ML20205B040
| ML20205B040 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Haddam Neck, 05000000 |
| Issue date: | 06/15/1988 |
| From: | CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | |
| Shared Package | |
| ML20204H467 | List:
|
| References | |
| EOP-35-E, EOP-35-E-0, NUDOCS 8810260170 | |
| Download: ML20205B040 (16) | |
Text
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[
STATION PROCEDURE COVER SHT A.
IDENTIFICATION
'i Number: E0P 35'E-0 Rev., 2
Title:
REACTOR TRIP OR St.FETY INJECTION I
Prepared By: H.
K. COVIN B.
REVIEW I have reviewed the above procedure and have found it to be satisfactory.
TITLE SIGNATURE DATE DEPARTMENT HEAD
(,
/ P fr y-C.
' SPECIFIC UNREVIEWED SAFETY QUESTION EVALUATION REQUIRED:
Modifies intent of procedure and changes operation of systems as described in design documents.
YES [ ]
NO [-T (If yes, perform written USQ determination and Safety Evaluation, and contact Manager, Safety Analysis Branch to determine need for Integrated Safety Evaluation.)
ENVIRONMENTAL REVIEW REQUIRED (Adverse environmental impact),
YES [ ]
NO [v[
D.
SPECIFIC SAFETY EVALUATION REQUIRED Affects response of safety systems, performance of systems which may have been credited in the safety. analysis or non-credited systems which may indirectly affect safety system response.
YES [ ]
NO [ [
(If yes, perform written Safety Evaluation and contact Manager, Safety Analysis Branch to determine need for Integrated Safety Evaluation.)
E.
INTEGRATED SAFETY EVALUATION REQUIRE 0 YES [ ]
NO ((
F.
PROCEDURF REQUIRES h/SORCREVIEW (In addition to revTew, iteps-with a YES response mustbedocumentedinthel{0RC/$0RCmeetingminutes.)
YES[4 NO [ ]
G.
/SORC APPROVAL
/50RC Meeting Number _ % g 7-2 d 7 H.
APPROVAL AND IMPLEMENTATION The attached procedure is hereby approved, and c' factive on the date below:
g = /J * [f
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" Station / Service / Unit Superintendent Effective Date SF301/9/s/SES/87-12/lof1 88IO260I70 881007 DR p
ADOCK 05000D13 PDR
I i.
f E0P 35 E-0 Page 1 Rev. 2
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REACTOR TRIP OR SAFETY INJECTION 1
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Eff. Rev.
1-15 2
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E0P 35 E-0 Page 2 SAFETY. INJECTION Rev. 2 s
A.
PURPOSE This procedure provides actions to verify proper response of the automatic protection systems following manual or automatic actuation of a reactor trip or safety injection, to assess plant conditions, and to identify the appropriate recovery procedure.
l B.
ENTRY CONDITIONS This procedure is applicable to Modes 1, 2, and 3 when SI is not blocked.
Using this procedure when not in these modes requirer. a step by step evaluation to determine if the required action is still applicable to current plant conditions.
1.
The following are symptoms that require a reactor trip, if one has not occurred.
a.
PR Flux Hi 109% (2/4) b.
PR. Flux Hi 25% (2/4) c.
PR Flux Rate Hi
+5%/second'(2/4)
-5%/second (2/4) d.
IR Flux Hi 25% (1/2)
O e.
SR Flux Hi 105 CPS (1/2) f.
OTAT 108% 1 penalties (2/4)
I g.
OP6T 109%
penalties (2/4) h.
PZR Level Hi 89% (2/3) i.
PZR Press Hi 2385 psia (2/4)
J.
PZR Press to 1900 psia (2/4) k.
SG Level Lo-Lo 23.5% (2/4) 1.
One Loop Flow Low 90% (2/3) m.
Two Loop Flow Low 90% (2/3) n.
Turbine Trip Turb Stop Valves Closed (4/4) l ETS Press <500 psig (2/3)
{
o.
SSPS Gen Warning Train A and B p.
