ML20237H986
| ML20237H986 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 05/15/1987 |
| From: | Anthony J, Strickland G TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20237H133 | List:
|
| References | |
| E-3, NUDOCS 8708170448 | |
| Download: ML20237H986 (8) | |
Text
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TENNESSEE VALLEY AUTHORITY C
SEQUOYAH NUCLEAR PLANT
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EMERGENCY INSTRUCTION E-3
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STEAM GENERATOR TUBE RUPTURE
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Revision 2 PREPARED BY:
G. Strickland RESPONSIBLE SECTION: Operations
' REVISED BY:
G. Strickland
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SUBMITTED BY:
M.
Reshn'sibleSection$upervisor jfr MAY 51987 PORC REVIEW DATE.
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APPROVED BY:
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Plant Manager DATE APPROVED:
MAY T51987 Reason for revision (include all Instruction Change Forn Nos.):
Revised to make minor change of HP to RAD CON for page 1 SYMPTOMS and steps 1 and 3.
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The last page of this instruction 1s number:
6 8708170440 070811 PDR ADOCK 05000327 p
PDR 2
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1 SEQUOYAH NUCLEAR PLANT l
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i PLANT INSTRUCTION REVISION LOG C : )T'-
EMERGENCY INSTRUCTION E-3 REVISION Date Pages REASON FOR REVISION (INCLUDE COMMIT-LEVEL Approved Affected MENTS AND ALL ICF FORM NUMBERS)
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' Revised to add transition from other 1 instructions; add check of S/G Press prior to closing PORV; expand table for 1
08/21/85 All RCS cooldoin.
Revised to make minor change of HP to RAD CON for page 1 SYMPTOMS and steps 2 MAY1 a 1987.:
1.2 1 and 3.
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1 0236L/ jaw s_
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SQNP E-3 Unit 1 or 2 Page 1 of 6 Rev. 2
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STEAM GENERATOR TUBE RUPTURE A.
PURPOSE This guideline provides actions to terminate. leakage of reactor coolant into the secondary system following a steam generator tube rupture.
B.
SYMPTOMS q
1.
Condenser exhaust radiation high 2.
Steam generator blowdown radiation high 3.
Rad Con survey of main steam lines abnormal 4.
Rad con survey of steam generator tlowdown lines abnormal 5.
Chem lab sample of steam generator blowdown abnormal 6.
Increasing steam generator level with no AFW flow
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TRANSITION FROM OTHER INSTRUCTIONS 1.
E-0, Reactor Trip Or Safety Injection 2.
E-1, Loss Of Reactor Or Secondary Coolant 3.
ES-1.1,. Post LOCA Coeldown 4.
E-2, Faulted Steam Generator Isolation 5.
ES-3.2, Post-SGTR Cooldown Using Backfill 6.
ES-3.3, Post-SGTR Cooldown By Ruptured ~ S/G Depressurization
.i. Foldout Page s
8.
FR-H.3, Response To Steam Generator High Level l
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SQNP i
E-3 Unit 1 or 2 Page 2 of 6 Rev. 2
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STEAM GENERATOR TUBE RUPTURE STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 1
Implement REP Per IP-1 a.
Notify Operations Duty Specialist within 5 min b.
Sound eme gency siren to assemble personnel c.
Dispatch Rad Con to survey secondary plant 2
Bypass Condensate DI 3
Identify Ruptured S/G a.
Check one or more of the
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a.
Do not proceed until
, following:
ruptured S/G identified
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- 1) Unexpected rise in S/G 1evel
- 2) S/G blowdown monitors RM-90-120,121, or 124
- 3) Rad Con survey of main steamlines
- 4) Rad Con survey of blowdown lines
- 5) Chem lab sample im SQNP E-3 Unit 1 or 2 Page 3 of 6 Rev.1 l(
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STEAM GENERATOR TUBE RUPTURE STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION: At least one S/G must be maintained available for RCS cooldown 4
Isolate Ruptured S/G a.
