ML18087A740

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Rev 5 to Safety Injection Initiation
ML18087A740
Person / Time
Site: Salem  PSEG icon.png
Issue date: 03/13/1983
From:
Public Service Enterprise Group
To:
Shared Package
ML18087A720 List:
References
EI-I-4.0, NUDOCS 8303160594
Download: ML18087A740 (15)
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Text

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SALEM GENERATING STATION OPERATIONS DEPARTMENT DOCUMENT APPROVAL COVER SHEET SAFETY INJECTION INITIATION 1

EI I-4.0

'No.: ________ _

Unit:

5 Rev.:

t Remarks:

14 oaoes of text, last OTSC-None

__.....;;; __.....,."'"""'" ___...... ___......,-....;. ____________________ --t Chanoed steps: 4.10, 5.1 thru 5.4, and the Matrix Safety Related Review (Ref, AD-13) :

S/R yes X

Author's Checklist Comp~eted:

SORC

.General Manager

/

  • required for SPM documents only

+ required for EOP validation acceptance

      • required for safety *related documents protection document*S 8303160594 830314

\\

PDR ADOCK 05000272

.yes __ x __ _

only and fire no __ -__

--i Date 1*1 :?~~3 Date J f:g Date

/

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/*

Date

/

S PDR Salem Unit 1/2 AD-1-B-l MASTER

1.0 PURPOSE EMERGENCY INSTRUCTION I-4.0 SAFETY INJECTION INITIATION 1.1 This instruction is provided to present the immediate automatic and manual actions required to be performed on the receipt of any Safety Injection Actuation, whether automatically or manually initiated.

1.2 This instruction contains the information required to direct the operator to the appropriate Emergency Instruction to cope with the existing plant conditions.

2.0 INITIAL CONDITIONS 2.1 Safety Injection has been initia~ed,. either automatically or manually.

3.0 IMMEDIATE ACTIONS 3.1 Verify the following automatic actions have occurred.

3.1.1 REACTOR TRIP by verifying all control rods are fully inserted by checking the individual rod position indications and _rod bottom lights.

a.

If any control rods do not indicate full insertion, initiate a manual reactor trip.

NOTE The Rod Position indications & Rod Bottom lights may be erroneous due to an adverse containment-environment.

3.1.2 ACCIDENT LOADING OF the SAFEGUARDS. EQUIPMENT has taken place and the following equipment is running by observing the indicating lights on the status panel on 1RP4 or by observing the control bezels for each of the following:

a.

Centrifugal Charging Pumps

b.

Safety Injection Pumps

c.

Residual Heat Removal Pumps

d.

Auxiliary Feedwater Pumps (Motor Driven)

e.

Service Water Pumps

f.

Containment Fan Coil Units in slow speed.

g.

Diesel Generators Salem Unit 1 1

Rev. 5 I

~-

  • .~~. --... -~....,. ... '*--*,, **-.

I-4.0 3.1.3 REACTOR COOLANT TEMPERATURE is decreasing to or being maintained at 547°F by either steam dump or atmosphere steam relief.

3.1.4 TURBINE TRIP by verifying unit trip light on the EH console and turbine speed decreasing.

a. If the turbine does not indicate a tripped condition, initiate a manual trip from the control console.

3.1.5 MAIN FEED PUMPS tripped by observing the indications on the Control Bezel.

a.

If either pump does not indicate a tripped condition, initiate a manual trip from the

.control console.

3.1.6 FEEDWATER ISOLATION by observing the indicating lights on the Feedwater section of !RP4.

3.2 Verify Safety Injection Pump flow to the Cold Legs from the operating Safety Injection Pump(s) by observing the discharge flow meters on the control console.

3.3 When RCS pressure decreases to less than 1500 psig as read on the Wide Range Indicators on the control console, perform the following:

3.3.1 STOP all Reactor Coolant Pumps.

3.3.2 CLOSE 1CV139,1CV140 The Charging Pump Recirc Stop Valves.

NOTE Monitor RCS pressure throughout this procedure.

