ML20112C962

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Rev 25 to Procedure Work Plan 1202.001, Reactor Trip
ML20112C962
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 12/22/1994
From:
ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20112C961 List:
References
1202.001, NUDOCS 9606030251
Download: ML20112C962 (9)
v • d • e


Text

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J J gc:= ENTERg ENTERGY OPERATevNS INCORPORATED ARKANSAS NUCLEAR ONE-63 of 79 N M M. REV.

TITLE: REACTOR TRIP 1202.001 25 EXP.DATE SAFETY RELATED ,

[ N/A EVES DNO lh a N 9 CONTROLLED COPY # ,A E 1 o, ,

5DNO PAGE REV CHG PAGE REV CHG' PAGE REV CHG PAGE REV CHG 1 25 fc-i 18 25 2 25 19 25 l i

3 25 20 25 4 25 21 25 5 25 22 25 6 25 23 25 7 25 1 8 25 1

9 25 f 10 25 f'*L .)

VERIFIED BY DATE TIME .

11 25 fE li 12 25 f(-t g 13 25

- 14 25 l

15 25 25  ;

16 i

I 17 25 APPROVAL AUTHORITY: APPROVAL DATE:

s /2/za/9 FORM TITLE:

[ REQUIRED EFFECME DATE: 12 9 4 ~ '

FORM NO. REV.

UST OF AFFECTED PAGES 1000.006A 41 9606030251 960531 PDR ADOCK 05000313 '

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_ _ _ _ _ .. . ._. _ __ . _ . _ .-_. .__ _ _ _ _ _ =

lpc.g 1202 001 REACTOR TRIP RREV 25 PAGE 1 of 23

. ENTRY CONDITIONS e An automatic Rx trip or DSS trip. ,

e Failure of RPS to trip the Rx upon reaching a limit listed below:

I

- High power .......................... 104.9% )

1 High power / pumps .................... one pump per loop . 255% l 9E I O pumps in one loop . 20%

gl - High power / imbalance / flow ........... COLR Figure 9  !

- High RCS temp ...................... 2618 'F(T-hot)

High RCS press ..................... 22355 psig

- Low RCS press ....................... $1800 psig

- va riable low RCS press . . . . . . . . . . . . . . Tech Spec Figure 2. 3-1 High RB press ...................... 218.7 psia

- Turbine trip ........................ Rx power 243% AMD Turbine is tripped

- Both MFW pumps trip ................. Rx power 29% AND both MFW pumps tripped.

  • PZR level dropping <100",

AND no indication of recovery.

  • PZR level >290".
  • Any MSIV closure at power.

-e Either SG level <l5" or >95%,

AMD no indication of recovery.

  • A system degradation that requires manual Rx trip based on operator judgment.
  • Abnormal operating Procedure requirement.
  • Ir a system degradation occurs while shutdown, above DHR operation, THEN perform applicable steps.

l

., .1202.001 REACTOR TRIP REV 25 PAGE 2 of 23 INSTRUCTI0ftS CONTINGEllCY ACTIONS Depress Rx Trip PB.

A. Verify all rods inserted A. Perform the following:

Alf 1) Depress CRD Power Supply Breaker Trip PBs on C03 (A-501 Reactor power dropping. and B-631).

2) H A-501 or B-631 fails to trip, IHt! manually insert rods at C03.

a) Dispatch an operator to open CRD AC Power Supply breakers.

3) H acre than one rod fails to fully insert 91 Rx power is ag1 dropping, IBt!

perform Energency Boration (RT 12).

Depress Turbine Trip PB.

A. Verify Turbine throttle and A. Perform the following:

governor valves closed.

1) II,125 V DC Bus D01 is de-energized as indicated by both of the following, IEEt!

perform Loss of 125V DC (1203.036) " Loss Of Bus D01" section in conjunction with this procedure.

  • Breaker position indications on left side of C10 off.

(2. CONTINUED ON NEIT PAGE)

L _.-- ___

k202.001 REA R TRIP RIV 25 PAGE 3 ef 23 InsrRocrI0.s _ C0 r s. cr 4crIO.,

2. (Continued).
2) H SG press is <900 psig, Iggt!

perform the followings a) Actuate MSLI for affected SG(s)

AEt actuate EFV ARE verify proper actuation and control (RT 6).

b) G0 TO 1202.003, "0VERC00 LING" procedure.

Reduce Letdown by closing Orifice Bypass (CV-1223).

Check adequate SCN. 4. GO TO 1202.002, " LOSS OF SUBC00 LING MARGIN" procedure.

l'

5. Advise Shift Superintendent to implement Baergency Action Level Classification (1903.010).
6. Check for proper electrical response as follows:

A. Check 125V DC Bus D01 energized: A. Perform Loss of 125V DC (1203.036)

" Loss Of Bus D01" section in

  • Turbine Trip Solenoid Power conjunction with this procedure.

Available light lit.

  • Breaker position indications available on left side of C10.

