ML20237H770

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Rev 2 to Emergency Instruction E-1, Loss of Reactor or Secondary Coolant
ML20237H770
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 06/12/1987
From: Strickland G, Terpstra G, Jacqwan Walker
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20237H133 List: ... further results
References
E-1, NUDOCS 8708170351
Download: ML20237H770 (15)
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Text

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.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 L- "

SUBMITTED BY k k .IA nh an_

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

=(

w TI-66.1: this constitutes a biennial review.

The last page of this instruction is number: 13

" 8708170351 870811 PDR ADDCM 05000327 P PDR. ,t _ _ _ _ . . . _

. _ _ _ _ . ___________1

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,. - 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 1 Revised to add transition from other 1,9, instructions; to reword step for clari-1 08/21/85 10,11 fication.

Revised to make minor procedure enhance-I' 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 2 JUN 1 2 Ic87 All constitutes a biennial review.

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I, SQNP-'

,E-1 Unit 1 or 2 Page 1 of 12 p Rev. 2

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f, 1 x - -

9 LOSS OF REACTOR OR SECONDARY COOLANT- _

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
e. Pzr PORV open and block valve cannot be closed
f. '
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. .ES-0.2, SI Termination
3. E-2, Faulted Steam Generator Isolation
4. Foldout page
5. ECA-0.2, Recovery From Loss Of All AC Power With SI Required

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l~' SQNP

'E-1 Unit 1 or 2

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.. Page 2 of 12 Rev. 2 j

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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 3 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 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

1) VerEy at least one CCP O_R SI Pump running

, , . THEN stop all RCPs

2) Perform steps a.1 to a.3 in column above EMERPR/E aac
g{l - .SQNP

.. 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

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b. S/C b' wdown monitors IF condenser exhaust and f 57G blowdown monitors 1 NOT available, l TIllfN:

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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 Aux Bldg 690

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' SQNP' E-1 Unit 1 or 2

. Page 4 of 12 l 7 Rev. 2 1

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1 x LOSS OF REACTOR OR SECONDARY COOLANT -

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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

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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 C

a. CST level > 3 ft a. IF CST level < 3 ft, 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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s-SQNP ,

E-1 Unit 1 or 2 Page 5 of 12 e

Rev. 2

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A,- s LOSS OF REACTOR OR SECONDARY COOLANT ' ' !

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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
c. Place Cntmt Spray Pumps in standby I.. -

9 Check If Cntmt Vacuum Control l "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.

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t f SQNP 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,

1) RCS press > 180 psig THEN establish CCS

' to RHR heat exchanger.

  • 2) RCS press - STABLE Go 'to next step OR INCREASING
b. Reset SI b. Check P-4 interlock with SI reset, SI-268 1 c. Stop. RHR Pumps and place in standby L
1. .

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F-t EMERPR/E aaC L .

SQNP E-1 Unit 1 or 2

, Page 7 of 12

[ Rev. 2

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LOSS OF REACTOR OR SECONDARY COOLANT -

STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBT INED 11 Check If UHI Should Be Isolated IF UHI injected, l 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 l

. a. All shutdown boards energized a. Attempt to restore l by offsite power offsite power per AOI-35 l

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

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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 '

STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBT INED l .. 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,

' THEN do not . terminate ~

b. ~ RCS presss - STABLE -

SI. Go to step 15.

I-. OR INCREASING

c. Secondary heat: sink

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1) . Total AFW flow to '

intact S/Gs > 440 gpm 1 OR .

)3, 2) Narrow range level  ;

in at least one intact

  1. . 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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EMERPR/E I aac

{ SQNP l E-1 Unit 1 or'2 l

' Page 9 of 12 )

Rev. 2 j i, g. t I

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e.c LOSS 'OF REACTOR OR SECONDARY COOLANT

  • i 1

STEP ACTION / EXPECTED RESPONSE ~'

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 L I 16 Energize Hydrogen Ignitors

3 a. Pnl M-10

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17 Place Cntmt Hydrogen Analyzers In Service

/' a. Refer to SOI-43.1 18 Continue Recovery Based On Event

a. IF a loss of a. IF LOCA in progress, a secondary coolant THEN go to next step g is in progress WITH NO - LOCA:
1) S/G press - LOW OR DECREASING
2) Cntmt radiation -

NORMAL '

THEN return to step 1

\ and repeat the previous L

steps until plant conditions allow transition to another instruction y

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EMERPR/E aac -

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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 a.

BUT do not stop any ECCS 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

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22 Start Post Accident Sampling

'lt a. Notify chem lab to start TI-66.1, Post Accident Sampling And Analysis Methods 23 Evaluate Plant Equipment j

a. Check system status i per Appendix A I e

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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

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l STEP- ACTION / EXPECTED RESPONSE RESPONSE-N'OT OBTdINED -

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'< 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 m 27 Depressurize S/Gs To RCS Press
a. Check S/G radiation - a. Do not dump steam  ;

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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

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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,

4 28 Prepare For Switchover To 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 u Plant Status '

( a. Consult TSC I.

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<- - END -

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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 s ,
8. ECCS Re, circulation Availability t- ~
9. Emergency Gas Treatment System
10. Auxiliary Building Gas Treatment System
11. Cntmt Isolation Systems (Refer to SOI-88.1A, SOI-88.1B , and SOI-88.1C.)

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