If RCS pressure should drop below the setpoirtt complete the actions required by 3.3.1 and 3.3.2.

3.4 Verify CONTAINMENT PHASE A ISOLATION has taken place by observing the indicating lights on the Status Panel 1RP4.

3.5 Announce over the Station PA System twice:

UNIT 1 REACTOR TRIP, SAFETY INJECTION.

Salem Unit 1 2

R 5 I ev.

4.0 SUBSEQUENT ACTIONS 4.1 If a C02 actuation occurs during Diesel Generator operation, perform the following:

4.1.1 Immediately STOP the affected diesel to prevent overheating of the generator.

  • 4.1.2 Refer to the immediate action statement of the annunciator alarm response for location A-29 "FIRE PROTECTION C02 DISCHARGE" CAUTION I-4.0 COMMENTS DO NOT REINITIATE Safety Injection 4.1.3 If restarting the diesel is necessary to supply minimum safeguards, then, MANUALLY START and LOAD the diesel.

4.2 Verify Safety Injection is in progress by checking each of the following.

If any equipment or valve is not in the desired condition or position attempt to establish the desired condition at the individual bezel on the control console.

4.2.1 Verify, utilizing console and/or 1RP4 status panel indications, that the loads listed on Table 1 have been loaded onto the vital buss'es.

Salem Unit 1 3

DO NOT ATTEMPT TO reset the Safety Injection or SEC in order to place equipment in desired condition.

System design is such that sufficient redundancy is provided to overcome single failures.

I Rev. 5

J 4.2.2 Verify Safety Injection flow to the Cold Legs through the Boron Injection Tank by observing Charging Pump Discharge Flow on the Safety Injection Bezel.

4.2.3 Check that the following valves have opened by observing the Status Panel on 1RP4.

If any valve fails to open, attempt to manually open from the Control Console.

lSJl Charging Pump Suction from RWST 1SJ2 Charging Pump Suction from RWST 4.2.4 Check that the following valves have closed by observing the Status Panel on 1RP4.

If any valve fails to close, attempt to close the valve from the' control console.

1SJ78 Recirc to Boric Acid Tank 1SJ79 Recirc to Boric Acid Tank 1SJ108 Recirc to Boron Injection Tank 1CV68 Charging System Isolation Valve 1CV69 Charging System Isolation Valve 1CV40 Volume Control Tank Discharge Valve 1CV41 Volume Control Tank Discharge Valve 1CV3 Orifice Isolation Valve (Letdown) 1CV4 Orifice Isolation Valve (Letdown) lCVS Orifice Isolation Valve (Letdown) 1CV7 CVCS Letdown Line 1CV116 Reactor Coolant Pump Seal Water Discharge 1CV284 Reactor Coolant Pump Seal Water Discharge Salem Unit 1 4

I-4.0 If no flow is indicated, check open 1SJ4, lSJS, 1SJ12, 1SJ13 1CV40 & 1CV41 will not close unless lSJl or 1SJ2 is full open.

Rev. 5 I

11SW20 Turbine Generator Area Supply Valve 13SW20 Turbine Generator Area Supply Valve 1SW26

4.3.1 If flow has not been established, proceed as follows:

Salem Unit 1

a. Gheck the discharge pressure on the Motor Driven Auxiliary Feedwater Pumps (11,12) which are running.

It should indicate greater than 1350psi.

b. If pressure is low(less than 1350psi) depress the PRESS OVERRIDE pushbutton.on the console bezel for each Auxiliary Feedwater Pump.
c. If pressure is greater than 1350psi check the valve demand set at approximately 95% for 11-14 AF21 on the console bezel.
Also, depress the PRESS OVERRIDE

. pushbutton on the console bezel for each Auxiliary Feedwater Pump.

5 I-4.0 This will remove the pump runout protection interlock on the AF21 valves and allow them to open to their preset demand regardless of discharge pressure.

Rev. 5 I

d. Start, if not already running, No. 13 Auxiliary Feedwater Pump and verify open 11-14 AFll.

4.4 Verify that Phase "A" Containment Isolation has taken place by check~ng that the valves listed in Table II are closed by observing the Status Panel on 1RP4. Should a valve fail to close, attempt to close it from the control console.