RCP Low Shaft Speed 97.8% (2/4) q.
SI Actuated 2.
The following are symptoms of a reactor trip Any reactor trip annunciator lit.
a.
j b.
Rapid decrease in neutron level indicated by nuclear I
instrumentation.
c.
All shutdown control rods are fully inserted.
Rod bottom lights l
are lit.
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I REACTOR TRIP OR FOP 35 E-0 Page 3 SAFETY INJECTION Fev. 2 mU 3.
The following are symptoms that require a reactor trip and safety injection, if one has not occurred a.
PZR Press Lo 1892 psia (2/4) b.
Ctmt Press Hi 17.7 psia (2/3) c.
Steam Line Press Lo 658.6 psig (2/3) 4.
The following are symptoms of a reactor trip and safety injection a.
Any SI annunciator lit.
b.
SI pumps running.
c.
Group II ESF Status lit.
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OPS 064 2 3 44 I
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i REACTOR TRIP OR E0P 35 E-0 Page 4
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SAFETY INJECTION Rev. 2 i
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l ns STEP ACTION / EXPECTED RESPONSE RESPONbf NOT OBTAINED NOTE 1.
Foldout page should be open.
2.
Adverse Containment is defined as 8
1 180 F or 1 10 R/hr in containment.
This definition applies to this and all subsequent E0Ps.
___1*
Verify Reactor Trip Manually trip reactor.
IF reactor will NOT trip, THEN
___a.
Reactor trip and go to E0P 35 FR-S.1, bypass breakers - OPEN RESPONSE TO NUCLEAR POWER GENERATION /ATWS, Step 1.
___b.
Digital Rod position indicators - AT ZERO c.
Neutron Flux - DECREASING
___2*
Verify Turbine Trip All turbine Main'Stop a.
Manually trip turbine.
a.
Valves - CLOSED IF turbine will NOT 7-,
(
)
trip, then manually,run
\\/
back turbine.
IF turbine can NOT be runback, THEN CLOSE Main Steam Isolation Valves and Main Steam Isolation Bypass Valves.
___3*
Verify Power to AC Emergency Busses a.
Bus 34C or 34D -
a.
Try to restore power to AT LEAST ONE at least one ac emergency ENERGIZED bus.
IF power can NOT be restored to at least one ac emergency bus, THEN go to E0P 35 ECA-0.0, LOSS OF ALL AC POWER, Step 1.
b.
Bus 34C and 34D -
b.
Try to restore power to BOTH ENERGIZED deenergized ac emergency bus.
___4*
Check If SI Is Actuated Check if SI is required.
If SI is required, THEN a.
Group II ESF status manually actuate.
IF SI lights - LIT is NOT required, THEN go to E0P 35 ES-0.1, REACTOR 73
(
).
b.
SI Actuation TRIP RESPONSE, Step 1.
\\- /
annunctator - LIT cvma su
REACTOR TRIP OR E0P 35 E-0 Page 5 SAFETY INJECTION Rev. 2 i
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STEP ACTION /EXPECTt O RESPONSE RESPONSE NOT OBTAINED
_ 5*
Verify Service Wacer Pumps -
RUNNING a.
Service Water <tmp a.
Manually start pump A or C.
A or C - RUNNING b.
Service Water Pump b.
Manually start pump B or D.
B or D - RUNNING
_ 6*
Verify Two RPCCW Pumps - RUNNING Manually start pump (s).
_ 7*
Verify Containment Isolation Phase A a.
Phale A valves -
a.
Manually actuate Phase A C1.0 SED (ESF Group II OR manually close valves.
Status columns 2-10) b.
TRAIN A & B RPCCW b.
Manually open valves.
Supply and Return to Chill Water - OPEN
/'
u (V')
_ 8*
Verify proper ESF Status Panel Indications a.
Verify ESF Group 1 a.
Manually operate lights - 0FF component (s),
b.
Verify ESF Group 2 b.
Manually operate lights - LIT component (s).
_ 9*
Verify ECCS Pumps Running Manually start pump (s).
a.
