ML17249A736

Emergency Procedure E-1.3,Rev 7,Loss of Secondary Coolant

ML17249A736
Person / Time
Site:	Ginna
Issue date:	12/03/1979
From:	Bodine J, Moon J ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17249A732	List: ML17249A731 ML17249A734 ML17249A735 ML17249A736
References
E-1.3, NUDOCS 8003060625
Download: ML17249A736 (25)

Text

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E-1.3 LOSS OF SECONDARY COOLAÃZ E-1.3:1

1.0 SYMPTOMS

2.0 Refer to Section 1.0 of E-l.l, if not already performed.

IMMEDIATE OPERA%)R ACTIONS:

2.1 Refer to Section 2.0 of E-l.l, if not already performed.

2.2 Verify the actuation of steamline isolation.

If not actuated, manually initiate steamline isolation on both S/G's.

3.0 SUBSEQUENT OPERATOR ACTIONS:

CAUTION:

The diesels should mt be operated at idle or minimum load for extended periods of time. If the diesels are shut down, they should be prepared for restart.

NI3ZE:

CAUTION:

The process variables referred to in this Instruction are typically monitored by more than one instrumentation channel.

The redundant channels should be checked for consistency while performing the steps of this Instruction.,

Eo not rely upon S/G or Pressurizer level irdication after any event &ere a high energy line break has occurred inside of containment.

An erroneous level indication will be caused by reference leg heatup and possible boiling as a result of increased CV temperature and/or changes in S/G or pressurizer pressures.

Basis for this is shown in Tables 1-4 and Figures 1-4 attached.

If S/G and pressurizer levels are maintained between 85% and 25%, this will ensure an actual water level is present.

NCTE:

The pressurizer water level indication should always be used in conjunction with other specified reactor coolant system indications to evaluate system conditions and to initiate manual operator actions.

3.1 If reactor ccolant pressure is above the RHR Pump shut-off head, manually reset safety injection after MOV 825A or 825B SI Pump suction frcm INST is open so that safeguards equipment can be controlled by manual action.

Ensure that containment isolation is maintained.

Stop the RHR Pumps and place in the standby mode.

CAUTION:

Whenever the wide range reactor coolant pressure decreases below the RHR shutoff head, the RHR pumps should be manually restarted to deliver fluid to the reactor coolant system.

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E-1.3:2 CAUTION:

Subsequent to this'Step, should loss of offsite power occur, manual safety injection initiation will be required to load the safeguards equipnent onto the diesel powered emergency busses.

3.2 Stop all reactor ccolant pumps after high head safety injection pump operation has been verified ard when the narrow range reactor coolant pressure is at 1715 psig.

CAUTION:

If the reactor coolant pumps are stopped, the seal injection flow should be maintained if possible.

NOZE:

The conditions given above for stopping reactor coolant pumps should be continuously monitored throughout this instruction.

3.3 Determine which steam generator is affected by observing the individual steamline pressures.

A low steamline pressure canpared to. the others

'enotes the faulted loop; terminate auxiliary feedwater to that steam generator ard close ard pull stop the turbine driven stean supply valve frcm that S/G.

MZE:

If no loop has a low steamline pressure canpared to the others ard all steamlines have been isolated, determine if a break has occurred in the steamline, in the main feedline or in any piping systen that connects with the secondary pressure bourdary.

If no indication of a break in the pressure boundary is found, go to Section 3.0 of E-l.l ard re-evaluate the accident with particular enphasis on the Zass of Reactor Coolant.

If a leak fran the secondary systems if found, continue to follow these instructions.

3.4 Regulate the auxiliary feedwater flow to the good steam generator to restore and/or maintain an indicated narrow range stean generator water level of 25%, sufficient to assure that the steam generator tubes are covered.

If water level increases in an unexplained manner in one steam generator, go to E-1.4, Steam Generator Tube Rupture.

NCTE Nonitor the primary water supply (Condensate Storage Tank) for the auxiliary feedwater pumps and upon reaching a low level, switch over to an alternate water supply source (per procedure

~lE).

3.5 R>nitor Refueling Water Storage Tank level 3.5.1 If containment spray has been actuated, and if the containment pressure is reduced to a value below 30 psig, the contairment spray actuation pressure, reset containment spray.

Spray pumps should be shut off and placed in the standby mcde with operable flow paths.

3.5.2 If a low Refueling Water Storage Tank level alarm is reached while the contairxnent spray punps are still running, stop 1 spray pump if 2 running.

Spray pumps should be realigned to the recirculation mcde per E-l.2.

The safety injection pumps should remain aligned to the Refuelirg Water Storage Tank.

If the Refueling Water Storage Tank low-low level alarm of 10$ is reached stop all operating SI, RHR and Spray Pumps, reset safety injection if not done previously.