Ensure ruptured S/G PORV controller in AUTO and PORV closed when S/G press < 1040 psig b.
Close ruptured S/G b.
IF MSIV or bypass MSIV and bypass valve can NOT be closed, THEN close:
- 1) Intact S/G MSIVs and bypasses
- 3) Condenser steam dumps
- 5) Steam seals
- 6) Steam header traps c.
Close ruptured S/G blowdown d.
Close steam supply from d.
IF at least one MD AFW ruptured S/G to turbine-pump aligned to an driven AFW pump intact S/G, THEN stop turbine-driven AFW pump e.
WHEN ruptured S/G e.
Maintain AFW flow to
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narrow range level > 5%
ruptured S/G until
[25% FOR ADVERSE level > 5% [25% FOR CNTMT),
ADVERSE CNTMT]
THEN isolate AFW to ruptured S/G _ _ _ _ _ _ _ - _ _ _
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-SQNP
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E-3
. Unit 1 or 2 l
Page 4 of 6-Rev. 1 STEAM GENERATOR TUBE RUPTURE p
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION: -Disregard 1250 psig RCP trip criteria during a controlled RCS depressurization.
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5 Cooldown RCSs a.
Ensure ruptured a.
Do not proceed until-c' S/G isolated ruptured S/G isolated.
E b.
Initiate rapid RCS cooldown b.
IF condenser steam l
to maximum T-hot using iliimps-NOT available, condenser dumps (see table
.THEN use intact S/G below)
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Target T-hot For RCS 'Depressurization ls Ruptured S/G Press Max T-hot For Intact S/G Loops 1100 psig 515 F-1000 psig 505 F 900 psig 490 F 800 psig 480 F 700 psig 460 F 600 psig 445 F 500 psig 430 F 400 psig 405 F
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300 psig 380 F
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200 psig 345 F - _ _ - _ _ -
4-g SQNP E-3 Unit 1 or 2
. Page 5 of 6
.. Rev. 1
. STEAM GENERATOR TUBE RUPTURE o'
n STEP.
~ ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION:
RCS depressurization may begin during cooldown provided RCS subcooling is maintained > 40 F 6.
Depressurize RCS a.
At 51900 psig, isolate UHI b.
Depressurize RCS using b.
IF normal sprays NOT F
normal pzr sprays available, THEN use one pzr PORV and note following:
- 1) Upper head may void during
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depressurization ic
- 2) Minimize cycling PORV 3)- PRT may rupture IF both normal sprays AND PORVs not available, THEN use aux spray l
c.
Stop depressurization c.
IF_ RCS depressurization when one of the following can NOT be stopped, conditions met:
THEN consider following actions:
RCS press < ruptured
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S/G press -
Stop RCP associated with failed spray valve OR Close pzr PORV block I
Pzr level > 70%
valve OR Isolate aux spray by closing FCV-62-90 RCS suboooling 5 40 F and 91 i
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a SQNP E-3 Unit 1 or 2 Page 6 of 6 Rev. 1 (i
STEAM GENERATOR TUBE RUPTURE STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 7
Check If SI Can Be Terminated RCS subcooling > 4'O F a.b.c.
IF RCS subcooling, a.
RCS press'- STABLE OR heat sink NOT satisfied,
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INCREASING THEN do not terminate SI.
Re-diagnose per foldout c.
Secondary heat sink:
page
- 1) Total AFW flow to intact S/Gs > 440 gpm O_R
- 2) Narrow range level in at least one intact
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S/G > 10% [25% FOR ADVERSE CNTMT]
.a d.
Pzr level > 20% [50% FOR d.
IF all SI termination ADVERSE CNTMT]
criteria satisfied EXCEPT pzr level, THEN:
Maintain ECCS flow Continue RCS cooldown and depressurization until pzr level > 20%
[50% FOR ADVERSE
)
CNTMT]
WHEN pzr level satisfied, THEN go to
TERMINATION FOLLOWING l
SGTR C !
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Go to ES-3.1, SI Termination Following SGTR
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