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

I-4.3

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EMERGENCY INSTRUCTION I-4.3 REACTOR TRIP 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.

In addition to de-energizing the shutdown and control rod drive mechanisms, a reactor

1. 2 trip signal will intiate a turbine trip and, in con1unction

- with a low T avg (554°F) 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) .

SETPOINT COINCIDENCE REACTOR TRIP 1/2 None

1. Manual None Low Sepoint 25% of 2/4 P-10
2. Pwr. Range, High Neutron Flux rated thermal pwr.

High Setpoint - 109% of 2/4 None Hated thermal pwr *.

+ 5% of rated thermal 2/4 None

3. Pwr. Range, High Flux Rate Trip pwr. in 2 sec.

Current equivalent to 1/2 P-10

4. Intermediate Range, High Neutron Flux 25% of full pwr.

P-6 Interlocked

5. Source Range, High 10 5 counts per sec. 1/2 with P-10 Neutron Flux Variable Setpoint 2/4 None
6. overtemperature 6T Variable Setpoint 2/4 None
7. overpower 6T 2/4 P-7
8. Low Reactor 1*865 psig Coolant Pressure 2/4 None
9. High Reactor 2385 psig Coolant Pressure 2/3 P-7
10. High Pressurizer 92% Level 2/3/Loop P-7 & P-8
11. Low Reactor 90% of Normal Flow Coolant Flow 75% of Normal Voltage with a 1/2 Taken P-7
12. Reactor Coolant Pump Twice Under Voltage 0.2 sec. time delay 56.5 Hertz with a 0.1 second 1/2 Taken P-7
13. Reactor Coolant Pump Twice Under Frequency time delay Rev. 5 Salem Unit l/Unit 2

I-4.3 REACTOR TRIP SETPOINT COINCIDENCE INTERLOCK

14. Reactor Coolant Pump 10% Pwr. 2 Bkr. Open l/Pump P-7 & P-8 Breaker Open 36% Pwr. 1 Bkr. Open
15. Low Feedwater Flow 1.4 X 10 6 Stm. Flow greater than 1/2 Flow None feedwater flow & 25% S/G level Mismatch, in coincidence with 1/2 low wtr level, per loop.

=16. Low-Low Stea~ 11% Level per S/G 2/3 per S/G None Generator Wtr. Lvl.

17. Turbine-Generator 45 psig Auto Stop Oil Pressure 2/3 P-7 Trip or all four Stop Valves closed 4/4
18. Safety Injection l. Manual 1/2 None (Actuation)
2. Pressurizer at 1765 psig 2/3 None
3. Containment at 4.7 psig 2/3 High Con- None tainment pressure
4. Any one S/G 100 psig lower 1/2 Stearn Pressure None than 'any other two S/G's on any S/G lower than 1/2 Steam Pres-sures on 2/3 of the other loops.
5. Variable5 S~eam line flow 1/2 High Steam flow None 1.4 X 10 */hr. 0-20% Goad 2/4 Steam Gen. in increasing to 4.0 X 10 #/hr. coincidence with 2/4 at 100% pwr. in coincidence LOW TAVG or 2/4 low with Low TAVG 543°F or low steam line pressure.

Stm. Press. 500 psig.

19. General Alarm 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 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(:\ ' \'.'!

~'0JTI, ~\\~ \lJiuuilJ~",\ UU""u\J l>l.IU\Jlb. U Salem Unit l/Unit 2 .. 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 COMMENTS Utilize redundant indications where possible to confirm evaluations and actions.

4.1 Verify the Generator Output Breakers, 4.1 Should open ~30 seconds after 1-5 & 5-6(1-9 & 9-10) are open. the turbine trip.

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 4.2.l Should occur in ~15-18 minutes voltage is reinstated below following the trip.

5 x lo- 11 amps on both Inter-mediate Range Channels.

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 4.2.3 This should be accomplished as reactor trip has occurred and that soon as practical to insure the compensating voltage on the Inter- proper Intermediate Range mediate Range detectors should be ad- indication.

justed.

  • 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~ UUJU*~ WJJ'\Jts U Salem Unit l/Unit 2 Rev. 5

I-4.3

~-~ 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 4.4.1 Open manually as necessary.

have opened and acknowledge them on the appropriate control console bezel; 1 (2) BGGD 1(2) BFGD 1(2) AEGD 1(2) AHGD 4.4.2 Check that the following 4160V Breakers 4.4.2 Close manually as necessary.

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 4.5 Check Steam Dump Valve position avg at 547°F due to steam dump operation. indicating lights and the Stearn Dump demand indicator.

4.5.1 Ensure the Main Steam Pressure set- 4.5.1 Check the setting first to point is set to maintain Steam prevent any unwanted Stearn Generator press~re at 1\,1005 psig, Dump operation.

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 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 13 (23)BF19 Feedwater Control Valve 14 (24) BF19 Feedwater Control Valve W@~ m~r.rmrrn1~

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  • .'!.; I " l

..:::/J' (Q~n~W J'J Salem Unit l/Unit 2 Rev. 5

e I-4.3 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 4.7 Prevent any inadvertent re-progress. duction in Shutdown Margin.

= 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 4.8 The feed ring drains slowly normal (~33%) as follows: through the loose fit connection to the feed inlet piping.

  • CAUTION: If the Level in any Steam Genera-tor has been <10% on the narrow range for If conditions require maximum more than 5 minutes and all feedwater flow flow for decay heat removal has been isolated for more than 5 minutes, considerations, this takes 5

flow must be limited to < 1 x 10 lbm/hr. precedence over the water to that Steam Generator until the level hammer considerations.

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 4.10 Tech Spec 3.4.8 Table 4.4.

Chem Dept. perform an I 131 , I 133 , I1 35 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 Rev. 5

I-4.3 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 4.13 If any of the automatic functions the plant to the Cold Shutdown Condition IAW required (i.e. reactor trip, OI I-3. 6, "Hot Standby to Cold Shutdown". 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 As authorized by AP-5, withdraw the Shutdown Banks as follows:

4.14.1 Reset the flux rate trip by momentarily 4.14.1 Any reactor trip from power taking the RATE MODE switches, on each will generate a negative NIS POWER RANGE A drawer, to the RESET rate trip signal which seals position. in and must be manually reset.

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 4.14.4 If the STARTUP pushbutton control console, and verify each Shut- has been pushed prior to down and Control Rod Step Counter resets closing the Reactor Trip to zero. Breakers, a Rod Urgent Alarm condition will be present. This can be cleared by pushing either the STARTUP pushbutton or the ALARM RESET pushbutton.

Salem Unit l/Unit 2 Rev. 5

I-4.3 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 4.16.4 AFW Storage Tank level may to its normal at power lineup IAW be low.

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""-~~~~~~~~

Manager - Salem Generating Station Chris Connor Reviewed by_*~~~~~~~~~~~~~~~~~~

SORC Meeting No. 80-17

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

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

Salem Unit l/Unit 2 -B- Rev. 5

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