ML20237H719

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Rev 1 to Emergency Instruction E-0, Reactor Trip or Safety Injection
ML20237H719
Person / Time
Site: Sequoyah  
Issue date: 08/21/1985
From: Patterson B, Strickland G
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20237H133 List: ... further results
References
E, E-0, NUDOCS 8708170323
Download: ML20237H719 (14)
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{{#Wiki_filter:_ - _ - _ ,.4g.s f TENNESSEE VAL, LEY AUTHORITY SEQUOYAH NUCLEAR PLANT EMERGENCY INSTRUCTION E-0 REACTOR TRIP OR SAFETY INJECTION Revision 1 PREPAikEDBY: G. Strickland RESPONSIBLE SECTION:/ Operatic REVISED BY: G. M SUBMITTED BY: MfrT[ / Resp'onylble Shctiion S'n ervisor- ~ PORC REVIEW DATE:__ ' ~ APPROVED BY: %s,$ Plant Manager b DATE APPROVED: Reason for revision (include all Instruction Change Form Nos.): Revised to' add transition from other instructions;: add note to , monitor status trees. The last page of this instruction is number: 12 v-870gi{0 g 97 [PDRh7 PDR ~- P n .~~

e s4 SEQUOYAH, NUCLEAR PLANT ) PLANT INSTRUCTION REVISION LOG . EMERGENCY INSTRUCTION E-0 REVISION Date Pages REASON FOR REVISION (INCLUDE COMMIT-LEVEL Approved Affected MENTS AND ALL ICF FORM NUMBERS) 0 10/04/84 ALL Revised to add transition from other MIG 211985 instructions: add note to monitor 1 2 status trees. 1 i i l j 0269L/mbs ~ l i ~..anweaua

. _ _ _ _ _ _ _ _ _ - _ _ = _. ..g.,_ t SQNP' E-0 Unit 1 or 2 ' Page 1 of 12 Rev. 0 .. \\~ REACTOR TRIP OR SAFETY INJECTION. A. PURPOSE This guideline provides actions to verify proper response of. the automatic protection systems following manual or automatic actuation of a reactor trip or safety injection, to assess plant conditions, and. to identify the appropriate recovery guideline. 'B. SYMPTOMS 1. Symptoms of a reactor trip: ~ a. Any rtactor. trip annunciator lit b. Rapid decrease in neutron level indicated by nuclear instrumentation c. All control rods fully inserted. Rod. bottom lights lit d. Rapid decrease in unit load to zero power. l 2. Symptoms of' a safety injection: e a. Any SI -. ounciator lit b. ECCS,. aps in service l ~ 1 i l: - -., - -..,... - - ~ l I .k 1 1 b ? } l ; __-_J T:2 L ~'

(- SQNP E-0 Unit 1 or 2 Page 2 of 12 Rpv. 1 REACTOR TRIP OR SAFETY INJECTION [ STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED i Note: Steps 1 through 13 are IMMEDIATE ACTION STEPS. L Note: Foldout page should be open. Note: Status Trees should be monitored when transitioned out of this I instruction. 1 Verify. Reactor Trip IF reactor can NOT be Iripped, a. Rod bottom lights - ON THEN go to

  • FR-S.1, RESPONSE TO NUCLEAR b.

Reactor trip breakers - OPEN POWER GENERATION /ATWS c. RPIs at 0 STEPS / d. Neutron flux - DECREASING 2 Verify Turbine Trip a. All turbine stop valves - CLOSED i i 3 Verify Shutdown Boards Energized IF one complete train of shutdown boards energized, a. Generator breakers - OPEN THEN continue with the next (normally 30 sec delay) step b. Station service transferred F no complete train of o shutdown boards energized, k c. Voltage on shutdown boards THEN go to

  • ECA-0.0, k

LOSS OF ALL AC POWER. 4 Check If SI Actuated I_F SI NOT actuated and NOT required, THEN go to

  • ES-0.1, REACTOR TRIP RESPONSE 3

2-l'lYb

SQNP E-0 Unit 1 or 2 Page 3 of 12 Rey. 0 REACTOR TRIP OR SAFETY INJECTION STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 5 Verify ECCS Status Establish at least one train of ECCS flow a. CCPs - RUNNING b. SI Pumps - RUNNING c. RHR Fumps - RUNNING f d. Flow through BIT (FI-63-170) e. I_F RCS press < 1500 psig, THEN verify SI Pump flow (FI-63-20 and 151) f. IF RCS press < 180 psig, THEN verify RHR Pump flow (FI-63-91 A and 92A) 6 Verify Cntmt Isolation And ECCS Alignment a. Verify status monitor light: l

