ML20205B052
| ML20205B052 | |
| 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-1, NUDOCS 8810260175 | |
| Download: ML20205B052 (18) | |
Text
t
)
Str. phen E.
ace 3-31-87 87-12 Form Approvad by Station Suparintendent Effective Doce_
50RC Mtg. No.
STATIbNPROCEDURECOVERSHEET j_
A.
IDENTIFICATION Number: E0P 35 E-1 Rev.
2_
Title:
LOSS OF REACTOR OR SECONDARY COOLANT
-Prepared By: H. K. COVIM B.
REVIEW I have reviewed the above procedure and have found it to be satisfactory.
TITLE SIGNATURE DATE M,
fo// CP DEPARTMENT HEAD v
C.
SPECIFIC UNREVIEVED SAFETY QUESTION EVALUATION REQUIRED:
Modifies intent of procedure and changes operation of systems as described in design documents.
YES ( )
NO ((
(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 ((
0.
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 (y (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 ( [
PROCEDURE REQUIRES h /50RC REVIEW F.
(In addition to review, item with a YES response y
must be documented in the j/SORCmeetingninutes.)
YES PT NO ( )
G.
50RC APPROVA(
SORC Meeting Number
]- 83 -/o N H.
APPROVAL AND IMPLEMENTATION The attach ur reby approved, and effective on the date below:
w
- e. n er
-station / Service / Unit Superintendent Effective Date O
SF 301 h0DOJhO Rev. 9 P
ADO Page 1 of 1 Og 3
E0P 35 E-1 Page 1 l
Rev. 2 LOSS OF REACTOR OR SECONDARY COOLANT I
PAGE NO.
EFF. REV.
1 - 16 2
Attachment A 2
l i
i 1
)
i l
.; 9 ij l
l l
I 1
i i
I l
e O
i
1 LOSS OF REACTOR OR SECONDARY COOLANT EOP 35 E-1 Page 2 Rev. 2 O
l f
A.
PURPOSE This procedure provides actions to recover f rom a loss of reactor or secondary coolant.
B.
ENTRY CONDITIONS This procedure was written for Modes 1, 2 and 3 assuming RHR is not in service. Using this procedure when not in these modes requires a step by step evaluation to determine if the required action is still applicable to current plant conditions.
This procedure is entered from 1)
E0P 35 E-0 REACTOR TRIP OR SAFETY INJECTION, Step 21, and EOP 35 FR-H.1, RESPONSE TO LOSS OF SECONDARY KEAT SIKK, Step 24, when a PZR PORV is stuck open and its block valve can not be closed.
2)
EOP 35 E-0, REACTOR TRIP OR SAFETY INJECTION, Step 25, with any of the following symptoms: high containment radiation, high containment pressure, or high containment recirculation sump level.
3)
EOP 35 E-0 REACTOR TRIP QR SAFETY INJECTION, Step 36, and EOP 35 ECA-2.1, UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS, Step 7, when RCS pressure is less than the shutoff head pressure of the low-head SI pumps.
4)
E0P 35 ES-1,1, SI TERMINATION,' Step 5, if RCS pressure decreases after stopping all but one charging pump.
5)
EOP 35 ES-1.1, SI TERMINATION, Step 11 and Step 28 and EOP 35 FR-1.2, RESPONSE TO LOW PRESSURIZER LEVEL, Step 4, if SI has to be reinitiated.
6)
E0P 35 E-2 FAULTED STEAM GENERATOR ISOLATION, Step 7, af ter identification and isolation of a faulted SG.
7)
EOF 35 ECA-0.2, LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED, Step 10, after normal injection mode conditions are established.
8)
EOP 35 ECA-1.2, LOCA OUTSIDE CONTAINMENT, Step 5, when a LOCA outside containment is isolated.
9)
E0P 35 FR-C.1, RESPONSE TO INADEQUATE CORE COOLING, Step 17 and Step 24, and E0P 35 FR-C.2, RESPONSE TO DEGRADED CORE COOLING, Step 19 after core cooling has been reestablished.
OPSMa4 3 44
LOSS OF REACTOR OR SECONDARY COOLANT E0P 35 E-1 Page 3 Rev. 0 v
- 10) E0P 35 FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, Step 1, if RCS pressure is less than all non-faulted SG(s) pressure.
- 11) E0P 35 FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, Step 24, after secondary heat sink has been reestablished and all PZR PORVs are closed.