4.5 Verify that Feedwater Isolation has taken place due to the Safety InjectiQn.

4.5.1 Check that the following valves have closed by observing the Status Panel on 1RP4.

If any valve has failed to close, attempt to close it from the control console.

11BF13 11BF19 11BF40 12BF13 12BF19 12BF40 13BF13 13BF19 13BF40 14BF13 14BF19 14BF40 Feedwater Inlet Stop Valve Feedwater Control Valve Feedwater Bypass Valve Feedwater Inlet Stop Valve Feedwater Control Valve Feedwater Bypass Valve Feedwater Inlet Stop Valve Feedwater Control Valve Feedwater Bypass Valve Feedwater Inlet Stop Valve Feedwater Control Valve Feedwater Bypass Valve 4.6 If the Reactor Coolant Pumps have been tripped, insure the Steam Dump Pressure Controller is set to 1005 PSIG and transfer the Steam Dump to Pressure Control.

Salem Unit 1 6

I-4.0 Tavg is not a reliable indication with no RCP's running.

Wide Range TH and TC are reliable for RCS temperature.

Rev. 5

4.7 Verify that the 4160V Group Busses have transferred from the No. 1 Auxiliary Power Transormer to No. 11 and No. 12 Station Power Transformers.

4.7.1 Check that the following 4160V Breakers have opened and acknowledge them on the appropriate control console bezel.

lBGGD lBFGD lAEGD lAHGD 4.7.2 Check that the following 4160V Breakers have closed and acknowledge them on the appropriate control console.

12GSD 12FSD llESD llHSD 4.8 If the RWST level is decreasing rapidly (greater than approximately 2 ft/min.), proceed directly to EI I-4.4, "Loss of Coolant."

Salem Unit 1 7

I-4.0 A large LOCA is the only accident which will cause the RWST to decrease rapidly.

Rev. 5 I

4.9 Verify the following fans have stopped by observing the indications as noted.

If any fans are still running, attempt to stop them manually.

No. 11 & 12 Iodine Removal, (Control Console)

No. 11, 12, 13, 14 Nozzle Support, (Control Console)

No. 11 & 12 Reactor Shield, (Control Console)

No. 11, 12,13, 14 Control Rod Drive (Control Console)

No. 11 & 12 RHR Pump Room Coolers, (1RP2)

No. 11 & 12 Charging Pump Room Coolers, (1RP2)

No. 11 & 12 Containment Spray Pump Room Coolers, (RP2) 4.10 Verify Control Area Air Conditioning has shifted to the ACCIDENT -

INSIDE AIR mode of operation and the following actions have occurred by observing the Status Panel on RP2. If any actions do not occur,

  • manually initiate them IAW II-17.3.2, "Control Room Ventilation Operation."

4.10.1 No. 11, 12, 13 Chillers are running.

4.10.2 No. 11 & 12 Chilled Water Pumps are running.

4.10.3 No. 11, 12, 13 Control Area Supply Fans are running.

4.10.4 No. 11 & 12 Emergency Control Area Supply Fans are running.

4.10.5 Battery Exhaust Fan has stopped.

Salem Unit 1 8

I-4.0 R

5 I ev.

4.10.6 Control Valves 1CH30 and 1CH151 close to isolate the Administration Building.

4.10.7 Control Area Dampers positioned as follows1 CAAl CLOSED CAA2 CLOSED CAA3 CLOSED CAA4 CLOSED CAA5 OPEN CAA14 -

CLOSED CAA17 OPEN CAAlB CAA19 CAA20 CAA31 CAA32 CAA33 5.0 IDENTIFICATION QF FOLLOW UP ACTIONS 5.1 Perform the following Notifications of the Reactor Trip/Safety Injection.

5.1.1 Notification of the Reactor Trip/SI to the following:

a. OPER;TIONS MANAGER and/or
b. OPERATING ENGINEER and
c. NRC and
d. other appropriate people IAW Emergency Plann Procedure EP-I-0.

