ML20237H726

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Rev 1 to Emergency Instruction ES-O.1, Reactor Trip Response
ML20237H726
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 06/15/1987
From: Strickland G, Terpstra G
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20237H133 List: ... further results
References
ES-.1, ES-0.1, NUDOCS 8708170328
Download: ML20237H726 (15)
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Text

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. TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT

' EMERGENCY INSTRUCTION .

ES-0.1 REACTOR TRIP RESPONSE s Revision]

, PREPARED BY: G. Strickland .

RESPONSIBLE SECTION: Operations-REVISED BY: G. L. Terpstra SUBMITTED BY: , .1/

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g,podsibleSectionSupervisor PORC REVIEW DATE: Jujl 151987 APPROVED BY:

PlantManager

~DATE APPROVED:

Reason for revision (include all Instruction Change Form Nos.):

Revised to step 4: add transition to FR-H.1 for loss of all FH; step 9:

delete letdown flow established due to conf 11ct with Writers Guide; step 11:

revised P-6 setpoint to'< 10- amps; and step 20: revised SI-407 to SI-407.2.

_The last page of this instruction is number: 13

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8708170328 870811 DR ADOCK O y7

SEQUOYAH NUCLEAR PLANT I

PLANT INSTRUCTION REVISION LOG l- .

EMERGENCY INSTRUCTION ES-0.1 -

REVISION Date Pages REASON FOR REVISICN (INCLUDE COMMITMENTS AND ~

LEVEL Approved Affected ALL ICF FORM NUMBERS) 0 10/04/84 All Revised to step 4: add transition to FR-H.1 for loss of all FW; step 9: delete letdown flow s established due to cor.flict with kriters Guide; step 11: . revised P-6 setpoint to < 10-' amps; lU N 1 5108~/

I 3,6.7,12 and step 20: revised SI-407 to SI-407.2.

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,, ES-0.1 Unit 1 or 2 l Page 1 of 13

- l Rev. 0 l

1 j((- I REACTOR TRIP RESPONSE 3

A. PURPOSE This guideline provides the necessary iristructions to stabilize and control the plant following a reactor trip without a safety injection.

B. SYMPTOMS

1. Any reactor trip annunciator lit
2. Rapid decrease in neutron level indicated by nuclear instrumentation i
3. All control rods fully inserted. Rod bottom lights lit.
4. Rapid decrease in unit load to zero power.

C. TRANSITION FROM OTHER INSTRUCTIONS -

E-0, Reactor Trip or Safety Injection l

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' ' , ._ , ES-0.1 Unit 1 or 2 Page 2 of 13 -

1Rev. 0 REACTOR TRIP RESPONSE ' ~

STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTkINED CAUTION: If SI actuation occurs,- then E-0, Reactor Trip Or -

Safety Injection, should be used. _ ,,

s.

1 Verify ' All Control Rods Fully IF any control rod NOT Inserted fully inserted, THEN' emergency borate

a. Rod bottom lights ' ON 350 gal for each rod not fully inserted
b. RPIs at 0 STEPS "
c. Announce reactor trip 2 Check T-avg a, T-avg < 547 F a. IF T-avg > 547 F, -

THEN verify steam dumps O_R S/G PORVs open

b. T-avg - STABLE AND b. 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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, SQNP ES-0.1 Unit 1 or 2 Page 3 of 13

, Rev. 1 4

REACTOR TRIP RESPONSE 9

w STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 3 Verify MFW Isolation

a. MFW isolation valves - CLOSED -
b. MFW reg valves - CLOSED
c. MFW bypass valves - CLOSED
d. MFW pumps - TRIPPED 4 Verify AFW Status .. Establish at least one AFW pump operation and AFW
a. AFW Pumps - RUNNING flow or MFW
b. AFW level control valves IF AFW or MFW flow can in AUTO ITOT be established,

{' ) THEN go to

  • FR-H.1, j3 ) c .* IF S/G level < 33%, RESPONSE TO LOSS OF THEN verify AFW flow SECONDARY HEAT SINK
d. S/G blowdown valves - CLOSED 5 Check S/G Levels
a. Narrw range S/G a. Verify AFW flow and levels > 25% S/G levels returning to normal program
b. Control S/G levels between 25% and 50%

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SQNP ES-0.1 Unit 1 or 2 Page 4 of 13 Rev. O REACTOR TRIP RESPONSE l(f .

STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 6 Check RCS Press

a. Press > 1870 psig a. IF RCS press < 1870 ,,,

psig, t TIIEN actuate SI. Go to

b. Press < 2235 psig b. IF RCS press > 2235 '

psig, ,

THEN: (

1) Verify pzr heaters off
2) Control press using normal pzr sprays,

, aux spray with letdown, or one pzr PORV in this preferred order

c. Press trending to 2235 psig c. IF RCS press decreasing, THEN:
1) VerHy pzr PORV or  !

block valve closed

2) Verify normal pzr sprays closed or stop RCP supplying failed spray valve
3) VerHy aux spray valve closed
4) Turn on pzr heaters as necessary l i

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,, ES-0.1 Unit 1 or 2 Page 5 of 13 Rev. O e~

REACTOR TRIP RESPONSE STEP ACTION / EXPECTED RESPNSE RESPONSE NOT OBTAINED 7 Check Pzr Level

a. Level > 17% a. IF pzr level < 17%,

THEN:

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1) Verify letdown isolation
2) Verify pzr heaters off
3) Restore pzr level

> 17%

4) WHEN pzr level

> 17%,

THEN turn on pzr j heaters as necessary I

b. Level trending to 25%

8 Check Charging In Service IF charging isolated, THEN establish charging

a. Charging flow established a. Close FCV-62-89
b. Open charging line isolation FCV-62-90 and 91
c. Open FCV-62-85 or 86
d. Adjust FCV-62-89 and 93 to establish following:
1) Seal injection floiv 8 gpm per RCP
2) Pzr level s 25% and stable
e. Open seal water return FCV-62-61 and 63

... ..SQNP

. '. ES-0.1 Unit 1 or 2 Page 6. of 13

.. Rev. 1

... REACTOR TRIP RESPONSE

-STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 9 Check Letdown In Service WHEN pzr level > 17%,

THEN establish letdown:

y a. Verify one charging pump. [

running

b. Open letdown isolation

. valves:

1) FCV-62-69

- 2) FCV-62-70

3) FCV-62-77

, c. Adjust letdown press controller FCV-62-81 j *

~25% open and in manual

d. Open an orifice valve
e. Adjust FCV-62-81 for desired press, then place in AUTO
1) 320 psig at normal letdown temp

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10 Check Cntmt Conditions -NORMAL

a. Press
b. Radiation  !
c. Temp ^

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ES-0.1 Unit 1 or 2 Page 7 of 13 Rev. 1

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REACTOR TRIP RESPONSE STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED ,

j 11 Check If Source Range Detectors Should Be Energized

a. Check intermediate range a. WHEN intermediate flux range < 10 -10 amps flux < 10 -10 amps, THEN ensure source

~

range detectors - "

energized

b. Ensure source range detectors energized ,
c. Transfer NR-45 to one source and intermediate range

) 12 _C_ heck Offsite Power

a. Au shutdown boards a. Attempt to restore energized by offsite power offsite power per AOI-35 O =%

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,, ES-0.1 Unit 1 or 2 Page 8 of 13 Rev. O I

REACTOR TRIP RESPONSE -

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STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION: Normal T-avg indication and associated interlocks will be inaccurate during natural circulation or ...

when RCS temp is below 530 F.

s 13 Check RCP Status

a. At least one RCP running a. Attempt to restart an RCP (loop 2 preferred) per SOI-68.2 IF an RCP can NOT be started, THEN verify natural circulation RCS subcooling

