ML20009D193

Transient W/Failure to Scram Emergency Procedure

ML20009D193
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	07/17/1981
From:	LONG ISLAND LIGHTING CO.
To:
Shared Package
ML20009D181	List: ML20009D180 ML20009D183 ML20009D184 ML20009D185 ML20009D188 ML20009D189 ML20009D192 ML20009D193 ML20009D194
References
29.024.01-DRFT, NUDOCS 8107230269
Download: ML20009D193 (5)

Text

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Submittcd:

SP Number 29.024.01 (Section tiead)

Approved:

Revision: C (Plant Manager)

Date Eff:

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TRANSIENT WITH FAILURE TO SCRAM Y[id.ic

,g E' 'n.7.l i/_. :: 1 EMERGENCY PROCEDURE j

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1.0 SYMPTOMS 1.1 A valid scram signal due to a reactor transient is alarmed or indicated and all control rods do not insert as indie.ated on the full core display, rod position printout on the computer, or four rod display.

1.2 Reactor pressure and/or neutron flux indication increases abruptly and may go off-scale on recorders and meters.

1.3 Safety relief valves may lift.

2.0 AUTOMATIC ACTIONS 2.1 -

1115 prig reactor vessel pressure and above actuates various safety relief valves.

2.2 1120 reactor vessel pressure TRIPS the reactor recirculation' pumps.

3.0 IMMEDIATE OPERATOR ACTIONS 3.1 Manually scram reactor.

-3.1.1 Arm and depress manual scram pushbutton.

3.1.2 Place the mode switch in refuel.

3.1. 3 - Verify all rods are inserted.

l 3.2

.If.the reactor scrams, all rods insert, and power is decaying, refer to SP 29.010.01, Energency Shutdown, and do not continue this procedure.

3.3 Trip the recirculation pumps.

3.4 Commence suppression pool cooling per SP 23.121.01, residuai heat removal (RHR) system.

4.0 SUBSEQUENT OPERATOR ACTION 4.1 Determine if reactor power is 6% or greater.

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4.1.1-If rstetor powar is 6% or graster, continue this procedu.re at Step 4.2.

4.1.2-If reactor power is less than 6%, continue this procedure at Step 4.4.

4.2

' Start either A or B standby liquid control pump and inject the entire contents of the tank. Verify isolation / isolate RWCU.

4.3'. Terminate all injection into the RPV with the exception of CRD and RCIC or HPCI at a flow rate of approximately (Later) 4.4.

The following attempts to scram the reactor are to be performed concurrently if manpower is available.

4.4.1 Confirm'all scram valves are open by observation of scram valve position lights. If not, perform the following.

4.4.1.1 DE-ENERGIZE RPS Subchannel Logic by opening breakers on panel IC71*PNL-991, CB2A, 2B, 7A, and 7B in the Relay Room.

4.4.1.2 Vent air frma the scram' air system by closing valve C11-92V-9794 an0 opening vent valve downstream of C11-Olv-7104.

4.4.1.3 Restore when all scram valves are open.

4.4.2:

Bypass the scram discharge volume high level scram switches, reset-the RPS trip and verify the vent and drain valves open.-

4.4.2.1 Alternately RESET the Reactor Protective System and SCRAM the reactor until all rods are fally inserted.

4.4. 3 ' Bypass-the scram discharge volume (SDV) high level scram i

switches, reset the RPS trip and varify the vent and drain valves open.

4.4.3.1-INDIVIDUALLY SCRAM Control Rods at.'.ocal l

Hydraulic Control Units (HCU's) by placing both NORM-TEST-S.R.I. switches to the TE!.T position.__

4.4.4 Insert those rods not fully inserted with the reactor manual control system as the Rod Sequence Control System L

(RSCS) permits.

4.5 SAMPLE reactor coolant frequently to verify boron concentration H

above the. level determined to maintain the plant shutdown.

SP29 924 01 Rev. C

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-4.6 Af tsr tha racetor is shutdown to the leval where the cnly source of power is decay heat, PROCEED to stabilize Plant Condition in Hot Shutdown as follows:

CAUTION Do not shutdown SBLC Injection once it has been started until the SBLC Solution Tank is verified to be empty.

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4.7 PERFORM either-steps 4.7.1, 4.7.2 or 4.7.3.

4.7.1

- Maintain Reactor pressure between 800 and 1000 psig by use of Main Condenser Bypass Valves.

CAUTION Consult wj rh the Nuclear Engineer to confirm that boron concentration in the reactor will be sufficient to i

maintain the reactor shutdown after accounting for a normal startup of the Steam Condensing Mode of RHR.

-4.7.2.

Maintain reactor pressure betwe n 800 and 1000 psig by use of the RER steam condensing in accordance with SP 23.121.01, Residual Heat Removal (Rhl) System.

4.7.3 Maintain. reactor: pressure between 900 and 1000 psig bv opening safety relief valves and' utilizing Suppression

~ Pool Cooling to limit Suppression Pool temperature.

4.8 When the reactor is to be placed in COLD SHUTDOWN, PROCEED using I

the following considerations:

4.8.1 Confirm by sample results and consultations with the

- Nuclear Engineer that sufficient negative-reactivity has l

been inserted into the reactor to account for the l

positive reactivity effects of temperature decrease and dilution.

4.8.2 Start the reactor recire pumps in slow speed.

4.8.3-If the main condensor is available, Shutdown and Cooldown

.in accordance with SP 22.995 91, Shutdown to Cold l

Shutdown.

SP29 924.01 Rev. C

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CAUTION Insure the unborated water in the RHR Shutdown Cooling lines does r.ot temporarily dilute the boron in the core and allow inadvertent criticality.

CAUTION The'RHR pump minimum flow valve must be overridden in the closed position to prevent the loss of borate water when starting up Shutdown Cooling.

i 4.9 When reactor pressure has decreased to 135 psig. Startup RHR Shutdown Cooling in accordance with SP 23.121.01,. Residual Heat Removal (RRR) System.

4.10 If flooding the reactor veteel up to the steam dome is necessary.

use a source of water borated to at least the same concentration as the water in the reactor. The SBLC Solution Tank can be used.

-4.11 ' Maintain boron concentration in the vessel between 750 and 1000 PPM.

5.0 - FINAL PLANT CONDITIONS

'5.1 The plant is in cold shutdown conditions.

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5.2 Reactor level being maintained between 33.5" and 42.75" L

Watch Engineer Review (Watch Engineer) 6.0 DISCUSSION An ATWS is extremely unlikely but will require prompt operator action to mitigate the consequences. Operator concerns are as follows:

6.1 Verify Recirc. pumps trip.

6.2 Shutdown the reactor.

- 6. 3 Limit reactor pressure.

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~6.4

-Maintain the core covered.

I 6.5 Limit Suppression Pool temperature.

6.6~

Place' plant in Cold Shutdown.

SP29.024.01 Rev. C

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Th2 cperator must cttsmpt to scran tha racetor with tha most readily available means.' If the reactor cannot be maintained suberitical with Control Rods and reactor level fal".s below +12.5" or Suppression Pool temperature can't be maintained below 110*F, SBLC must be initiated to minimize ~ containment heat-up.

Suppression Pool Cooling should be initiated as soon as possible to ensure suppression pool temperature limits are not exceeded.

A Cooldown must' not be initiated until control rods are inserted or Boron concentration is satisfactory to prevent a restart of the reactor.

'Once. Boron injection is started, it must be run to completion.

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SP29.024.01 Rev. C l

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