ML18081B212

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Emergency Instruction I-4.3,Revision 5, Reactor Trip
ML18081B212
Person / Time
Site: Salem PSEG icon.png
Issue date: 03/10/1980
From: Bailey J, Connor C
Public Service Enterprise Group
To:
Shared Package
ML18081B211 List:
References
I-4.3, NUDOCS 8003190498
Download: ML18081B212 (8)
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Text

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EMERGENCY INSTRUCTION I-4.3 REACTOR TRIP I-4.3

/

1.0 PURPOSE 1.. 1 A reactor trip is initiated automatically by the Reactor Protection System if unsafe operating conditions are approached.

It may also be *Rltia':ed.'81anuailly from the control console.

This instruction provides the actions requcired to e~suTe tne reactor is in a safe shutdown condition.

1. 2 In addition to de-energizing the shutdown and control rod drive mechanisms, a reactor trip signal will intiate a turbine trip and, in con1unction with a low T (554°F) avg initiate a feedwater isolation signal.

This ins':ruction delineates the actions required to ensure both of these have occurred.

2.0 INITIAL CONDITIONS 2.1 Any of the following conditions will lead to a reactor trip and to an autoDatic plant shutdown.

The condition causing the trip will be back lighted in red on the first out overhead annunciator panel (Section F).

REACTOR TRIP

1. Manual
2. Pwr. Range, High Neutron Flux
3. Pwr. Range, High Flux Rate Trip
4. Intermediate Range, High Neutron Flux
5. Source Range, High Neutron Flux
6. overtemperature 6T
7. overpower 6T
8. Low Reactor Coolant Pressure
9. High Reactor Coolant Pressure
10.

High Pressurizer

11. Low Reactor Coolant Flow
12. Reactor Coolant Pump Under Voltage
13. Reactor Coolant Pump Under Frequency Salem Unit l/Unit 2 SETPOINT None Low Sepoint 25% of rated thermal pwr.

High Setpoint -

109% of Hated thermal pwr *.

+ 5% of rated thermal pwr. in 2 sec.

Current equivalent to 25% of full pwr.

5 10 counts per sec.

Variable Setpoint Variable Setpoint 1*865 psig 2385 psig 92% Level 90% of Normal Flow 75% of Normal Voltage with a 0.2 sec. time delay 56.5 Hertz with a 0.1 second time delay COINCIDENCE 1/2 2/4 2/4 2/4 1/2 1/2 2/4 2/4 2/4 2/4 2/3 2/3/Loop 1/2 Taken Twice 1/2 Taken Twice None P-10 None None P-10 P-6 Interlocked with P-10 None None P-7 None P-7 P-7 & P-8 P-7 P-7 Rev. 5

REACTOR TRIP

14. Reactor Coolant Pump Breaker Open
15. Low Feedwater Flow

=16. Low-Low Stea~

Generator Wtr. Lvl.

17. Turbine-Generator Trip
18. Safety Injection (Actuation)
19. General Alarm SETPOINT 10% Pwr. 2 Bkr. Open 36% Pwr. 1 Bkr. Open 1.4 X 106 Stm. Flow greater than feedwater flow & 25% S/G level 11% Level per S/G 45 psig Auto Stop Oil Pressure or all four Stop Valves closed
l. Manual
2.

Pressurizer at 1765 psig

3.

Containment at 4.7 psig

4.

Any one S/G 100 psig lower than 'any other two S/G's

5.

Variable5 S~eam line flow 1.4 X 10

  • /hr. 0-20% Goad increasing to 4.0 X 10
  1. /hr.

at 100% pwr. in coincidence with Low TAVG 543°F or low Stm. Press. 500 psig.

Logic Train "A" & Train "B" in test simultaneously.

NOTE The General Alarm trip is not alarmed on the first out annunciator.

20. Trip Bypass Bkrs.

Racking in, or attempting to rack in, both Reactor Trip Bypass Bkrs.

at the same time.

NOTE COINCIDENCE l/Pump 1/2 Flow Mismatch, in coincidence with 1/2 low wtr level, per loop.

