ML20205B383

Rev 4 to Emergency Operating Procedure EOP 35 ES-1.1, Safety Injection Termination

ML20205B383
Person / Time
Site:	Millstone, Haddam Neck, 05000000
Issue date:	06/15/1988
From:	CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20204H467	List: A07413, Forwards Specific Emergency Operating Procedures for Use During Incident Response Ctr Activation ML20204H704 ML20204H734 ML20204H868 ML20204H928 ML20204H963 ML20204J027 ML20204J039 ML20204J092 ML20204J109 ML20204J115 ML20204J120 ML20204J128 ML20204J133 ML20204J139 ML20204J147 ML20204J497 ML20204J543 ML20204J565 ML20204J627 ML20204J633 ML20204J638 ML20204J642 ML20204J659 ML20204J669 ML20204J685 ML20204J707 ML20204J733 ML20204J739 ML20204J746 ML20204J767 ML20204J781 ML20204J786 ML20204J814 ML20204J824 ML20204J849 ML20204J853 ML20204J865 ML20204J878 ML20204J902 ML20204J914 ML20204J920 ML20204J939 ML20204J947 ML20204J954 ML20204J958 ML20204J965 ML20204J975 ML20204J982 ML20204J994 ... further results
References
EOP-35-ES-1.1, NUDOCS 8810260233
Download: ML20205B383 (15)

Text

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STATION PROCEDURE COVER SHEET

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A.

IDENTIFICATION

%J Number: E0P 35 ES-1.1 Rev.

4_

Titie: SI TERMINATION Prepared By: H.

K. COVIN B.

REVIEW I have reviewed the above procedure and have found it to be satisfactory.

TITLE SIGNATURE DATE DEPARTMENT HEAD W

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C.

SPECIFIC UNREVIEWED SAFETY QUESTION EVALUATION REQUIRED:

Modifies intent of procedure and changes operation of systems as described in design documents.

YES [ ]

NO((

(If yes, perform written USQ determination and Safety Evaluation, and contact Manager, Safety Analysis Branch to i

determine need for Integrated Safety Evaluation. )

ENVIRONMENTAL REVIEW REQUIRED O

(Adverse environmental impact)

YES [ ]

NO [g D.

SPECIFIC SAFETY EVALUATION REQUIRED I

Affects response of safety systems, performance of systems which may have been credited in.the safety analysis or non-credited systems which may indirectly affect safety system response.

YES [ ]

NO ((

j (If yes, perform written Safety Evaluation and contact Manager, Safety Analysis Branch to determine 7

need.for Integrated Safety Evaluation.)

j E.

INTEGRATED SAFETY EVALUATION REQUIRED Yr.S [ ]

NO ((

F.

PROCEDURE REQUIRES RMSORCREV1EW f

(In addition to rev'iew, itepe-with a YES response must be documented in the 50RC meeting minutes.)

YES I NO [ ]

G.

PORC SORC APPROVAL SORC Meeting Number J-8[-/d3 H.

APPROVAL AND IMPLEMENTATION The attached procedure is hereby approved, and effective on the date below:

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w rr Station / Service / Unit Superintendent Effective Date O

SF301/9/s/SES/87-12/lofl 8810260233 801007

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PDR ADOCK 05000213 P

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i E0P 35 ES-1.1 tage 1 4

Rev. 4 1

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SI TERMINATION tt i

Page No.

Eff. Rev.

1 - 13 4

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SI TERMINATION E0P 35 ES-1.1 Page 2 Rev. 4 (JI A.

PURPOSE This procedure provides the necessary instructions to terminate safety injection and stabilize plant conditions.

B.

ENTRY CONDITIONS This procedure was written for Modes 1, 2, and 3 assuming RHR is not in service.

Using this procedure when not in these modes requires a step by step evaluati,n to determine if the required action is still applicable to current plant conditions.

This procedure is entered from 1)

E0P 35 E-0, REACTOR TRIP OR SAFETY INJECTION, Step 27, when specified termination criteria are satisfied.

2)

E0P 35 E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 7 when specified termination criteria are satisfied.

