ML20237H770
| ML20237H770 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 06/12/1987 |
| From: | Strickland G, Terpstra G, Jacqwan Walker TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20237H133 | List:
|
| References | |
| E-1, NUDOCS 8708170351 | |
| Download: ML20237H770 (15) | |
Text
- _ _ _ _ _.
.d TENNESSEE VALL'EY AUTHORITY SEQUOYAH NUCLEAR PLANT y
EMERGENCY INSTRUCTION a
E-1 o
LOSS OF REACTOR OR SECONDARY COOLANT t
Revision 2 P
PREPARED BY:
G. Stri.ckland s
l RESPONSIBLE SECTION: Operations REVISED BY:
G. Terpstra SUBMITTED BY k k.IA nh an_
L-gsponsibi cfig Supervisor PORC REVIEW DATE:
"I 5 5-dir JUN 1 2 1987
~
APPROVED BY:
Plant Manager DATE APPROVED:
.dONI s
Reason for revision (include all Instruction Change Form Nos.):
Revised to make minor procedure enhancements; step 4 RNO -
changed Chem Lab to chem lab and HP to RAD CON: step 13.c changed Heat Sink to heat sink: step 18 RNO changed 'to to' to
'go to'; and added S01-88.1 as a reference for cntmt iso?ation in Appendix: step 26 added to place H2 Recombiners I/S (B45 870402 254)
=(
added note to step 14 and step 22 change TI-66 to TI-66.1: this constitutes a biennial review.
w The last page of this instruction is number:
13 8708170351 870811 PDR ADDCM 05000327 P
PDR.
,t
___________1
I d
SEQUOYAH NUCLEAR PLANT PLANT INSTRUCTION REVISION LOG EMERGENCY INSTRUCTION E-1 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 1
1,9, instructions; to reword step for clari-1 08/21/85 10,11 fication.
I' Revised to make minor procedure enhance-ments; step 4 RNO - changed Chem Lab to chem lab and HP to RAD CON; step 13.c changed Heat Sink to heat sink; step 18 RN0' changed 'to to' to 'go to'; and added S0I-88.1'as a reference for cntmt isolation in Appendix; step 26 added to
. l, place H2 Recombiners I/S (845 870402 L
254), added note to step 14 and step 22 change, TI-66 to TI-66.1; this JUN 1 2 Ic87 All constitutes a biennial review.
2
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_.---____._-.-____.-_-__---__-_-_____.___---a
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SQNP-'
I,
,E-1 Unit 1 or 2 Page 1 of 12 p
Rev. 2
. lI f,
1 x LOSS OF REACTOR OR SECONDARY COOLANT-9 A '.
PURPOSE
/
This guideline provides actions to recover from a loss of reactor or secondary coolant.
a rB.
SYMPTO'MS s
t L
1.
Symptoms of a loss of reactor coolant:
a.
Cntmt press high b.
Cntmt radiation high L
c.
Cntmt sump level high
- d.. Cntmt temp high f.
Pzr PORV open and block valve cannot be closed e.
2.
Symptoms of a loss of secondary coolant:
a.
S/G press 100 psi. lower in one S/G than the others b.
Any S/G press decreasing in an uncontrolled manner C.
TRANSITION FROM OTIIER INSTRUCTIONS 1.
E-0, Reactor Trip Or Safety Injection 2.
E-2, Faulted Steam Generator Isolation 4.
Foldout page 5.
ECA-0.2, Recovery From Loss Of All AC Power With SI Required
?(p EMERPR/E aac
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SQNP
'E-1 Unit 1 or 2
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Page 2 of 12 j
f Rev. 2
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f i-i LOSS OF REACTOR OR SECONDARY COOLANT l
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED -
1 Check If RCPs Should Remain In Service
'a.
No phase B isolation a.
IF phase B isolation t
has occurred, THEN:
s
- 1) Stop all RCPs
[
- 2) Maintain seal injection 3
- 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 NOT L
verified THEN increase dumping steam b.
RCS press > 1250 psig b.
I_F RCS press decreases 4
uncontrolled to < 1250 psig,
~-
THEN:
L
- 2) Perform steps a.1 to a.3 in column above EMERPR/E aac
- {l -
.SQNP g
.. E-1 Unit 1lor 2 Page.3 of 12 Rev. 2 4-1 (
LOSS.0F REACTOR OR SECONDARY COOLANT d.
- l STEP ACTION / EXPECTED RESPONSE '
RESPONSE NOT OBTAINED 2-Initiate REP Per IP-1 a.' Notify Operations -
i Duty Specialist within 5 min
-3 Check S/G Press IF the S/G with low or IIecreasing press has
~ ~
a.
Press in all S/Gs within NOT been isolated, 100 psi of each other THEN go to
- E-2, FAULTED STEAM b.
All S/G press -
GENERATOR ISOLATION STABLE OR INCREASING i:
4.
