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

% s1 TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT

' EMERGENCY INSTRUCTION ES-0.1 REACTOR TRIP RESPONSE Revision]

s PREPARED BY:

G. Strickland RESPONSIBLE SECTION: Operations-REVISED BY:

G. L. Terpstra SUBMITTED BY:

.1/

n_

g,podsibleSectionSupervisor

~

Jujl 151987 PORC REVIEW DATE:

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

'4 L

8708170328 870811y7 DR ADOCK O

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; lU N 15108~/

step 11:. revised P-6 setpoint to < 10-'

amps; I

3,6.7,12 and step 20:

revised SI-407 to SI-407.2.

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L 1421C/ jaw 1

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SQNP

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ES-0.1 Unit 1 or 2 Page 1 of 13 Rev. 0 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

1 s

1 i

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a SQNP ES-0.1 Unit 1 or 2 Page 2 of 13 -

1Rev. 0 REACTOR TRIP RESPONSE

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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 l(f REACTOR TRIP RESPONSE 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

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 i 1 I

SQNP 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:

(

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:

a.

Verify one charging pump.

[

y 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

~~

10 Check Cntmt Conditions -NORMAL

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~~

a.

Press b.

Radiation c.

Temp

^

b-

  • l

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SQNP ES-0.1 Unit 1 or 2

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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 Check intermediate range a.

a.

WHEN intermediate

-10

-10 flux range < 10 amps flux < 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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SQNP ES-0.1 Unit 1 or 2 Page 8 of 13 Rev. O I

REACTOR TRIP RESPONSE

(

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

1 u

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SQNP 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 Bearing, oil pumps a.

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

9 I

SQNP 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 S/G with low press l

i _ _ _ _ _ _ - _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _

g SQNP 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

C '

1

i SQNP ES-0.1 Unit 1 or 2 l

Page 13 of 13

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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 I

b4 GOI-2, Plant Startup

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From Hot Standby To Minimum Load c.

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

- END -..

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