B. Perform the following:

B. Check Main Generator and Exciter Pield breakers open.

1) H D01 is energized, IEEE manually trip Main Generator and Exciter Field breakers.

(6. CONTINUED ON NEIT PAGE)

_~_

j202001

. REACTOR TRIP- REY 25 PAGE 4 of 23 INSTRUCTI0lts 00lffDGNCY ACTI0ttS

6. (Continued).
2) H D01 is de-energized, M i leave Main Generator and Exciter Field breakers closed. 1 C. Check DGs off. C. Verify SERV VTR to running DG(s) open:  ;

l El M2  !

l CV-3806 CV-3807

)

i D. Check A3 and A4 energized (4160V D. Perform the following for buses).

de-energized bus:

R associated bus'L.O. RELAY l 1)

TRIP alarm is clear on K02 E

associated EDG is running with normal voltage and frequency (4160VAC and 60HZ), M attempt to reset breaker anti-pump feature by taking handsvitch to PULL-TO-LOCK M releasing:

DG1 DG2 l

A-308 A-408 1

l l

l 3

J (6. CONTINUED ON NEIT PAGE)

..' [1202.001 REACTOR TRIP RIV 25 FAGE 5 ef 23 INSTRUCTIONS CONTDIGENCY ACTIONS i

6. (Continued). l

' 2) R associated EDG sa n g.1 supply 1 ES bus M .l associated bus L.O. RELAY TRIP' alars is clear on K02 l

.g associated non-vital bus is i energised, IB M attempt to close ES bus normal feeder  !

breaker (use SYNC switch): l l

A3 A4  !

A-309 A-409 l

3) H all 4160V buses are.

de-energized, IE E GO TO 1202.008, "BIACKottt" procedure. l

4) R only EDG power is supplying i 4160V buses, IE E GO TO 1202.007, " DEGRADED POWER" procedure. j (6. CONTINUED ON NEIT PAGE)

,1202.001 REACTOR TRIP REV 25 PAGE 6 cf 23 INSTRUCTIONS - CONTINGENCT ACTIONS

6. (Continued).

Check Al and A2 energized (4160V E. Perform the following:

E.

buses).

1) H non-vital 4160V bus is needed to power required equipment M

associated bus L.O. RELAY TRIP alarm is clear on K02 M

off-site voltage is normal, M perform the following:

SU1 SU2 222KV 2157KV a) H SUI is available, M energize bus from SUI (use SYNC switch).

(1) IF. non-vital 4E,0V bus feeder breaker fails to close, M attempt to reset breaker anti-pump feature by taking handsvitch to PULL-TO-LOCK M releasing.

(6. CONTI MED ON NEXT PAGE)

1202.001 REACTOR TRIP EEV 25 PAGE 7 ef 23

. INSTRUCTIONS _ CONTDGNCf. ACTIONS

6. (Continued).

.........................................a.i

. CAUTION .

  • The following step will result in load .;
  • shed of non-vital 4160V buses Al and A2..l

...........................................J NOTE SU2 is considered available if all the following conditions are met:

  • AUTO I-FMR energized from 500KV
  • AUTO I-FMR aligned to SU2
  • En Unit 2 buses aligned to SU2 i
  • SU2 V REG 3% reduction disabled l b) R SU2 only is available, IgIt[ energize bus from SU2 i (use SYNC switch). j l

(1) H non-vital 4160V bus l feeder breaker fails to close, IEEl[ attempti to reset breaker anti-pump feature by taking handsvitch to t PULL-TO-LOCK AlE releasing.

2) H only EDG power is supplying 4160V buses, IIIl[ GO TO 1202.007, " DEGRADED POVER" procedure.

,, .1202.001 REACTOR TRIP REV 25 PAGE 8 of 23 INSTRUCTIONS . 00RTINGENGT 4CTIONS l

7. Check OP HPI pump supplying normal 7. Perform the following:

Makeup and Seal Injection.

A. Isolate Letdown by closing either:

Letdown Coolers Outlet (CV-1221) l DE Letdown Cooler Outlets (CV-1214 and ;

I 1216).

B. Restore normal Makeup and Seal i Injection (RT 1). l

8. Check both SG 1evels remain $410". 8. Trip both MW pumps Alg), perform the following:

A. Place overfilled SG E W Pump Turbine (K3) Steam Supply valve in MANUAL 4t]R close SG A SG B CV-2667 CV-2617 B. Actuate E W Atg verify proper actuation and control (RT 5).

1) H all MW and EW is lost, IEEE GO TO 1202.004, "0VERHEATING" procedure. l C. H SG press is <650 psig, L1EN, trip all Condensate pumps.
9. Check Instrument Air Header press >75 9. H Instrument Air Header press drops psig. below 35 psig, IEEE perform the following:

A. Actuate MSLI and E W AHg verify .

proper actuation and control (RT 6).'

B. Perform Loss of Instrument Air (1203.024) " Loss of Instrument Air Pressure (s35 psig)" section in conjunction with this procedure. ,

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