Two Charging pumps a.
RUNNING b.
Safety injection b.
Manually start pump (s),
pumps - RUNNING c.
RilR pumps - RUNNING c.
Manually start pump (s).
_ 10*
Verif y AFW Pumps Running Manually start pumps.
a.
MD pumps - RUNNING a.
b.
Turbine-driven pump -
b.
Manually open steam supply l
RUNNING, IF NECESSARY valves.
v oPW41 3 84 l
REACTOR TRIP OR E0P 35 E-0 Page 6
/__
SAFETY INJECTION Rev. 2 s
)
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
_ 11*
Verify FW Isolation Manually close valves as
.iec e s s a ry,
-a.
FW Flow Control valves - CLOSED
_ b.
FW Bypass Level Control valves -
CLOSED c.
Feed Line Trip valves - CLOSED
-d.
SG Blowdown Ctmt Isolation Valves -
CLOSED
_ e.
SG Blowdown Sample Isolation valves -
CLOSED
~12*
Check If Main Steat.ltnes Should be Isolated V
a.
Ctmt Press above 17.7 a.
Go to Step 13.
< 660 psig b.
Verify main steamline b.
Manually close valves.
isolation and bypass valves - CLOSED
_ 13*
Verify Containment Spray Not Required a.
Containment Pressure a.
Perform the following
< 22.7 psia
- 1) Verify quench spray initiated.
IF NOT,
-AND-TilEN manually initiate.
.0_T initiated 1
- 2) Verify containment isolation Phase B valves closed.
IF NOT, TilEN manually close valves.
- 3) Stop all RCPs.
(Gv)
- 4) Go to step 15.
C%Mi 3 44
REACTOR TRIP OF E0P 35 E-0 Page 7 SAFETY INJECTION Rev. 2
(
)
x_-
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OSTAINED 2 14*
Verify Containment Air Recirculation - RUh3ING IN EMERGENCY MODE a.
Verify two Ctmt Air a.
Manually start two Ctmt Recirculation Fans -
Air Recirculation fans.
RLS3ING b.
Verify RPCCW Ctmt b.
Manually open valves.
Supply / Return Header Isolations - OPEN
_ 15 Verify the following plant status:
a.
SLCRS doors - CLOSED.
a.
Have Security close all SLCRS doors which are not closed.
b.
IF a Control Building Isolation has occurred, THEN dog the Control s
'v-)
Room doors.
_ 16 Verify ECCS Flow
_a.
Charging pump flow a.
Manually start pumps and indicators - CHECK align valves.
FOR FLOW Consistant with RCS Pressure
_ b.
RCS pressure b.
Go to Step 17.
1635 psia (1905 psia
(
for adverse containment)
_ c.
liigh Pressure SI pump c.
Manually start pumps and
. flow indicators -
align valves.
CllECK FOR FLOW Consistant with RCS Pressure
_d.
RCS pressure d.
Go to Step 17
< 300 psia (450 psia for adverse containment)
_e RHR pump flow indicators e.
Manually start pumps and CllECK FOR FLOW align valves.
C\\
oPFM 1 3-84
REACTOR TRIP Oh E0P 35 E-0 Page 8 SAFETY INJECTION Rev. 2 N
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STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
___17 Verify Total A1W Flow IF SG narrow range level > 4%
4 525 GPM.
(34% FOR ADVERSE CONTAINMENT) in any SG, TREN control feed flow to maintain narrow range level.
IF narrow range level < 4%
(34% FOR ADVEhoE CONTAINMENT) in all~SG's, TliEN manually start pumps and align valves as necessary.
IF AFW flow
> 525 gpm can NOT be established, ThEN go to E0P 35 FR ti.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, Step 1.