[l(

l S/G press stable or decreasing i T-hot stable or l decreasing 1

Core exit T/C stable or decreasing T-cold at saturation temp for S/G press IF natural circulation NOT verified, TilEN increase dumping steam l

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'.. ES-0.1 Unit 1 or 2 Page 9 of 13 Rev. O REACTOR TRIP RESPONSE -

l STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED l l

14 Check Main Turbine

a. Bearing, oil pumps , .

running ( 1500 rpm)

b. Bearing lift pump running ( 600 rpm)
c. Place turbine on turning gear af ter shaft stops s

.e :

15 Align MSRs Normal

a. Press RESET on MSR control panel _s
b. Close HP steam to MSR

..,. , ' isolation valves

c. Open starting vents  :
d. Close operating vents 16 Shutdown Unnecessary Plant Equipment
a. Leave 2 hotwen pumps running
b. Leave 1 condensate booster pump running
c. Stop DI booster pumps
d. Stop heater drain tank -

pumps and close discharge valves

e. Open exciter field breaker I and place voltage regulator control switch in off position l

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. . , ES-0.1 Unit 1 or 2 Page 10 of 13 Rev. O REACTOR TRIP RESPONSE STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 17 Check Extraction Steam Valves And Drain Valves

a. Close heaters 1 and 2 extractiod steam valves
b. Open turbine drain valves
c. Open MFW pump turbine drain valves
d. Locally open extraction ,

drain valves, HS-5-94 18 Control S/C Press

a. Transfer condenser steam a. IF condenser NOT

, dump to press control mode Eailable, -

THEN use S/G PORVs

b. Control set + 1005 psig
c. Maintain all S/G press c. IF S/G AP > 100 psi, within 100 psi THEN verify SI actuation.

Go to

  • E-0, REACTOR
1) Avoid feeding any S/G TRIP OR SAFETY too rapidly INJECTION I
2) Divert AFW from any I S/G with low press l

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,. ES-0.1 Unit 1 or 2 Page 11 of 13 Rev. 0 REACTOR TRIP RESPONSE -

STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 19 If Available, Align MFW Normal

a. MFW pump controllers _ ,_

in manual and set to zero A

b. MFW reg valve and bypass valve controllers in manual and set to ~

zero

c. Reset MFW isolation ,
d. Restart MFW pump  !

turbine

e. Open MFW isolation valves o

, f. Control MFW pump speed f. I_F S/G level or T-avg and feedwater bypass can NOT be maintained, valve position as follows: THEN return to AFW control

1) S/G levels s 33%
2) T-avg s 547 F L _ _____-___-____

, SQNP ES-0.1 Unit 1 or 2 Page 12 of 13

. Rev. 1 REACTOR TRIP RESPONSE STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 20 Complete Surveillance And Reports

a. SI-268, Verif!. cation Of P-4 Interlock
b. SI-603, High Flux Adjustment After .

Shutdown, within 30 min after reactor trip ,

c. SI-407.2 and SI-415 if reactor power decreased by 215%
d. SI-38, Shutdown Margin

. et AI-18, file package 18 for Reactor Trip Report and NRC notification within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after reactor trip t

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.. ES-0.1 Unit 1 or 2 l Page 13 of 13 .]

Rev. 0 1 I

REACTOR TRIP RESPONSE I STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 21 Maintain Stat le Plant Conditions

a. RCS press
  • 2235 psig _ _
b. Pzr level % 25%
c. S/G narrow range levels between 25% and 50%
d. RCS T-avg N 547 F 22 Go To Applicable Plant Instruction
a. ES-0.3, Natural Circulation Cooldown

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. I b4 GOI-2, Plant Startup From Hot Standby To Minimum Load

c. GOI-3, Plant Shutdown From Minimum Load to Cold Shutdown Conditions

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