2/3 per S/G 2/3 4/4 1/2 2/3 I-4.3 INTERLOCK P-7 & P-8 None None P-7 None None 2/3 High Con-None tainment pressure 1/2 Stearn Pressure None on any S/G lower than 1/2 Steam Pres-sures on 2/3 of the other loops.

1/2 High Steam flow None 2/4 Steam Gen. in coincidence with 2/4 LOW TAVG or 2/4 low steam line pressure.

The Bypass Breaker trip is not alarmed on the first out annunciator 3.0 IMMEDIATE ACTIONS 3.1 Automatic 3.1.1 Reactor Trip 3.1.2 Turbine Trip 3.1. 3 Generator Trip Salem Unit l/Unit 2 Rev. 5

L I-4.3

.3. 2 Manual

=

3.2.1 If an automatic reactor trip has not occurred, proceed as follows until the reactor is successfully tripped:

1)

Initiate a manual reactor trip with either handle on the control console.

2)

Open the Reactor Trip Breakers manually from the control console by depressing open pushbuttons on both Reactor Trip Breaker A & B bezels.

3)

Manually initiate Safety Injection by inserting the Safeguard Key into either Train A or B Safety Injection Operate Bezel and turn the key.

4)

Manually trip both Reactor Trip Breakers locally at their cubicle in the 84 Ft. elevation switchgear room.

5)

Manually trip both Control Rod MG sets at their control panels in the 84 Ft.

elevation switchgear room.

3.2.2 If an automatic reactor trip has occurred, proceed as follows:

1)

Check that all full length rods are fully inserted by checking individual rod position indicators and rod bottom lights.

2)

If any full length control rod does not indicate fully inserted, manually initiate a reactor trip.

3)

If all full length control rods are not then fully inserted, RAPID BORATE by 150 ppm (approximately 8 minutes) for each rod not inserted IAW OI II-3.3.8, "Rapid Boration".

3.2.3 Verify Turbine trip by checking the following:

1)

UNIT TRIP light on E/H console illuminated.

2)

Turbine Stop Valves, Governor Valves, Interceptor Valves and Reheat Stop Valves closed.

3)

Turbine speed decreasing.

If the turbine has not tripped, proceed as follows until steam flow from the Steam Generators is terminated.

4)

Initiate a manual turbine trip with the handle on the console.

5}

Manually open the Generator Output Breakers, 1-5 & 5-6 (1-9 & 910).

6}

Trip closed the Main Steam Isolation Valves, ll-14(21-24)MS167 from either the Safeguard bezels or Main SP:~if b0~~f.\\1\\*~\\, '. l(:\\

\\'.'!

Salem Unit l/Unit 2

~'0JTI, ~\\\\~ \\lJiuuilJ~",\\ U U""u\\J l>l.IU\\Jlb. U

.. Rev. 5

I-4.3 If the uncontrolled steam flow has caused Reactor Coolant System pressure to decrease to <1765*, insure Safety Injection is actuated.

If Safety Injection is not actuated, initiate it manually by inserting the Safeguards Key into either Train A or B Safety Injection Operate bezel and turn the key.

Proceed to EI I-

4. 0, "Safety Injection Initiation".

3.2.4 Verify that Tavg is decreasing toward or is being maintained at 547°F by either steam dump or atmospheric steam relief.

3.2.5 Verify that Feedwater Isolation takes place when Tavg decreases to 554°F.

3.2.6 Announce over the plant PA system twice:

UNIT NO. 1(2) REACTOR TRIP.

4.0 SUBSEQUENT ACTIONS 4.1 Verify the Generator Output Breakers, 1-5 & 5-6(1-9 & 9-10) are open.

If they do not open, open manually by depressing the OPEN pushbutton on the bezel for each breaker on the control console.

4.2 Check that nuclear power is decreasing by observing the nuclear instrumentation.

4.2.l Check that the Source Range High voltage is reinstated below 5 x lo-11 amps on both Inter-mediate Range Channels.

COMMENTS Utilize redundant indications where possible to confirm evaluations and actions.