Manually align valves as
___18 Verify AFW Valve Alignment PROPER EMERGENCY ALIGNMENT necessary.
Manually align valves as
___19 Verify SI Valve Alignment PROPER EMERGENCY ALIGNMENT necessary.
fv A
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l REACTOR TRIP OR E0P 35 E-0 Page 9 SAFETY INJECTION Rev. 2
'wJ STEP ACTICH4/ EXPECTED RESPONSE RESPONSE NOT OBTAINED
___20 Check RCS Average Temperature -
IF temperature < 557'F STABLE AT OR TRENDING TO 557 F and decreasing, TifEN a.
Stop dumping steam, b.
IF cooldown continues, THEN control total feed flow.
Maintain total feed flow >
525 gpm until narrow range level > 4% (34% for adverse containment) in at least one SG.
c.
IF cooldown continues, TifEN close main steamline isolation and bypass valves.
IF temperature > 557*F and increasing, THEN 1)
Dump steam to condenser
-OR-v 2)
Dump steam to atmosphere.
___21 Check PZR PORVs and Spray Valves a.
PORVs - CLOSED a.
1F PZR pressure < 2350 psis, TiiEN manually close PORVs.
IF any valve can M be closed. THEN manually close its block valve.
IF block valve can hy be closed, THEN go to E0P 35 E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.
b.
IF PZR pressure < 2275 h.
Normal PZR spray valves CLOSED psia, THEN raanually close valves.
IF valves 'can NOT be r losed, TiiEN stop RCP(s) supplying tailed spray valve (s).
O O PS&4. t 3 84
REACTOR TRIP OR E0P 35 E-0 Page 10 y;_
SAFETY INJECTION Rev. 2
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STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OSTAINED NOTE Seal injection flow should be maintained to all RCPs.
_ 22 Check If RCPs Should Be Stopped a.
Charging or Safety a.
Go to Step 23.
Injection Pumps - AT LEAST ONE RUNNING b.
Verify RCS Press b.
Go to Step 23.
< 1435 psia (1700 psia FOR ADVERSE CTt!T) c.
Stop all RCPs
,__2 3 Check If SGs Are Not Faulted a.
Go to E0P 35 E-2, FAULTED a.
Check pressures in all SGs STEA?! GENERATOR ISOLATION, Step 1.
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- 1) NO SG PRESSURE DECREASING IN AN UNCONTROLLED ttANNER
- 2) NO SG C0tlPLETELY DEPRESSURIZED
~24 Check if SG Tubes Are Not Go to E0P 35 E-3, STEAll Ruptured GENERATOR TUBE RUPTURE, Step 1.
a.
Steam Line Radiation -
NORftAL b.
Conddnser air ejector radiation - NOR!!AL c.
SG blowdown radiation -
NOR!!AL d.
IF the radiation monitoring computer is j
NOT available, TilEN have an ItP technician manually determine main steam line ra d ia t i o n-NORt!AL.
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PIACTOR TRIP OR E0P 35 E-0 Page 11
/-
SAFETY INJECTION Rev. 2
(
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STEP ACTION / EXPECTED RESPONSE RESPONSE NOT O8TAINED
_ 25 Check if RCS Is Intact Go to E0P 35 E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.
a.
Containment radiation -
NORt!AL b.
Containment Pressure -
NORMAL c.
Containment recirculation sump level - NORMAL
_ 26 Check If SI Flow Should Be Reduced a.
RCS subcooling based on a.
DO NOT STOP SI PUtiPS.
Go core exit TCs > 30 F to Step 28.
b.
Secondary heat sink b.
E neither condition satisfied, THEN DO NOT
!) Total feed flow to SGs STOP SI'PUr!PS. Go to
> 525 GPr!
Step 28.
es
(
-OR-
- 2) Narrow range level in at least one SG > 47, c.
DO NOT STOP S1 PUt!PS.
Go INCREASING to Step 28.
d.
PZR level > 77.
it.
DO NOT STOP S1 PUt!PS.
Try to stabilize RCS pressure with normal PZR spray. Return to Step 26a.
_ 27 GO to E0P 35 ES-1.1, S1 TER?l! NATION, Step 1
_ 28 initiate ttonitoring of the Following Critical Safety function a.
Status Trees b.