5.1.2 Refer to Emergency Plan Procedure EP-I-0 Salem Unit 1 for the appropriate accident classification.

9 OPEN CLOSED CLOSED CLOSED CLOSED CLOSED I-4.0 R

5 I ev.

5. 2 Veri'fy the following are closed or isolated at their.individual control bezels.

5.2.1 Pressurizer Spray Valves (PS-1 & 3)

a.

If PSl or PS3 is open and will not close, Trip the Reactor Coolant Pump in the associated loop.

lPSl - Trip 11 RCP 1PS3 Trip 13 RCP 5.2.2 Pressurizer Power Operated Relief Valves (PRl & 2) 5.3 If RCS pressure has stabilized after the initial decrease which initiated Safety Injection and Containment Isolation, the problem may be in an area or system which has been subsequently isolated.

Investigate the following:

5.3.1 Auxiliary Building for:

a.

Increases in radiation

b.

Unexplained accumulations of water.

5.3.2 Pressurizer Auxiliary Spray Valve (1CV75).

Ensure it is closed.

5.4 Utilize the Matrix on the next page to determine which subsequent Emergency Instruction to follow.

Salem Unit 1 9.1 I-4.0 Utilize Redundant indications where available to ensure proper diagnosis.

Containment Pressure may spike due to adverse environment but should return to near actual pressure.

I Rev. 5

I-4.0

--~~~~~~~! SAFETY INJECTION INITIATED~!~--

RCS Press less than 1500 psi &

SI Flow or CCW Flow to RCP's Isolated Trip All RCP's Perform appropriate notifications and Refer to EP-I-0 CONT Rad Mon, Temp, Press, Humidity Sump Level INCREASING Go to EI.I-4. 4 Loss of Coolant Accident RCS Press is between 1500 psi &

2000 psi Perform appropriate notifications and Ref er to EP-I-0 LOW STEAM PRESS in one or more Steam Generators Go to EI I-4.6 Loss of Secondary Coolant RCS Press above 2000 psi and PZR Level above 22%

and*

Heat Sink Available(Note 1) and TH more than 50 F less than TSAT Perform appropriate notifications Refer to EP-,I-0, Go to EI I-4.2 Recovery From Safety Injection I

If RCS Press decreases by 200 psi or PZR Level decreases below 10%

or TH is within 50 F of TSAT REINITIATE SAFETY INJECTION

  • S/G Blowdown or Air Ejector RMS INCREASING with no increase in CONT Parameters Go to EI I-4.7 Steam Generator Tube Rupture Part II NOTE 1 Heat Sink exists if the following are present:
1.

Total Aux Feed flow to all S/G's is greater than 42E4 lb/hr or Level in at least one S/G is greater than 5% on 2/3 of the narrow* range indicators.

2.

Core exit T/C and Wide Range TH indicate stable or slowly decreasing temperatures.

Salem Unit 1 11 Rev. 5 I

I-4~0 TABLE I "BLACKOUT WITH SAFETY INJECTION" LOADING SEQUENCE lA DIESEL GENERATOR 240/480V Breaker 11 SI Pump 11 RHR Pump 15 SW Pump OR 16 SW Pump 11 Containment Fan (Low Speed) 11 Auxiliary Feed Pump 11 Auxiliary Building Exhaust Fan 11 Chiller lB DIESEL GENERATOR 240/480V Breaker 11 Charging Pump 12 RHR Pump 14 SW Pump OR 13 SW Pump 12 Containment Fan (Low Speed)

[4 Containment Fan (Low Speed) tl.2 Auxiliary Feed Pump

~2 Auxiliary Building Supply Vent Fan lC DIESEL GENERATOR 240/480V Breaker 12 Charging Pump 12 SI Pump 11 SW Pump OR 12 SW Pump I 13 Containment Fan (Low Speed) 15 Containment Fan (Low Speed)

Emergency Air Compressor 11 Auxiliary Building Supply Vent Fan 13 Auxiliarv i

I 11 SWGR Room Supply Fan

~2 Auxiliary Building Exhaust Fan*

Building Exhaust.

