ML20074A811

Rev 6 to Emergency Operating Procedure FNP-1-EOP-5.0, Reactor Trip

ML20074A811
Person / Time
Site:	Farley
Issue date:	05/09/1983
From:	ALABAMA POWER CO.
To:
Shared Package
ML20074A803	List: ML20074A802 ML20074A811 ML20074A818
References
FNP-1-EOP-5.0, NUDOCS 8305160100
Download: ML20074A811 (6)

Text

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VOLUME 5 FNP-1-EOP-5.0

May 6, 1983 i Revision 6 i

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I j FARLEY NUCLEAR PLANT EMERGENCY OPERATING PROCEDURE f

FNP-1-EOP-5.0

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Operationssuperigtendent

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Date Issued: /33 Diskette EOP-1 8305160100 830510 PDR ADOCK 05000348 G PDR

V01;UME 5 FNP-1-EOP-5.0

. LIST OF EFFECTIVE PAGES REVISION NO. 5 PAGE NO. 0 1 2 3 4 5 6 7 '8 9 10 11 1 X. X X y 7 2 X X X X X x 3 X X X x 4 X x i

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VOLUME 5 FNP-1-EOP-5.0 FARLEY NUCLEAR PLANT

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v 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 l Actions required for a reactor trip.

2.0 Symptoms 2.1 Any reactor trip indicated on the First-Out Annunciator Panel.

3.0 Automatic Actions 3.1 Reactor Trip-Turbine Trip 1

3.2 Turbine Trip-Generator Trip NOTE When a step is completed place the operators initial or the .

value noted in the space provided T s in the left hand margin.

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>P 4.0 Immediate Operator Actions c y

() -[e l am Date of trip:

C') # f, 4.1 Verify Reactor Tripped by observing all full

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length rods fully inserted and nuclear power decreasing. If not, refer to EOP-15.

a 4.2 Verify the main turbine is tripped. If not, F~ refer to EOP-15.

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4.3 Verify RCS temperature is stable or decreasing.

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4.4 Verify 4160V buses lA, 1B, 1C, 1D and lE energized

~r 4- y on the S/U transformers.

)<()(h 5.0 Sabsequent Operator Actions 5.1 Indicate the position of the Reactor Trip and Bypass Breakers immediately following the trip by circling the appropriate response, and record Date/ time and i Ci initials. Manually open any breaker which failed to automatically open.

Rev. 6 1/4 i

VOLUME 5 FNP-1-EOP-5.0

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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"V9 of the cold water into the Steam Generators.

5.4.1 If MDAFW pumps started automatically regain control of the FCV's per FNP-1-SOP-22.0.

5.4.2 If the TDAFW pump started, regain control of its FCV's and the turbine per

>- 3 FNP-1-SOP-22.0.

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CAUTION

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-!  !? - With insufficient decay heat J %o available overfeeding the steam

() N "S Qd generators will result in excessive cooldown with no l-~ apparent increase in Steam 2[ '79 5

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Generator level. AFW flow

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i must be balanced to limit the cooldown rate and regain the

_, [3 ) steam generator level.

S~L) <[ b 5.4.3 If Condensate Storage Tank level decreases 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 contf521er-Os PK464 in manual and demand on the steam pressure controller is adjusted to a setpoint of 1005 psig Rev. 6 2/4

VOLUME 5 FNP-1-EOP-5.0 and place the steam dump mode selector switch to O the pressure position and place in Auto Manual 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 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 N1N11V555 A, B, 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.

O Evaluate the need for isolating steam to the Auxiliary Building, and if necessary secure steam to the Auxiliary Building.

5.7.5 Secure Heater Drain Pumps lA and 1B.

5.7.6 Secure all but one Condensate pump.

5.7.7 If T decreases to 543 0 F block the stea8YIne low pressure safety injection.

5.7.8 Maintain Pressurizer pressure and level at the no-load values.

5.7.9 Secure one steam jet air ejector.

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CAUTION: .mo- =;nX;;~; .

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Rev. 6 1

3/4

,, VOLUME 5 FNP-1-EOP-5.0 5.7.10 Verify Steam Generator Blowdown is isolated.

CAUTION The intent of closing the MSIV's in Step 5.7 is to regain control of the cool-down rate and ensure against exceeding 100 0 F cooldown in one hour. If cooldown rate is under control, but tempera-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 0 F close the MSIV4 59as follows:

5.8.1 Break condenser vacuum.

5.8.2 Isolate gland sealing steam.

5.8.3 Close the MSIV's.

5.9 Refer to FNP-1-SOP-28.1 to complete Turbine Generator shutdown. c 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.

UNCONTROLLED - s-g CO CAUTIONCS

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Rev. 6 4/4