ML20237H967

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Rev 2 to Emergency Instruction E-2, Faulted Steam Generator Isolation
ML20237H967
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 05/22/1987
From: Strickland G, Terpstra G
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20237H133 List: ... further results
References
E-2, NUDOCS 8708170440
Download: ML20237H967 (6)


Text

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TENNESSEE VALLEY AUTHORITY -

f SEQUOYAH NUCLEAR PLANT ..

-k EMERGENCY INSTRUCTION- -

i E-2 ~

, FAULTED' STEAM GENERATOR ISOLATION --

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..<. 5 Revision 2 .

PREPARED BY: G. Strickland RESPONSIBLE SECTION: Operations i

REVISED BY: Gary L. Terpstra SUBMITTED BY: N. x ,-

ReponsibleSection\ Supervisor PORC REVIEH DATE:

APPROVED BY: ~

P1 ant Manager DATE APPROVED: MAY 22 7007 Reason for revision (include all Instruction Change Form Nos.):

RevisedtochangeHPtoRADCON: step 1 - added S/G level to RNO in determin- s ing faulted S/G, and step 2 - added part a RNO (comment from training) and part d RNO (WP 12188). ~

The last page of this instruction is number: 4 r

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l 8708170440 870811 .  !

PDR ADOCX 05000327 '

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l SEQUOYAH NUCLEAR PLANT PLANT INSTRUCTION REVISION LOG

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EMERGENCY INSTRUCTION E-2 REVISION Date Pages REASON FOR REVISION (INCLUDE COMMIT-LEVEL Approved Affected MENTS AND ALL ICF FORM NUMBERS)

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0 10/04/84 ALL -

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Revised to add transitions from other l 08/21/85 1 instructions.

Revised to change HP to RAD CON; step 1-added S/G level to RNO in determining

.', faulted S/G, and step 2 - added part a htAY 2 2 1987 RNO (comment from training) and part d 2 2,3,4 RNO (WP 12188).

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SQNP E-2 Unit 1 or 2 Page 1 of 4 Rev. 1 FAULTED STEAM GENERATOR ISOLATION A. PURPOSE

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This guideline provides s

actions to identify and isolate a faulted S/G.

B. SYMPTOMS

1. S/G press 100 psi lower in one S/G than the oihers
2. Any S/G press decreasing in an uncontrolled manner

-1 C. TRANSITION FROM OTHER INSTRUCTIONS

1. E-0, Reactor Trip Or Safety Injection _ . ,

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2. E-1, Loss Of Reactor Or Secondary Coolant

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3. Foldout page

)[- 4. FR-S.1, Response To Nuclear Power Generation /ATWS ~

p s. FR-z.1, Response To High Containment Pressure L:

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SQNP E-2 . Unit 1 or 2 Page 2 of 4

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.I FAULTED STEAM GENERATOR ISOLATION

. k, STEP ACTION / EXPECTED ' RESPONSE . RESPONSE NOT OBTAINED r.

1 Identify Faulted.S/G IF faulted S/G can NOT be

a. . Any S/G press decreasing Identified, THEN: -

'in an uncontrolled manner

b. Check S/G enclosure Press in one S/G' lower temp T1002A and than the others T1003A Search.for break in

- main 'steamlines, main feedlines, and other secondary piping IF faulted S/G NOT identified, .

THEN:  !

-> AFTER all S/G narrow

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range levels > 25%,

THEN close all MSIVs, MSIV bypasses, and isolate all AFW Check for uncontroHed decrease in S/G press or level to identify faulted S/G l IF faulted S/G NOT iifentified, THEN go to step 3 4

SQNP i- E-2 Unit 1 or 2

l. Page 3 of 4 L -,

Rev. 2 -

-FAULTED STEAM GENERATOR ISOLATION .

STEP. ACTION / EXPECTED RESPONSE. RESPONSE NOT OBTAINED i

CAUTION: At least one S/G must be maintained available for RCS cooldown.

CAUTION: The pressure difference between the RCS and the faulted S/G should be maintained less than 1600 psid.

1 2 Isolate Faulted S/G  !

a. Close faulted S/G MSIV and . a. I_F MSIV or bypass MSIV bypass. can NOT be closed,

,, THEM cTose:

1) Intact S/G MSIVs and bypasses
2) HP steam to MSRs and MFW pump turbine  !
3) Condenser steam -

dumps *

4) Steam seals
b. Close AFW
c. Ensure main FW - ISOLATED
d. Ensure S/G PORV - CLOSED d. Locally,close S/G PORV from 480-V SD Bd Rm (S/Gs 1 and 4) or annulus (S/Gs 2 and 3)
e. Ensure blowdown - CLOSED
f. Ensure turbine - driven f. IF both S/G 1 and 4 ~

AFW pump being supplied Taulted, from intact S/G THEN verify at least one motor-driven AFW

  • pump aligned to an intact S/G, g THEN stop turbine -

driven AFW pump

{k SQNP E-2 Unit 1 or 2 Page 4 of 4 Rev. 2 j FAULTED STEAM GENERATOR ISOLATION

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. I STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION: Any faulted S/G or secondary break should remain isolated during subsequent recovery actions unless needed for RCS cooldown.

3 Check Secondary Side IF secondary side radiation Radiation - 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 37G blowdown monitors

- NOT available, THEN:

Notify Rad Con to l survey main steamlines and S/G blowdown lines

,, Notify chem lab to sample S/G activity l

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Check RM-90-124 Aux Bldg 690 4 Go To E-1, Loss Of Reactor Or Secondary Coolant j

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