3)

E0P 35 FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, Step 30, after secondary heat sink has been reestablished and SI is terminated or specified termination criteria are satisfied.

O OP%682 344

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S1 TERMINATION EOP 35 ES-1.1 Page 3 Rev. 4

1635 psia depressurization stops.

(1905 psia for IF no SG is faulted or Adverse Containment) ctiteria for stopping SI pumps can NOT be satisf ted af ter f aulted SG depressurization stops, THEN go to E0P 35 ES-1.2, POST LOCA CDOLDOWN AND DEPRESSURIZATION, Step 1.

b.

Slop SI pumps and place

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in AllTO L

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SI IERMINATION E0P 35 ES-1.1 Page 5 Rev. 4 STEP ACTION / EXPECTED RESPONFE RESPONSE NOT OBTAINED 10 Stop RHR Pumps and Place in AUTO 11 Verify ECCS Flow Not Required a.

RCS subcooling based a.

Manually operate ECCS on core exit TCs pumps as necessary. Go

> 30'F (90*F for to E0P 35 E-1, LOSS Adverse Containment) 0F REACTOR OR SECONDARY COOLANT, Step 1.

b.

PZR level > 7% (50%

b.

Control charging flow for Adverse Containment) to maintain PZR level.

IF PZR level can NOT be maintained, THEN manually operate ECCS pumps as necessary.

Go to E0P 35 E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.

12 Check If Containment Spray Should Be Stopped a.

Quench Spray pumps -

a.

Go to Step 13 r~')s RUNNING

(

b.

Containment pressure b.

Continue with Step 13.

<13 psia.

WHEN containment pressure

<13 psia, THEN do Steps 12c and d.

c.

RESET CDA Signal, d.

STOP containment spray pumps and pl. ice in AUTO.

1) STOP Quench Spray pumps

2) STOP Containment Recirc pumps

3) CLOSE Chemical Addition Isolation valves.

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OfV44 9 3-44

SI TERMINATION E0P 35 ES-1.1 Page 6 Rev. 4

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4 NY STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 13 Chech If Letdown Can Be Established a.

PZR Level >17% (50% FOR a.

Continue with Step 14.

ADVERSE CONTAINMENT)

WHEN PZR level increases to >17% (50% FOR ADVERSE CONTAINMENT), THEN do Step 13b.

b.

Establish letdown b.

Establish excess letdown per OP 3304A, CHARGING AND LETDOWN 14 Check VCT Makeup Control System a.

Makeup set for greater a.

Adjust boric acid flow than RCS boron rate concentration b.

Mak?up set for b.

Adjust controls automatic control c.

BTRS - 0FF 15 Align Charging Pump Suction to VCT a.

OPEN VCT to charging isolations b.

CLOSE RWST to. charging isolation valves 16 Check if RCP Seal Return Flow sheuld be established a.

Check RPCCW flow a.

Go to Step 17.

available to seal water heat exchanger b.

Establish flow, open containment inner and outer RCP Seal isolation valves O

oPVba1 3 44

SI IERMINAIION E0P 35 ES-1.1 Page 7 Rev. 4 7-w.-

STEP ACTHM4/FXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE Low-low Tavg interlock must be bypassed before 553*F to maintain condenser steam dump operation if in use.

17 Establish SG Pressure IF condenser is NOT available, Control Mode THEN dump steam to atmosphere, a.

Set SG Pressure 1)

Manually CLOSE all controller - 0 output atmospheric dump valves 2)

Verify MSIV Bypass b.

Trans er Steam Dump to Valves - CLOSED with STEAM PRESSURE control mode zero output 3)

Reset MSI c.

Verify Steam Dump 4)

Set the Atmospheric Dump Interlock Selectors - ON valve controller to 1092 psig and select AUTO d.

Adjust SG Pressure control controller - 1002 psig,,if necessary 18 Check RCS Hot Leg Control steam dump and total

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Temperature - STABLE feed flow as necessary to x_,/

stabilize RCS temperature.