Check Secondary Side Radiation IF secondary side radiation
- NORMAL is high, THEN go to
- E-3, STEAM
- a.
- Condenser exhaust monitors GENERATOR TUBE RUPTURE
(
b.
S/C b' wdown monitors IF condenser exhaust and f
I, 57G blowdown monitors 1
NOT available, l
TIllfN:
{.
Notify Rad Con to survey main steamlines I
and S/G blowdown lines Notify chem lab to -
sample S/G activity Check RM-90-124
.L Aux Bldg 690
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l
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w EMERPR/E aac-
SQNP' E-1 Unit 1 or 2 Page 4 of 12 l
7 Rev. 2 1
\\_
LOSS OF REACTOR OR SECONDARY COOLANT 1 x
' t o.
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBT kNED 5
' Check Intact S/G Levels a.
. Narrow range S/G a.
Verify AFW flow and S/G levels > 25%
levels returning to normal
~
s program b.
Control S/G levels b.
IF any S/G level continues
.g.
between 25% and 50%
lo increase with no AFW
'[
- flow, THEN go to
- E-3,
' E, STEAM GENERATOR
[.
TUBE RUPTURE l
6 Check CST Level a.
CST level > 3 ft a.
IF CST level < 3 ft, C
THEN verify ERCW aligned to AFW b.
CST level > 17 ft b.
IF CST level < 17 ft, l,
THEN attempt to refill E.
CST while continuing with this instruction 7
Check Pzr PORVs and Block Valves a.
Pzr PORVs - CLdSED a.
IF RCS press < 2335 psig, THEN close pzr PORV OR
~
block valve
- b. ' At least one block valve -
b.
Open one block valve,
OPEN unless it was closed to isolate an open' PORV 7
EMERPR/E 83C
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_.___.__m________-___a
s-SQNP E-1 Unit 1 or 2 Page 5 of 12 e
Rev. 2
/
LOSS OF REACTOR OR SECONDARY COOLANT A,- s
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STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 8
Check If Cntmt Spray Should Be Stopped a.
Cntmt press < 2.81 psig a.
WHEN cntmt press t
reduced to < 2.81 psig, THEN place Cntmt Spray Pumps in standby b.
Reset entmt spray signal I..
c.
Place Cntmt Spray Pumps in standby l
9 Check If Cntmt Vacuum Control "Should Be Returned Normal I
a.
Cntmt press < 1.5 psig a.
WHEN cntmt press reduced to < 1.5 psig, THEN open FCV-30-46, 47 and 48 b.
Ensure entmt vacuum relief valves in service
- 1) FCV-30-46 open
- 2) FCV-30-47 open
- 3) FCV-30-48 open I.
t
)
'4 f
\\
m EMERPR/E aac m
f SQNP t
t E-1 Unit.1 or 2' Page 6 of 12 Rev. 2
.j..
. ;l LOSS OF. REACTOR'OR SECONDARY COOLANT i
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION:
If RCS press decreases to 180 psig, then.
i the RHR Pumps 'must be manually restarted.
t CAUTION:
If offsite power is lost after SI reset, then manual
_g action will be required to restart the S1 Pumps and
. )
RHR Pumps.
10 Check If RHR Pumps Should
. Be Stopped a.
Check RCS press a.
F RCS press low or
. decreasing,
/
Reset SI b.
Check P-4 interlock with SI reset, 1
SI-268 c.
Stop. RHR Pumps and place in standby L
1.
h'
- (F-t EMERPR/E aaC L
SQNP E-1 Unit 1 or 2 Page 7 of 12
[
Rev. 2
{,.
LOSS OF REACTOR OR SECONDARY COOLANT STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBT INED 11 Check If UHI Should Be Isolated IF UHI injected, THEN verify isolation a.
WHEN RCS press valves closed and gag f 1900 psig isolation valves AND STABLE, THEN isolate UHI 12 Check If D/G Should Be Stopped a.
All shutdown boards energized a.
Attempt to restore by offsite power offsite power per 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 I
i E
u e
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f s
f 7
b n
EMERPR/E aac
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SQNP E-1 Unit-1 or 2 i
Page 8 of 12:
i Rev. 2 i
4, LOSS OF REACTOR OR SECONDARY COOLANT o '
l STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBT INED l
13 Check If SI Can Be Terminated IF any of the 4 SI termination criteria a.
RCS subcooling > 40 F can NOT be satisfied, I-.
' THEN do not. terminate ~
Go to step 15.
s OR INCREASING c.
Secondary heat: sink
)
~
l
- 1). Total AFW flow to intact S/Gs > 440 gpm 1
- )
- 2) Narrow range level 3,
in at least one intact S/G > 10% [25% FOR ADVERSE CNTMT]
' d. ' Pzr level > 20%
[50% FOR ADVERSE CNTMT) l Note:
If a small break LOCA is in. progress, then E-1 should be used
[
instead of terminating SI per ES-0.2 14 Terminate SI Per ES-0.2 a.