1) Panel 6C - DARK
2) Panel 6D - DARK
3) Panel GE - LIGHT except in outlined area
4) Panel 6F - LIGHT except in outlined area
5) Panel 6G - DARK except in outlined area
6). Panel 6H..- DARK i

j

SQNP E-0 Unit 1 or 2 Page 4 of 12 Re,v. O REACTOR TRIP OR SAFETY INJECTION STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 7 Verify MFW Isolation a. MFW isolation valves - CLOSED b. MFW reg valves - CLOSED c. MFW bypass valves - CLOSED d. MFW pumps - TRIPPED 8 Verify AFW Status Establish at least one AFW pump operation and AFW flow a. AFW Pumps - RUNNING E AFW flow can NOT be b. AFW level control valves established, in AUTO THEN go to

  • FR-H.1, RESPONSE TO LOSS OF E S/G level < 33%,

SECONDARY HEAT SINK c. THEN verify AFW flow d. S/G blowdown valves - CLOSED 9 Verify CCS Pumps - RUNNING Establish at least one train of CCS 10 Verify ERCW Pumps - RUNNING Establish at least one train of ERCW i 11 Verify EGTS And ABGTS - Establish at least one train j RUNNING of EGTS AND ABGTS l l l 1 l l I l

t l V SQNP E-0 Unit 1 or 2 j Page 5 of 12 Re,v. O REACTOR TRIP OR SAFETY INJECTION . STEP ACTION / EXPECTED RESPONSE , RESPONSE NOT OBTAINED 12 - Check Cntmt Press < 2.81 psig IF cntmt press > 2.81 psig, THEN verify:

a.. Cntmt Spray Pumps running b.

MSIVs AND bypass valve.s = closed c. Phase -B isolation

1). Panel GE - light -
2) Panel 6F -- light

~

d.. Manually stop all RCPs-e.

Air return fans start in ~ 10 minutes 13 Check T-avg a. T-avg < 547 F a. IF T-avg > 547 F,. THEN verify steam -dumps OR S/G PORVs open b. T-avg - STABLE AND 15. IF T-avg decreasing in an CONTROLLED uncontrolled manner, THEN verify steam dumps AND S/G PORVs closed. IF uncontrolled cooldown

Entinues, THEN close MSIVs AND.

MSIV bypass valves } ' ~5- ~ ;. ___-_.____----_s

l SQNP E-0 Unit 1 or 2 Page 6 of 12 Re,v. O REACTOR TRIP OR SAFETY INJECTION STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 14 Check Pzr PORVs - CLOSED IF RCS press < 2335 psig, THEN close pzr PORV O_R block valve IF pzr PORV AND block valve can NOT be closed, THEN go to

  • E-1, LOSS OF REACTOR OR SECONDARY COOLANT 15 Check Pzr Spray Valves -

F RCS press < 2250 psig, CLOSED THEN close pzr spray valve, IF_ spray valve can NOT be closed, THEN stop RCP supplying failed spray valve b

SQNP E-0 Unit 1 or 2 Page 7 of 12 Rev. 0 . \\ REACTOR TRIP OR SAFETY ' INJECTION STEP ~ ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 4 .16 - Check If RCPs Should . Remain In Service a. No Phase B isolation a. IF phase,B isolation F has occurred, THEN:

1) Stop all RCPs j
2) Maintain seal injection
3) Verify natural circulation a) RCS subcooling b) S/G press stable

-{ or decreasing c)- T-hot stable or decreasing d) Core exit T/C stable or decreasing } e) T-cold at saturation temp for S/G press IF natural circulation N~OT verified THEN increase dumping steam b. RCS press > 1250 psig b. I_F RCS press decreases uncontrolled to < 1250 psig THEN:

1) Verify at least one CCP OR SI Pump running

[ THEN stop all RCPs ' Q,;

2) Perform steps a.

to a.3 in column above ) l w

SQNP E-0 Unit 1 or 2 Page 8 of-12 Re,v.'O-Rj! ACTOR TRIP OR SAFETY INJECTION i STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED L17 Check S/G Press j S/G press low and decreasm, g in an a. Press in all S/Gs within uncontrolled manner 100 psi of each other THEN go' to

  • E-2,

. FAULTED STEAM y b. All S/G press - GENERATOR ISOLATION 'l ' STABLE OR INCREASING 18 Check Secondary Side Radiation IF secondary side radiatico- - NORMAL Is high, THEN go 'to

  • E-3, STEAM a.