NOTE 1 NOTE 2 12 Chiller 12 SWGR Room Supply Fan Fan 13 Chiller 13 SWGR Room Supply This sequence is initiated on any Safety InJection Actuation with or without.a Blackout, only in a blackout condition will the Diesel Generator Breakers close after first stripping the bus and the loads will then be sequenced onto the bus.

This sequence is also initiated with a Safety Injection coincident with undervoltage on one 4kV Vital Bus.

Only the lead Service Water Pump will start, however, if the lead pump fails to start the backup pump breaker will close.

Salem Unit 1 12 Rev. 5 /

1.

TABLE II PHASE "A" ISOLATION Waste Disposal System 1WL12 1WL13.

1WL16 1WL17 1WL96 1WL97 1WL98 1WL99 1WL108 RCDT Pump Discharge RCDT Pump Discharge Containment Sump Pump Discharge Containment Sump Pump Discharge Gas Analyzer From RCDT Gas Analyzer From RCDT RCDT Vent RCDT Vent N2 Supply to RCDT

2.

Sampling System 1SS27 Accumulator Sample 1SS33 Hot Leg Sample 1SS49 Sample from PZR Water Space 1SS64 Sample from PZR Steam Space 1SS103 Accumulator Sample 1SS104 Hot Leg Sample 1SS107 Sample from PZR Water Space lSSllO Sample from PZR Steam Space 11SS94 Sample from No. 11 Stm Gen Blowdown 12SS94 Sample from No. 12 Stm Gen Blowdown 13SS94 Sample from No. 13 Stm Gen Blowdown 14SS94 Sample from No. 14 Stm Gen Blowdown

3.

Component Cooling I-4.0 1CC113 Excess Letdown Heat Exchanger Cooling Water Outlet iCC215 Excess Letdown Heat Exchanger Cooling Water Inlet

4.

Steam Generator Drains and Blowdown 11GB4 Steam Gen Outlet No. 11 12GB4. Steam Gen Outlet No. 12 13GB4 Steam Gen Outlet No. 13 14GB4 Steam Gen Outlet No. 14

5.

Pressurizer Relief Tank 1WR80 1PR17 1PR18 1NT25 Salem Unit 1 Primary Water Supply to PRT Gas Analyzer From PRT Gas Analyzer From PRT N2 Supply to PRT 13 Rev. 5 I

    • .-..,... -.. *.--.,~-.--~----.,,,,......... -,-*-*.... *.. ** -* *-*............ -=-**-**-***..,.-..... _..... -*-** - - --**. **_....*-.;--_*_*-._... _. _. __.____._*, _... _. --*
c. *-**:

-~-* **....... ~.<-

--'-~.* : ___,.* '.*.:*....!..*...

6.

Accumulators 1NT32 Accumulator N2 Supply

7.

Containment Ventilation lVCl 1VC2 1VC3 1VC4 lVCS 1VC6 1VC7 1VC8 lVCll 1VC12 Purge Supply Purge Supply Purge Exhaust Purge Exhaust Cont Press Vac Relief Cont Press Vac Relief Containment Radiation Containment Radiation Containment Radiation Containment Radiation Isolation Valve Isolation Valve Sample.outlet Sample Outlet Sample Inlet Sample Inlet

8.

Demineralized Water 1DR29 DM Water to Flushing Connections

9.

Fire Protection 10 1FP147 Fire Protection Water Supply Safety Injection 1SJ123 Accum Test Stop Valve 1SJ60 Accum Disch Test Stop 1SJ53 SJ HDR Test Stop Valve

11.

Control Air 11CA330 A HDR Isolation Valve 12CA330 B HDR Isolation Valve I-4.0

12.

Containment Ventilation -

The following sample valves receive no automatic isolation signal, however, they should. be verified closed.

1VC9

  • lVClO 1VC13 1VC14 Containment Radiation Sample Outlet Backup Containment Radiation Sample Outlet Backup Containment Radiation Sample Inlet Backup Containment Radiation Sample Inlet Backup Salem Unit 1 14 I

Rev. 5

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