ML20237H726
| ML20237H726 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 06/15/1987 |
| From: | Strickland G, Terpstra G TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20237H133 | List:
|
| References | |
| ES-.1, ES-0.1, NUDOCS 8708170328 | |
| Download: ML20237H726 (15) | |
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
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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
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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
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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
- E-0, REACTOR TRIP OR SAFETY INJECTION 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
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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
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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 -
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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
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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.
, ' 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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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
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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
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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
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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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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
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