ML20237H464

Rev 5 to Abnormal Operating Instruction AOI-25.4, Loss of 120-Volt AC Vital Instrument Power Board 1-IV

ML20237H464
Person / Time
Site:	Sequoyah
Issue date:	05/14/1987
From:	Anthony J, Epperson J TENNESSEE VALLEY AUTHORITY
To:
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References
AOI-25.4, NUDOCS 8708170226
Download: ML20237H464 (5)

Text

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TENNESSEE VALLEY AUTHORITY SEQUOYAH' NUCLEAR PLANT f

l ABNORMAL OPERATING INSTRUCTION r;

I A01-25.4 LOSS OF 120V AC VITAL INSTRUMENT POWER BOARD l-IV Unit 1

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Revision 5 i

PREPARED BY:

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

Jeff Epperson SUBMITTED BY:

. M.

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Responsible 'Section Super)/1sor

'ffAY I 4 IS07 PORC REVIEW DATE:

APPROVED BY:

Plant Manager DATE APPROVED:

MAY 'i 41987 Reason for revision (include all Instruction Change Form Nos.):

Revised to streamline operator actions, delete erroneous Appendices "A" and "B".

The last.page of this instruction is number:

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8708170226 87Mh7 PDR ADOCM ppg P

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SEQUOYAH NUCLEAR PLANT PLANT' INSTRUCTION REVISION LOG m

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f ABNORMAL OPERATING INSTRUCTION AOI-25.4 REVISION Date

.Pages REASON FOR REVISION-(INCL.hDE COMMIT-LEVEL Approved Affected MENTS AND ALL ICF FORM NUMBERS) 0 09/03/80 All i

1 12/19/80 2,3,6

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2 09/12/83 All 1

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07/31/84 1, 4

10/04/84 2

Revised to streamline operator actions, 5 MAY " 4 1987 All delete erroneous Appendices "A" and "B".

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9 0999H/ SAT /p1w

p r-SQN A0I-25.4 Page 1

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Revision 5 I.

SYMPTOMS

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A.

Alarms r

1.

120V AC VITAL PWR BD 1-IV UV OR BREAKER TRIP 2.

120V AC VITAL INVERTER l-IV ABNORM L

'B.

Indications 1.

Power Range Channel N-44 failure.

L 2.

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

3.. Loss of feedflow Portion of Signal to Feedwater control system resulting in failure to control steam generator level if channel IV is selected.

4.

Possible Reactor Trip and Turb.

Trip due to Steam Generator Low-Low Level.

5.

Loss or decrease of feedwater flow to all steam generators.

6.

Malfunction of. trip status lights and safeguards systems annunciators.

C.

System Partial Failures 1.

Reduction of feedwater flow due to demand signal from steam generator 4 failing low.

2.

Both trains of Solid State Protection System Protection Set IV input relays lose power.

3.

Loss of Steam Generator Power Operated Relief valves PIC-1-6A and PIC-1-31A if in normal mode.

NOTE: The above failures are of greatest immediate consequence, for complete loads list of vital board 1-IV see Appendix A.

II. AUTOMATIC ACTIONS A.

Possible reactor trip due to low-low S/G 1evel.

.0146H/ SAT /Imt

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AOI-25.4

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Page 2 T

Revision 5'

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J III.

IMMEDIATE OPERATOR ACTIONS I

1 A.

None i

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IV.

SUBSEQUENT OPERATOR ACTIONS i

l' A.

If reactor trip occurs then refer to emergency instructions.

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B.

If reactor does not trip, then, at the NIS panel, defeat the PR rod stop.

C.

Assume and maintain manual rod control.

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NOTE:

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

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i D.

Dispatch operator to restore power to failed board (transfer

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to auxiliary power supply).

l E.

Assume Manual steam generator level control on the affected steam generators.

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F.

Transfer Power Operated Relief valved PIC-1-6A and PIC-1-31A l

to the Auxiliary control room.

j G.

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

H.

Evaluate need to shutdown per TS 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 G0I-3.

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

Refer to TS 3.8.2.2.

NOTE: Operation may be continued at'the discretion 4

of the Manager, operations group, with respect to Tech Spec. section 3.

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I.

Dispatch operator to Cardox units to verify master valves are closed.

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V.

REFERENCES A.

TS 3.8.2.1, 3.8.2.2 B.

S0I-SS Series C.

45N706-4 0146H/ SAT /imt

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I AOI-25.4

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Page 3

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Revision 5

. *j APPENDIX A

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Page 1.of 1 Load List:

120V AC Vital Inst. Power Bd 1-IV

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SSPS (A) CH IV input relays (1-R-46)

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

NIS instr. power CH IV g-NIS control power CH IV

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Process protection set IV (1-R-12)

UHI accumulator CH IV 15o1. valve FCV-87-24 RCP 4 UV and UF relays I

AFWP. turbine flow controller (alternate) FIC-46-57 TDAFWP S/Gs 1 and 2 LIC-3-173, 174 TDAFWP S/Gs 1 and 2 instr. loop l

Incore temp. monitoring system i

PIC-1-13A, 24A instr. bus 4 Aux. control panel B instr. bus Process control group 4 (1-R-22) l-BOP process instr. control rack (1-R-130)

AB instr. B bus 1 Aux. relay rack, B bus (1-R-76) l_

NSSS aux, relay rack, C bus (1-R-58)

• 1 NSSS aux. relay rack, B bus (1-R-58)

Aux. relay rack, B bus (1-R-75) 1 Aux. relay rack, C bus-(1-R-75)

L Aux. control panel, B relay bus Aux. control panel, B instr. bus Reactor vessel level instrumentation system (1-R-148).

Control air header B moisture alarm Aux. relay rack, B bus (1-R-72)

Aux. relay rack, C bus (1-R-72)

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Post accident monitoring 2 f..

LOCA H, contmt. flow monitor XI-43-210 CO, fire protection turb. and serv. bidgs.

C0, fire protection DG 1B, 2B, and fuel oil room Reactor vessel level instrumentation system (JB 4031)

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UHI instr. bus 4 t

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0146H/ SAT /imt

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