Go to ES-0.2, SI Termination 2
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- (
i w
EMERPR/E I aac
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SQNP l
E-1 Unit 1 or'2
)
Page 9 of 12 Rev. 2 j
i, g.
- {
t I
LOSS 'OF REACTOR OR SECONDARY COOLANT c
e.
i STEP ACTION / EXPECTED RESPONSE 1
RESPONSE NOT OBTAINED
~'
15 Open Ice Condenser AHU ACBs a.
Rx Vent Bd A-A Compt 6E and 7D
- g, O
b.
Rx Vent 15'd B-B Compt 4D and GE I
L 16 Energize Hydrogen Ignitors
- 3 a.
Pnl M-10
-[
17 Place Cntmt Hydrogen Analyzers In Service
/'
a.
Refer to SOI-43.1 18 Continue Recovery Based On Event a.
IF a loss of IF LOCA in progress, a.
a secondary coolant THEN go to next step g
is in progress WITH NO - LOCA:
- 2) Cntmt radiation -
NORMAL
\\
THEN return to step 1 and repeat the previous L
steps until plant conditions allow transition to another instruction y
L L.%
EMERPR/E aac -
p.
SQNP E-1 Unit 1 or 2 Page 10 of 12 Rev. 2 LOSS OF REACTOR OR SECONDARY COOLANT r
STEP
_ ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED s
19 Check Aux Bldg Radiation Try to identify and isolate
- NORMAL radiation leakage paths BUT do not stop any ECCS a.
Area monitor recorders injection when isolating ~
I RR-90-1 and 12 leakage b.
Vent monitor RM-90-101 20 Verify Aux Bldg Isolation a.
Refer to SOI-30.5E 21 Verify Main Control Room Isolation
~
a.
Refer to SOI-30.1
/
22 Start Post Accident Sampling
'l a.
Notify chem lab to start t
TI-66.1, Post Accident Sampling And Analysis Methods 23 Evaluate Plant Equipment j
a.
Check system status i
per Appendix A I
e i
s J
7 w
EMERPR/E <
aac t
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L.
SQNP L.
E-1 Unit 1 or 2 u..
c Page 11 of 12 Rev. 2 l'
Ir LOSS OF REACTOR OR SECONDARY COOLANT
}%
s l
STEP-ACTION / EXPECTED RESPONSE RESPONSE-N'OT OBTdINED -
i s y
24 Check If RCS Cooldown And Depressurization Required n.
IF RCS press > 180 psig -
a.
IF RCS press < 180 psig, I,
AND LOCAcin progress, THEN verify RHR flow
,L.
THEN go to ES-1,1, and go to next step -
Post LOCA Cocidown
{-
IF 'LOCA NOT in
)
'l progress,
THEN return to' step 1 r
25 Prepare For Switchover To RHR-Cntmt Sump a.
Restore power to FCV-63-1 g#
b.
Power available to
, RHR Pumps c.
WHEN RWST level < 29%,
THEN go to ES-1.27 Transfer To RHR Cntmt Sump-26 Place Hydrogen Recombiners In Service a.
Refer to SOI-83.1 27 Depressurize S/Gs To RCS Press m
a.
Check S/G radiation -
a.
Do not dump steam NORMAL from a S/G with high j
"~
radiation.
Isolate-l AI"W flow to a S/G with high radiation b.
Depressurize intact S/G i
below RCS press m
EMERPR/E aac
_-J
SQNP E-1 Unit 1 or 2 Page 12 of 12 Rev. 2 LOSS OF REACTOR OR SECONDARY COOLANT STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED i,
28 Prepare For Switchover To 4
Hot Leg Recire a.
Restore power to FCV-63-22 l'
s
(
b.
AFTER 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> from switchover to entmt sump, THEN go to ES-1.3, Transfer To Hot Leg Recire i
I 29 Evaluate Long Term Plant Status u
(
a.
Consult TSC I.
. l t~
L 1-I i,
- END -
h EMERPR/E j aac
)
i
P SQNP E-1 Unit 1 or 2 Appendix A Page 1 of 1 Rev. 2 LOSS OF REACTOR OR SECOND'ARY COOLANT Check equipment availability:
4
- 1. Centrifugal Charging Pumps
- 2. Safety Injection Pumps
- 3. RHR Pumps
- 4. Auxiliary Feedwater System L
- 5. Cntmt Spray System
- 6. Shutdown Boards
- 7. Diesel Generators (Fuel oil supply and starting air) f
- 8. ECCS Re, circulation Availability s
t- ~
- 11. Cntmt Isolation Systems (Refer to SOI-88.1A, SOI-88.1B, and SOI-88.1C.)
O m
- "(:-
o EMERPR/F aac
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-..... _ _