NOTE Do not use Aux Spray unless pressure cannot be controlled by turning off PZR heaters and maintaining level.

19 Control PZR Pressure by IF normal spray NOT operating PZR heaters available and letdown and normal spray as is in service, THEN use necessary to maintain auxiliary spray.

IF NOT, pressure stable THEN use one PZR PORV.

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Si TERMINATION E0P 35 ES-1.1 Page 8 Rev 4

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STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED l

CAUTION AFW pump suction should be shifted to the CST if DWST level decreases to <80,000 gal.

20 Check intact SG levels a.

Narrow range level a.

Maintain total feed

>4% (34% FOR ADVERSE flow >525 gpm until CONTAINMENT) narrow range level

>4% (34% FOR ADVERSE CONTAINMENT) in at least one SG.

b.

Control feed f1.ow b.

IF narrow range level to maintain narrow in any SG continues to range level between increase, THEN stop 4% (34% FOR ADVERSE feed flow to that SG.

CONTAINMENT) and 50%

21 Check RCP Cooling - NORMAL a.

RCP RPCCW Flow a.

Establish RPCCL system

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flow to RCPs IAW OP 3330A

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REACTOR PLANT COMPONENT COOLING WATER b.

Maintain Required RCP b.

Adjust as necessary Seal Injection Flow IAW OP 3304A CHARGING between 8 to 13 gpm AND LETDOWN 22 Verify all AC Busses -

a.

Try to restore offsite ENERGIZED by offsite power.

power b.

IF necessary. THEN manually load the following equip.nent on the ac emergency busses

1. Instrument Air Compressor.

2. PZR heaters.

3. Fuel building filter system.

4 If CDA not present evaluate need for Fuel Pool cooling pump c.

Energize MCC 32 3T and verify it is supplying

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SI TERMINATION E0P 35 ES-1.1 Page 9 Rev. 4 l

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STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OSTAINED CAUTION If Seal Cooling had previously been lost, the affected RCP(s) should not be STARTED prior to a status evaluation.

NOTE, RCPs should be run in order of priority (RCP 2,1 THEN 3 or 4) to provide normal PZR spray.

23 Check RCP Status - AT Try to start preferred RCPs LEAST ONE RUNNING a.

Establish conditions for starting an RCP per OP 3301D, REACTOR COOLANT PUMP OPERATION.

b.

Start one RCP.

IF a RCP 7

can NOT be started, THEN

(,)

refer to attachment A to verify natural circulation.

IF natural circulationN0f~ verified, THEN increase dumping steam from intact SGs.

24 Check if Source Range Detectors should be energized a.

Check intermediate a.

Continue with Step 25.

range flux WHEN flux <10E-10 amps,

<10E-10 amps THEN do Steps 24b and c.

Steps 24b and c.

b.

Verify source range b.

Manually energize source detectors - ENERGlZED range detectors.

c.

Transfer nuclear recorders to source range scale

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S1 TERMINATION E0P 35 ES-1.1 Page 10 Rev. 4

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STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 25 Check if diesel generators should be stopped a.

Verify AC emergency a.

Try to restore offsite busses - ENERGIZED power to AC emergency by Offsite power busses.

b.

RESET any LOP, SIS, OR CDA signal at MB2 c.

Stop any unloaded diesel generator and place in standby d.

RESET Station LOP at both Sequencer panels e.

RESET, then turn ON each Diesel Sequencer Automatic Tester toggle switch, f.

CLOSE Feeder Breakers to Emergency Generator Distribution

/N)

Panels 3EGS*PNL1A at 32-1T-3H

(,

and 3EGS*PNLIB at. 32-1U-3H.

26 Shut down unnecessary plant equipment a.

Place stetm plant in a shutdown lineup per AOP 3550, TURBINE /

GENERATOR TRIP b.

All but one condensate pump c.

All but one circ water pump per condenser d.

Moisture separator t

drain pumps c.

4th point heater drain pumps l

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S1 TERMINATION E0P 35 ES-1.1 Page 11 Rev. 4 I

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STEP ACTIONsEXPECTED RESPONSE RESPONSE N0T CBTAINED 27 Maintain plant conditions -

STABLE a.