4.1 Should open ~30 seconds after the turbine trip.

4.2.l Should occur in ~15-18 minutes following the trip.

l)

If the Source Range high voltage does not energize automatically, manually depress the RESET SOURCE RANGE "A" and RESET SOURCE RANGE "B" pushbuttons on the control console.

4.2.2 Switch the Nuclear Power Recorder (NR-45) to read one Intermediate Range channel and one Source Range Channel.

4.2.3 Notify the Performance Department that a reactor trip has occurred and that the compensating voltage on the Inter-mediate Range detectors should be ad-justed.

4.2.3 This should be accomplished as soon as practical to insure proper Intermediate Range indication.

  • 4.3 Verify that. the Pressurizer pressure and level mf.:f~ cW~~~nuMl~~~l as necessary.

are within limits, and under cof~tffi ~OOT@~Ui(JU~ U U JU*~ WJJ'\\Jts U Salem Unit l/Unit 2 Rev. 5

~-~ Verify that the 4160V Group Busses have trans-ferred from the No. 1(2) Auxiliary Power Trans-former to No. 11(21) & No. 12(22) Station Power Transformers.

4.4.1 Check that the following 4160V Breakers have opened appropriate 1 (2)

BGGD 1(2)

BFGD 1(2)

AEGD 1(2)

AHGD and acknowledge them on the control console bezel; 4.4.2 Check that the following 4160V Breakers have closed and acknowledge them on the appropriate control console bezel:

12(22) GSD 12(22) FSD 11(21) ESD 11(21) HSD 4.5 Verify that T is being maintained at avg at 547°F due to steam dump operation.

4.5.1 Ensure the Main Steam Pressure set-point is set to maintain Steam Generator press~re at 1\\,1005 psig, then transfer the Steam Dump con-trol to Main Steam Pressure control.

4.5.2 If Condenser steam dump is not avail-able, utilize the Atmospheric Steam Relief Valves, ll-14(21-24)MS10 to maintain Steam Generator pressure at 1\\,1005 psig.

4.6 Verify that Feedwater Isolation has taken place due I-4.3 4.4.1 Open manually as necessary.

4.4.2 Close manually as necessary.

4.5 Check Steam Dump Valve position indicating lights and the Stearn Dump demand indicator.

4.5.1 Check the setting first to prevent any unwanted Stearn Dump operation.

to the reactor trip in coincidence with low Tavg(554°F).

4.6.1 Check that the following valves have closed by observing their appropriate bezel indi-cation:

lll2l)BF19 Feedwater Control Valve 12 (22)BF19 Feedwater Control Valve W@~

13 (23)BF19 Feedwater Control Valve 14 (24) BF19 Feedwater Control Valve Salem Unit l/Unit 2 m~r.rmrrn1~ vu~*i LJ

  • \\Ji I

l i.J u

..:::/J' (Q~n~W J'J Rev. 5

e ll(2l)BF40 Feedwater Bypass Valve l2(22)BF40 Feedwater Bypass Valve l3(23)P.F40 Feedwater Bypass Valve l4(24)BF40 Feedwater Bypass Valve 4.7 Terminate any RCS dilution which is in progress.

= 4.7.l Depress the STOP pushubtton on the Makeup Mode Selector Bezel and align the-Blender for Auto makeup IAW OI II-3.3.6, "Boron Concentration Control".

4.7.2 Bypass the deborating demineralizers by aligning 1(2)CV27 to the VCT.

4.8 Return the levels in the Steam Generators to normal

(~33%) as follows:

  • CAUTION:

If the Level in any Steam Genera-tor has been <10% on the narrow range for more than 5 minutes and all feedwater flow has been isolated for more than 5 minutes, flow must be limited to < 1 x 10 5 lbm/hr.

to that Steam Generator until the level is returned to >10% in the narrow range.

4.8.1 Control flow to the Steam Generators as required by controlling the following valves:

1) ll-14(21-24)AF11 if No. 13(23)

Aux. Feedwater Pump is in operation.

2) ll-14(21-24)AF21 if No. 11 & 12 Aux. Feedwater Pumps are in operation.

4.9 Establish and maintain the Hot Standby condition 1AW OI I-3.5, "Minimum Load to Hot Standby", and OI 1-3.8, *Maintaining Hot Standby".

