESPONSIBLE SECTION: Operations REVISED BY:

Jeff Epperson sh SUBMITTEI BY:

M Responsible Sdction Supervisor PORC REVIEW DATE:

. M,AY 151987 l

APPROVED BY:

Plant Manager DATE APPROVED:

MAYl 51987 Reason for revision (include all Instruction Change Form Nos.):

Streamline Operator actions, delete erroneous Appendices "A" and "B".

This revision constitutes a biennial revision in accordance with AI-4, Appendix H.

The last page of this instruction is number:

5 m.

M resa

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.3 SEQUOYAH NUCLEAR PLANT PLANT INSTRUCTION REVISION LOG e

ABNORMAL OPERATING INSTRUCTION AOI-25.1-REVISION Date-Pages REASON FOR REVISION (INCLUDE COMMIT-LEVEL' Approved Affected MENTS AND ALL ICF FORM NUMBERS) 0 09/03/80 All-1 12/12/80 2,3,8 2

09/12/83 All 3

07/31/84 1,9-4 10/04/84 2

Streamline Operator actions, delete erroneous Appendices "A" and "B".

This revision constitutes MAY 1 5 1987 a bienniai revision in accordance with 5

All AI-4, Appendix H-l 0126H/ SAT /bbh

f SQN AOI-25.1 4

Page 1 Revision 5 I.

SYMPTOMS A.

Alarms r

1.

120V AC VITAL PWR BD l-I UV OR BREAKER TRIP 2.

120V AC VITAL INVERTER l-I ABNORMAL B.'

Indications 1.

Power Range N-41, failure 2.

Auto and manual Rod Block and Rod Stop due to High Flux Rod Stop, and C-5 Interlock.

3.

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Loss of steam flow portion of signal to feedwater control system resulting in failure to control steam generator level if channel 1 is selected.

LI 4.

Loss of steam generator level control due to loss of input signal to program on steam generators 2 and 3.

5..

Main feed pumps go to minimum speed due to loss of input signal (PT-1-33) to speed controller.

6.

Possible reactor trip due to steam generator level changes.

7.

Malfunction of trip status. lights and safeguards systems annunciators.

8.

Loss of auto-makeup to volume control tank.

C.

System Partial failures 1.

Loss of CVCS Auto-Makeup to Volume Control Tank.

FCV-62-89 falls open (Charging Line Flow Controller) a.

2.

Possible swap-over of charging system from volume control tank to refueling water storage tank.

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3.

Letdown divert valve LCV-62-118 diverts to hold-up tank and TIS-62-79 bypasses letdown demineralizers.

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SQN AOI-25.1 Page 2

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3 Revision 5 i

I.

SYMPTOMS (cont.)

C.

System Partial Failures (cont.)

4.

Loss of power to Solid State Protection Sydtem input and output relays (Train A) and Channel 1 input relays (Trains'A-

.and B)'.

5.

If pressurizer level'is selectdd to channel LT-68-339 f control, pressurizer lo level auto actions will occur. or

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s 6.

If pressurizer pressure is selected to chann-el PT-6'4-3m.,

The sprays will be closed and the back-up hesters energized until locked out by the low level signal if LT-68-339 was '

selected for level control.

s 7.

Loss of condenser steam dump capability.

A

8. ' Loss of automatic control in'AFW system of LCV-3-164.156, (Level control for S/G's 1 and 2) for Motor Driven AFW Pump 1A-A.

9.

Loss of automatic control in AFH system of LCV-3-172, 175 (Level control for S/G's 3 and O for Turbine Driven AFW Pump 1A-S.

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NOTE:

The above failures &re of greatest immediate consequence, for complete loads list of vital board 1-I see Appendix A.

L II.. AUTOMATIC ACTIONS s

g A.

Possiblereactortripduetojow-lows /G1ev'e1.

III.

IMMEDIATE OPERATOR ACTIONS A.

None IV. SUBSEQUENT OPERATOR ACTIONS r

A.

x.

If reactor trip occurs, then refer to hmergency' instructions.

sN B.

If reactor does not trip, then, at the MS panel, defeat the PR s

o rod stop.

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0153H/ SAT /1gm s

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f SQN AOI-25.1 Page 3 Revision 5 IV.

SUBSEQUENT OPERATOR ACTIONS (cont.)

C.