PZR pressure b.

PZR level c.

RCS temperatures d.

Intact SG levels 28 Vere / ECCS flow not required a.

RCS subcooling based on a.

Manually operate ECCS l

core exit TCs >30'F pumps as necessary. Go (90'F FOR ADVERSE to E0P 35 E-1, LOSS OF CONTAINMENT)

REACTOR OR SECONDARY COOLANT, Step 1.

b.

PZR level >7% (50% FOR b.

Control charging flow to l

ADVERSE CONTAINMENT) maintain PZR level.

IF PZR level can NOT be maintained, THEN manually operate ECCS pumps as

[~

necessary.

Go to E0P 35 i.

E-1, LOSS OF REACTOR OR s

SECONDARY COOLANT, Step 1.

29 Resetting MSI signal a.

Verify the Atmospheric Dump a.

MANUALLY CLOSE the controllers - zero output atmospheric dump valve.

b.

Verify MSIV Bypass Valves -

CLOSED witt, zero output

signal, c.

RESET MSI.

d.

Set the Atmospheric Dump Controllers -

1125 psig in AUTO.

30 Reset Auto SI Block Monitor SI reinitiation a.

Verify all Reactor Trip criteria until Auto SI is signals - CLEAR.

reset.

b.

CLOSE, then OPEN Reactor Trip Breakers.

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n SI TERMINATION E0P 35 ES-1.1 Page 12 Rev. 4 I

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STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 31 Resetting of FW Isolation Signal.

a.

Verify TV Flow Control valves and Bypass v11ves -

CLOSED.

b.

Verify FW Isolation Valves - CLOSED c.

Verify SG Blowdown Sample Isolations -

CLOSED d.

RESET FWI at MB2 and MB5 d.

IF the Auto SI Block has by reset, EEN perform the following.

1) Momentarily pull Universal Logic Card A213 from both trains of the solid state protection system.

2) Reset FW Isolation.

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3) RESET and OPEN FW (m_l Isolation valves.

4) Replace Universal Logic Card A213 in both trains of the solid state protection system.

5) Go to step 31f.

e.

RESET and OPEN FW Isolation valves.

f.

RESET both trains SG dlowdown Isolation.

g.

RESET SG Blowdown Sample Isolation.

h.

IF desired, THEN establish main feedwater flow per OP 3321, FEEDWATER.

32 RESET the Safety Injection Recirc (Sik) memory by depressing both "SIR FESET" pushbuttons

/N t

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SI TERMINATION E0P 35 ES-1.1 Page 13 Rev. *

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7 ~N STEP ACTICH0 EXPECTED RESPONSE RESPONSE NOT OBTAINED 33 Review Tech Spec 4.4.6.2.2.d and determine which portions of SP 3601F.4, REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVE TEST are required to be performed.

34 Veri'y all AC busses -

IF offsite power cannot ENERGIZED BY OFFSITE POWER be restored THEN perform an RCS cooldown per E0P 35 CS-0.2, NATURAL CIRCULATION C00LDOWN, to establish the following conditions:

I a.

RCS temperature <400*F b.

.FCS preswure >700 psia c.

Accumulator isolation

-l valves - CPEN d.

Cooldewn rate <100"F/hr

,,_ _35 Go to.ppropriate plant procedure I( j

-FINAL-i O P'Xd4 1 3 44

e SI TERMINATION E0P 35 ES-1.1 Page 1 of 1 Rev. 4 f3 U

1 SI TERMINATION ATTACIIMENT A The following conditions support or indicate natural circulation flow 1.

RCS subcooling based on core exit TCs - >30*F (90*F l

FOR ADVERSE CONTAINMENT) i 2.

SG pressures - STABLE OR DECREASING 3.

RCS hot leg temperatures - STABLE OR DECREASING 4.

CORE exit TCs - STABLE OR DECREASING 5.

RCS cold leg temperatures - AT SATURATION TEMPERATURE FOR SG PRESSURE

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