Condenser exhaust monitors GENERATOR TUBE RUPTURE b. S/G blowdown monitors IF condenser exhaust and 3/G blowdown monitors NOT available, l THEN: Notify HP to survey main steamlines and S/G blowdown lines Notify chem lab to sample S/G activity Check RM-90-124 Aux Bldg 690 19' Check Cntmt Conditions IF, any entmt parameter is - NORMAL high, THEN go to

  • E-1, LOSS OF

-a. Press-REACTOR OR SECONDARY _ COOLANT b. Radiation c. Sump level d. Temp / i k j l

I i SQNP y E-0 Unit.1 or 2 4 . Page 9 of 12 i Rey. 0 ) l REACTOR TRIP OR SAFETY INJECTION STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 4 20 Check If SI Can Be Terminated a. RCS subcooling > 40 F a.,b.,c. IF RCS subcooling, RCS press, OR_ secondary b. RCS press - STABLE OR heat sink NOT satisfied, INCREASING THEN do not terminate SI. J Go to step 22. c. Secondary heat sink

1) Total AFW flow

- > 440 gpm

O_R,

~

2) Narrow range level in at least one S/G > 10%

d. Pzr level > 20% d. E all SI termination ,l criteria satisfied EXCEPT pzr level, THEN: . Maintain 'ECCS flow Stabilize RCS press with normal pzr sprays WHEN pzr level. > 20%, THEN go to

  • ES-0.2, SI TERMINATION 21 Terminate SI Per EC-0.2 a.

Go to ES-0.2, SI Termination i

SQNP E-0 Unit 1 or 2 + Page 10 of 12 Re,v. 0 - REACTOR TRIP OR SAFETY INJECTION STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 22 Monitor Status Trees - 23 Check S/G Levels a. Narrow range S/G a. Verify AFW flow and levels > 25% S/G levels returning to normal program b. Control S/G 1evels b. E any S/G 1evel between 25% and 50% continues to increase with no AFW flow, THEN go to

  • E-3, STEAM GENERATOR TUBE RUPTURE 24 Check Aux Bldg Radiatier.

Try to identify and isolate - NORMAL radiation leakage paths BUT do not stop any ECCS a. Area monitor recorders injection when isolating RR-90-1 and 12 leakage b. Vent monitor RM-90-101 25 Check PRT Conditions - NORMAL IF PRT abnormal, THEN check following: a. Press Pzr PORV b. Level Pzr safety valve c. Temp Reactor vessel head vent b - l'

SQNP E-0 Unit 1 or 2 Page 11 of 12 Rev. O REACTOR TRIP OR SAFETY INJECTION STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION: If RCS press decreases to 180 psig, then the RHR Pumps must be manually restarted. CAUTION: If offsite power is lost after SI reset, then manual action will be required to restart the SI Pumps and RHR Pumps. 26 Check If RHR Pumps Should i Be Stopped a. Check RCS press

1) RCS press > 180 psig
1) IF, RCS press 5180 psig, THEN go to
  • E-1, C-

} LOSS OF REACTOR OR SECONDARY COOLANT

2) RCS press - STABLE
2) IF, RCS press OR INCREASING decreasing, THEN estabush CCS to RHR heat exchanger.

Go to. next step. b. Reset SI b. Check P-4 interlock with SI reset, SI-268 c. Stop RHR Pumps and place in standby d

f-J,' . E-0 Unit 1 or 2 SQNP Page 12 of 12 Rev. 0 i'( REACTOR TRIP OR SAFETY' INJECTION STEP ACTION / EXPECTED RESPONSE RESPONSE NOT'OBTAINED 27- . Check If D/G Should Be~ Stopped.

a. - All shutdown boards a.

Attempt to restore energized by offsite offsite power per power-AOI-35

b.. Reset SI b.

Check P-4 interlock with SI reset, SI-268 c. Place D/G in standby per SOI-82, Removing D/G From Service After An Emergency Start ~ 28 Return To Step 13 m = 9 e +., mom s, .e p aup pgan - M oe,m em emp*e m e+w 4 . mis- =- see mem e ei em p,,, END - ) l l .. -}}

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