ML20237H719
| ML20237H719 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 08/21/1985 |
| From: | Patterson B, Strickland G TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20237H133 | List:
|
| References | |
| E, E-0, NUDOCS 8708170323 | |
| Download: ML20237H719 (14) | |
Text
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. ,.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-
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PORC REVIEW DATE:__
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APPROVED BY: %s,$ <% Plant Manager DATE APPROVED: b ' 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 PDR g 97 [PDRh7 ~- P
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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. -
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SQNP'
. . E-0 Unit 1 or 2
' Page 1 of 12 Rev. 0
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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:
Any rtactor . trip annunciator lit
~
a.
- 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 Symptoms of' a safety injection: e 2.
- a. Any SI -. ounciator lit ..
- b. ECCS , . aps in service l
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(- - 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 o b. Station service transferred F no complete train of 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:
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- 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
- c. E S/G level < 33%, SECONDARY HEAT SINK
, 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
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, 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 -
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- 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 . ._ . _ . _
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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
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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 F phase,B isolation 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
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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 .
)
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.- 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
/ -
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I i SQNP y 4 E-0 Unit.1 or 2 l
. 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, LOSS OF REACTOR C- }
. 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,' SQNP
. E-0 Unit 1 or 2 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 ...
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28 Return To Step 13
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