4.10 If Rx trip was from >15% Rx Power, have the Chem Dept. perform an I 131, I 133, I135 isotopic analysis between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following the Rx Trip.

Salem Unit l/Unit 2 I-4.3 4.7 Prevent any inadvertent re-duction in Shutdown Margin.

4.8 The feed ring drains slowly through the loose fit connection to the feed inlet piping.

If conditions require maximum flow for decay heat removal considerations, this takes precedence over the water hammer considerations.

4.10 Tech Spec 3.4.8 Table 4.4.

Rev. 5

4.11 Obtain a sample of the Reactor Coolant System and determine boron concentration.

Adjust boron concentration as required IAW OI II-3.3.6, "Boron Concentration Control".

4.12 As per Administrative Procedure No. 5:

-4.12.1 Notify the Station Operating Engineer or Chief Engineer of the reactor trip and; 4.12.2 Initiate an Operational Incident Report IAW AP-6 and forward it to the Station Operating Engineer.

4.13 If, at this tim~, it becomes necessary, take the plant to the Cold Shutdown Condition IAW OI I-3. 6, "Hot Standby to Cold Shutdown".

4.14 As authorized by AP-5, withdraw the Shutdown Banks as follows:

4.14.1 Reset the flux rate trip by momentarily taking the RATE MODE switches, on each NIS POWER RANGE A drawer, to the RESET position.

4.14.2 Depress the CLOSE pushbutton, on the control console, for REACTOR TRIP BKR A, verifying the breaker does close.

4.14.3 Depress the CLOSE pushbutton, on the control console, for REACTOR TRIP BKR B, verifying the breaker does close.

4.14.4 Depress the STARTUP pushbutton, on the control console, and verify each Shut-down and Control Rod Step Counter resets to zero.

Salem Unit l/Unit 2 I-4.3 4.13 If any of the automatic functions required (i.e. reactor trip, turbine trip, Auxiliary Feed-water initiation) have failed to actuate, it will be necessary to proceed to Cold Shutdown IAW Tech Spec 3.0.3.

4.14.1 Any reactor trip from power will generate a negative rate trip signal which seals in and must be manually reset.

4.14.4 If the STARTUP pushbutton has been pushed prior to closing the Reactor Trip Breakers, a Rod Urgent Alarm condition will be present.

This can be cleared by pushing either the STARTUP pushbutton or the ALARM RESET pushbutton.

Rev. 5

4.14.5 Commence withdrawing Shutdown Bank A, B, C and D, in that order, to their fully withdrawn position.

4.15 When the cause of the trip has been deter-mined and corrected, obtain the permission of the Station Operating Engineer or the Chief Engineer, IAW AP-5, to take the reactor critical.

4.16 With Steam Generator* levels within their normal operating bands and just prior to commencing the recovery startup, perform the following:

4.16.1 Place the Steam Generator Feedwater Controls in MANUAL and run the valve demand to zero.

4.16.2 Reset the Feedwater Isolation signal by depressing the Train "A" and Train "B" FEEDWATER ISOLATION RESET pushbuttons on the control console.

4.16.3 Maintain Steam Generator levels within their normal operating bands by manually controlling Feedwater Bypass Valves 11, 12, 13 and 14(21, 22, 23 and 24)BF40.

4.16.4 Return the Auxiliary Feedwater System to its normal at power lineup IAW OI III-10.3.1, "Auxiliary Feedwater System Operation".

4.17 Return to Power Operation IAW OI I-3.3, "Hot Standby to Minimum Load", and OI I-3.4, "Power Operation".

Prepared by~~~-J_a~y'---Ba.~1_*1_e~y""-~~~~~~~~

I-4.3 4.16.4 AFW Storage Tank level may be low.

Chris Connor Manager -

Salem Generating Station Reviewed by_*~~~~~~~~~~~~~~~~~~

SORC Meeting No. 80-17

~~~~~~~~~~~~~~~~-

Date __

.5::.,i.-h:....;;o-#,.{_,,~~---

Salem Unit l/Unit 2

-B-Rev. 5

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