Realign the safety injection pumps to the cold leg recirculation mcde and spray pumps to the recirc mode if needed using procedure E-1.2.

E-l.3:3 NOZE:

If the reactor coolant systen pressure is above the shutoff head of the high head safety injection pumps, do not attempt to start pumps in recirc mode unless RCS pressure drops below their shutoff head as the pumps have m recirc in the recirculation

mode, 3.6 IF NO2E:

The corditions given below for termination of safety injection should be continuously monitored throughout this instruction.

3.6.1 3.6.2 Any wide range reactor coolant temperature TC is less than 350'F, AND Wide range reactor coolant pressure is greater than 700 psig ard is stable or increasing AND 3.6.3 Pressurizer water level is greater than 25% of span and rising (heaters covered)

AND 3.6.4 The reactor coolant indicated subcooling is greater than 50'F per subcooling meters, NOZE:

As a backup to the subcooling meters, the average of thermocouples (points 11,15,18,19 6 20) may be used with pressurizer pressure and the attached saturation curve to verify 50'F subcooling.

-',;,'. 6. 5 Stop all safety injection pumps and place in the standby mode and maintain operable flow paths.

3.6.6 If wide range reactor coolant pressure decreases more than 200 psi or pressurizer water level decreases by 10% of span following termination of safety injection or the RCS subccoling is less than 50'F, MANUALLY REINITIATE safety injection pump operation to maintain reactor coolant pressure and pressurizer water level.

Go to Section 3.0 of E-l.l to reevaluate the event.

3.6.7 If all wide range reactor ccolant temperature TC indicators go above 350'F when attempting to satisfy the conditions of 3.6.1 thru 3.6.4, initiate safety injection gunp operation and continue operation until corditions of 3.7 are satisfied.

3.6.8 If steps 3.6.6 and 3.6.7 do rat apply go to step 3.10 3.7 IF 3.7.1 3.7.2 All wide range reactor temperature TC are greater than 350'F, AND Reactor coolant pressue is above the shutoff head of the safety injection

punps, AND

3. 7.3

~.3.7.4 3.7.4.1 Safety injection flow to the Reactor Coolant System is zero, THEN attempt to reestablish the reactor coolant pressure to greater than 2000 psig and pressurizer water level to greater than 50% of span by Resetting safety injection, and

E-1.3:4

,. 3.7.4.2 Establishing full charging flow.

CAUTION:

Ensure that water edition during this process does not result in dilution of the reactor coolant systen water.

3.8.1 IF All wide range coolant temperature TC are greater than 350'F, AND 3.8.2 Wide range reactor coolant pressure is greater than 2000 psig and is stable or increasing, AND 3.8.3 Water level in at least one steam generator is >

25% in the narrow range span AND 3.8.4 3.8.5 Pressurizer water level is greater than 50 percent of span, AND The reactor coolant irdicated subcool'ing is greater than 50'F per subcooling meters NOTE As a backup to the subcooling meters the average of thermocouples (points 11,15,18,19 a 20) may be used with pressurizer pressure ard,the attached saturation curve to verify 50'F subcooling.

THEN go to Step 3.9 Stop all safety injection pumps and place in the standby mode and maintain operable safety injection flowpaths.

CAUTION If wide range reactor coolant pressure drops below the safety injection actuation pressure 1715 psig span following termination of safety injection or RCS subccoling

< 50'F MANUALLXREINITIATE safety injection pump operation to maintain reactor coolant pressure to a ncminal value of 2000 psig and pressurizer water level to a ncminal value of 50 percent of span.

Go to Section 3.0 of E-l.l to reevaluate the event.

3.10 3.10.1 3.10.2 Reset containment isolation by performing the following:

Place CV Sump A pumps in gull-stop position Place all containment isolation (T signal) valve switched in the closed position and manually reset containment isolation by use of key switch.

(Refer to Autcmatic Actions in Section 4 of E-l.l for Containment Isolation Valve nunbers) 3.10.3 If outside power has been lost, close bus tie breaker 14 to 13 and/or 16 to 15 a+3 restart instrument Air Containment Ccmpressors as necessary.

3.10.4 Open the Instrument Air Contaimnent Isolation valve.

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E-l.3:4.1 NOTE:

U n loss of instrument air operation of the pressurizer PORV's using the RCS overpressurization Nitrogen system can be achieved if 1).

RCS pressure is > 435 psig and 2).

There is > 200 psig of Nitrogen available frcm overpressurization storage tanks (normally at aproximately 700 psig) are satisfied.

CAUTXON:

One operator will have to be on the back of the board turning

~ke switches as instructed below while another operator is watching pressure indication from the front of the control board.

To o n PCV 431C:

1).

Turn "PC 431 SV8619B" to Arm 2).

Turn "Surge TK V802B SV8616B" to open To o n PCV 430:

1).