Abnormal control board annunctators - REl'URTED TO THE SS
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REACTOR TRIP OR E0P 35 E-0 Page 12 SAFETY INJECTION Rev. 2 l'._')
LJ STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION Shift AFV pump suction to the CST if DWST level decreases to < 80,000 gal.
___29 Check SG Levels a.
Narrow range level a.
Maintain total feed
> 4%
flow > 525 gpm until narrow range level > 4% in at least one SG.
b.
Control feed flow to b.
IF narrow range level in maintain narrow range level any SG continues to increase between 4% and 50%
in an uncontrolled manner, TH_EN go to E0P 35 E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
___30 Check Secondary Radiation GO to E0P 35 E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
a.
Computer Indications-NORE\\L
-OR-b.
If the radiation monitoring computer is NOT available, TilEN have an lip technician manually determine main steam line radiation indications-NORMAL.
_ 31 Check Auxi? iary and ESF Evaluate cause of abnormal Puildings for Radiation conditions.
IF the cause is NORMA L a loss of RCS inventory outside containment. Tl!EN go to E0P 35 ECA-1.2, LOCA OUTSIDE CONTAINMENT, Step 1.
C PWA. I 3 44
t' REACTOR TRIP OR E0P 35 E-0 Page 13 SAFETY INJECTION Rev. 2 L
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v STEP ACTION / EXPECTED RF.SPONSE RESPONSE NOT OBTAINED
___32 Check PRT Conditions - NORMAL Evaluate cause of abnormal conditions.
a.
PRT Temp < 115 F b.
PRT Level - 65% to 80%
c.
PRT Press - 3 to 6 psig CAUTION If offsite power is lost af ter SI reset, manual action may be required to restart safeguards equipment.
___33 Reset SI a.
SI Actuation Block Reset Train A - RESET
[)
b.
SI Actuation Block Reset
\\- /
Train B - RESET
___34 Reset Containment Isolation Phase A and Phase B
___35 Instrument Air To Containment Establish Instrument Air to
- ESTABLISilED Containment 1.
One instrument air compressor - RUNNING 2.
OPEN Instrument Air Containment 1. solation valves n
V 6Lxe., 3..
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REACTOR TRIP OR E0P 35 E-0 Page 14 SAf t.fY INJECTION Rev. 2 i
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STFP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION RCS pressure should be monitored.
IF RCS pressure decreases to < 300 psia the RER pumps raust be manually restarted to supply l
water to the RCS.
_ 36 Check If RllR Pumps Should Be Stopped a.
Check RCS pressure
- 1) Pressure > 300 psia
- 1) Go to E0P 35 E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.
- 2) Pressure - STABLE OR
- 2) Go to Step 37.
INCREASING b.
Stop R){R pumps and place in AUTO.
_ 37 Check If Diesel Generators Should Be Stopped a
Verify Bus 34C and 34D -
3 Try to restore offsite ENERGIZED BY OFFSITE power to Bus 34C and 34D.
POWER E offsite power can ? jot be restored. THEN load the following equipment on ac emergency busses.
- 1) Instrument Air Compressor
- 2) Spent Fuel Pool Cooling Pump
- 3) P%R Backup l{ eaters
- 4) Fuel Bldg Exhaust Fan
- 5) Energize !!CC 32-3T and verify it is supplying Inverter t>.
l b.
RESET any LOP, SIS, or CDA signal at flH2.
n m
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REACTOR TRIP OR E0P 35 E-0 Page 15 SAFETY INJECTION Rev. 2 I
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STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED l
c.
Stop any unloaded diesel generator and place in standby.
d.
RESET Station LOP at both Sequencer panels.
e.
RESET, then turn ON each Diesel Sequencer Automatic Tester toggle switch.
f.
CLOSE Feeder Breakers to Emergency Generator Distribution Panels 32GS*PNLIA at 32-1T-3H
.snd 3EGS*PNLIB at 32-1U-311.
_ 38 Return to Step 20.
-FINAL-v t v 1
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