Assume.and maintain manual rod control (TREF signal is lost).

NOTE:

Do not use bank select; use of bank select will cause the bank overlap program.to be lost.

s D.

Disp 4tch operator to restore power to failed board (transfer to auxiliary power supply).

E.

Assume manual control of steam generator water level on the affected steam generators.

F.

Assume n snual control of main feedwater pumps speed to adjust feedwater pressure.

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' Verify pressurizer level ar.d pressure are not selected to G.

LT-68-339 and-PT-68-340 respectively.

1.

Transfer FCV-62-89 to Auxiliary control room.

NOTE:

Verify charging line flow controller functioning to restore program level.

H.

Assume manual' control of volume control tank level l

NOTE:

If RWST suction valves to charging pump suctions are opened auto:natically - verify VCT level prior to returning to VCT suction valves.

I-I.

If power is restored to the failed boards return systems to normal operating mode.

NOTE:

Due to feedback signals and time delays in circuitry,

. controllers may not control immediately.

J.

Evaluate need to shutdown per TS.6.3.8.2.1 if power cannot be restored to the affected board.

If necessary, commence orderly shutdown to the hot standby condition per G01-5 and GOI-3.

..[

Initiate REP per IP-1 (Engineered Safety Features) as required.

O 1.

Steam Generator power operated relief valves are operable for cooldown using hand switch.

7 i

NOTE:

Operation in this mode may be continued at the discretion of the Manager, Operations Group, with respect to Tech. Spec. section 3.

0153H/ SAT /lgm

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E' SON AOI-25.1 Page 4 Revision 5 IV.

SUBSEQUENT OPERATOR ACTIONS (cont.)

2.

If shutdown is to continue to mode 5. follow GOI-3 with the following exception:

74-1 valve will require placing transfer sw. to Aux position at breaker to open valve when RCS pressure is below 380 psig.

Refer to TS 3.8.2.2 3.

Transfer FCV-74-16 and 32 to Aux. mode and control RHR cooldown temperature from Aux. control room.

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0153H/ SAT /lgm g

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SQN AOI-25.1 Page 5

-Revision 5

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APPENDIX A Page 1 of 1 l.

e Load List:

120V AC VITAL INST.' POWER BD.1-I SSPS (A) CH I input and train A output relays (1-R-48)

SSPS (B)'CH I input relays (1-R-49)

NIS instr. power CH I NIS I control power.CH I 1

Process protection set I (1-R-1)

FSV-87-21 UHI accumulator isol. valve (CH I)

ERCH and containment rad. monitor 1-RE-90-106 l

Instrument Bus A l

l Aux. relay rack, SSPS aux. relays (1-R-73)

RB isol.' valve FCV-32-80A, 808, 110A, 1108 l

Aux compressor A, AB isol. valve FCV-32-82

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Rad. rate meters and 1-RI-90-106 Rad, monitor 0-RE-90-125 125V dc vital battery board I instruments Letdown flow temperature switch TIS-62-79 Chlorine detector CLAN-43-205A Post accident sampling solenoid valves PC0-65-81 and 86 aux. relays (1-R-73)

Toilet, locker, spreading, and cont, rooms 1501. dampers-FC0-31A-17, 103, FCV-31A-105A, 1058 (1-R-73)

B0P process instr. control rack (1-R-128) l AB instr. Bus A 0-FCV-12-82 Containment purge air exhaust rad. monitor 1-RE-90-130 I-NSSS aux. relay rack, A bus (1-R-54)

Aux. relay rack sep. and aux. relays (1-R-73)

Aux. control panel, A relay bus Aux. control panel,- A instr. bus

'l-Reactor vessel level instrumentation Fystem (1-R-148)

Aux. dryer train A

' Aux. relay rack sep. and aux. relays (1-R-74)

BAT A htr. A-A controller TIT-62-239 AB gas treatment fan A-A press. controller BAT C htr. A-A controller TIT-62-243 Rad monitor 0-RE-90-205 Process control group 1 (1-R-14)

Instrument bus 1 (0-M-278)

Plugmold instr. bus 1 (1-M-5,1-M-6)

Instrument bus 1 and PIC-1-6A, 31A (1-M-4)

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Fire pump 2A-A sep. relays AB general exhaust fan 1A flow controller UHI instr. bus 1 0153H/ SAT /lgm M

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