Turn "PC430 SV8619A" to Arm.

2).

Turn "Surge TK V802A SV8616A" to open.

These steps will open respective PORV until 1 of the 2 valves in the train is closed.

Xf Nitrogen supply runs low, tanks can be refilled using procedure S29.2.

This will require reset of CV isolation.

E-l.3:5 If outside power is lost restore service water to the operatic ccmponent cooling water heat exchangers and Turbine Building.

Start one ccmponent coolie water pump ard restore HCC lC and 1D by resetting relays at the respective motor control centers.

3.10.6 Use the pressurizer PORV's for pressure control if necessary.

3.11 Re-establish normal makeup to maintain pressurizer level in the normal operating range ard to maintain system pressure; 3.11.1 at values reached Men safety injection was terminated at (TC < 350'F)

OR 3.11.2 to a ncminal value of 2000 psig (TC > 350 F).

CAUTI(N:

Ensure that water addition during this process does not result in dilution of the reactor coolant system boron concentration.

3.12 Reestablish operation of the pressurizer heaters (refer to o-8.1, "Restoration of pressurizer heaters to maintain natural circulation at HSD" if no RCP's are running) after verification of sufficient pressurizer level 50% to assure coverage of the pressurizer

heaters, an alternate means auld be to ccmpare pressurizer surge line, water space, ard vapor space temperatures.

When system pressure can be controlled by pressurizer

heaters, and containment temperatures are low enough to assure proper operation of control

systems, restore rmrmal pressurizer level control.

3.13 i~Unitor either the subcooling meters or the average temperature indication of core exit thermocouples (Points 11,15,18,19, 6 20) to verify that RCS temperature is at least 50'F less than saturation temperature at RCS indicated pressure per attached saturation curve.

3.14 If 50'F indicated subcoolirg is not present, then attempt to establish 50'F indicated subcooling by steam dump from the steam generator to the condenser or the atmosphere.

CAUTION:

If steam dump is necessary, reduce the steam generator pressure at least 200 psi below the lowest stean safety valve setpoint and maintain a reactor coolant cooldown rate of no more than 50'F/HR, consistent with plant make-up capability.

3.15 Stean dump should be initiated in the following manner to stabilize reactor coolant systen temperature:

3.15.1 Establish a flow path in at least one steamline in an intact loop (if possible)

IF the main condensor is available and IF an uncontrolled steam release is not reinitiated upon opening the MSIV.

Transfer the steam dump system to stean header pressure control.

Set the stean header pressure control setpoint to the pressure in the intact steam generator(s) at the tire safety injection was terminated.

E-1.3:6 OR IF all steamline stop valves are CIDSED and cannot be reooened, the main condenser is not available, or the rupture is downstream of the main steamline isolation valves, dump steam to the atmosphere fran the intact loop using the steam generator power operated relief valve.

Set steam generator power operated relief valve pressure control setpoint to the pressure in the intact steam generator at the time safety injection was terminated.

If 50'F indicated subcooling cannot be established or maintained, then manuall reinitiate safet in'ection.

Go to Section 3.0 of E-l.l to reevaluate the event.

When the reactor coolant temperature and pressure are stable, borate the reactor coolant system to cold shutdown conditions ard verify by sampling.

After offsite power is available if lost, establish the auxiliary systems necessary for a controlled cooldown to cold shut-down.

If offsite power is available and all reactor coolant pumps are stopped, restart at least one reactor coolant pump in the intact loop for cooldown purposes in accordance with procedures.

Maintain subcooled conditions in the reactor coolant system consistent with the normal cooldown curve.

If these subcooled conditions cannot be maintained, restart safety injection pumps.

NOZE:

If there is significant radioactivity in the intact steam generator's secondary side due to tube leaks and steam is being dumped to the atmosphere, begin cooldown ard depressurization of the reactor ccolant system to limit the release of radioactivity to the environs.

NOTE:

Safety injection pump operation should be reinitiated if an uncontrolled reactor coolant system depressurization or an uncontrolled drop in pressurizer water level occurs during the cooldown process.

These criteria apply in lieu of those given in Step 3.6.

After establishing cperation of auxiliary systems, initiate a controlled cooldown and depressurization to cold shutdown conditions using Normal Cooldown Procedures.

NOZE Safety Injection should be reinitiated if an uncontrolled reactor coolant system depressurization or an uncontrolled drop in pressurizer water level occurs during the ccoldown process.

These criteria apply in lieu of those given in 3.6.

During the controlled cooldown, the reactor coolant system pressure will decrease below 1715 psig.

Tripping the operating reactor coolant pump due to the pressure criteria of Step 3.2 is not required.

Other criteria of Step 3.2 are still applicable at this time.

Recovery procedures for the particular event must be developed and implemented to effect plant return to service.

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