O 1
i i
I t
I l
)
i O
OPSC64 2 3 64
t LOSS OF REACTOR OR SECONDARY COOLANT E0P 35 E-1 Page 4 Rev. 2 l
'\\
/
t,!
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT O8TAINED NOTE 1.
Foldout pa'ge should be open.
2.
Seal injection flod should be maintained to all RCPs.
1 Check If RCPs Should Be Stopped a.
Go to Step 2 RUNNING Charging OR SI b.
RCS Pressure <1435 psia b.
Go to Step 2 (1700 psia 'OR ADVERSE F
CONTAINMENT) c.
STOP all RCPs
__, _2 Check If SGs Are Not Faulted a.
Check pressures in all a.
Verify all faulted SG(s) 7-~s
(
)
SGs -
isolated v
- 1. N0 SG PRESSURE
- 1. Main Steam lines DECREASING IN AN UNCONTROLLED MANNER
- 2. Main Feed lines
- 2. NO SG COMPLETELY
- 3. Blowdown lines DEPRESSURIZED
- 4. Auxiliary Feed lines
- 5. Steam Supply and Warming valves to TD AFW pump
- 6. Main Steam low point drains
- 7. SG Atmospheric Dump valves IF NOT, THEN go to E0P 35 E-2 FAULTED STEAM GENEPdTOR ISOLATION, Step 1 O
L)
OPKt4 9 3 64
LOSS OF REACTOR OR SECONDARY COOLANT E0P 35 E-1 Page 5 Rev. 2 m _/
STEP ACTIONsEXPECTED RESPONSE RESPON5E NOT OBTAINED i
CAUTION Establish the CST as an alternate water source for the AFV pumps if DWST level decreases to <80,000 gal.
l 3
Check Intact SG Levels a.
Narrow range level a.
Maintain total feed flow
>4% (34% FOR ADVERSE
>525 gpm until narrow CONTAINMENT) range level >4% (34%
FOR ADVERSE CONTAINMENT) in at least one SG b.
Control feed flow to b.
IF narrow range level in maintain narrow range level any SG continues to between 4% (34% FOR increase in an ADVERSE CONTAINMENT) uncontrolled manner, and 50%
THEN go E0P 35 to E-3,
,- s
')
STEAM GENERATOR TUBE k- /
RUPTURE, Step 1 4
Check Secondary Radiation -
Go to E0P 35 E-3, STEAM GENERATOR NORMAL TUBE RUPTURE, Step 1 a.
Main Steamline radiation monitors b.
Condensor air ejector radiation monitor c.
Blowdown line radiation monitors d.
E the radiation monitoring computer is NOT available THEN have an llP technician manually determine main steam line radiation - NORMAL.
O oP*tA4 1 3 44
LOSS OF REACTOR OR SECONDARY COOLANT E0P 35 E-1 Page 6 Rev. 2
[
)
L,i STEF ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION IF any PZR PORV opens because of high PZR pressure, Step Sa should be repeated after pressure decreases to less than the PORV setpoint.
5 Check PZR PORVs and Block Valves a.
PORVs - CLOSED a.
E PZR pressure <2350 l
psia, THEN close PORVs.
E any valve can hy be closed, THEN close its block valve b.
Block valves - AT LEAST b.
Open one block valve ONE OPEN unless it was closed to isolate an open PORY N
e D.
O C PSCt e-1 3 84
LUSS OF REACTOR OR SECONDARY COOLANT E0P 35 E-1 Page 7 Rev. 2
((,)
v STEP
[ ACTION / EXPECTED RES/0NSE RESPONSE NCT OBTAINED 6
Check If ECCS Flow Should Be Reduced a.
P.C8 subcooling based on c.
DO NOT STOP ECCS PUMP.
core exit TCs Go to Step 8.
>30*F (90*F FOR l
ADVERSE CONTAINMENT) b.
Secondary heat sink b.
IF neither condition satisfied, THEN DO NOT Total feed flow to STOP ECCS PUMPS.
Go to intact SGs >$25 gpm Step 8 l
- OR -
Narrow range level in at least one intact SG
>4% (34% FOR ADVERSE CONTAINMENT) c.
DO NOT STOP ECCS PUMP INCREASING Go to Step 8 n
l x_,/
d.
PZR level >7.0% (50%
d.
DO NOT STOP ECCS PUMP FOR ADVERSE CONTAINMENT)
Go to Step 8 7
Go to E0P 35 ES-1,1, SI TERMINATION, Step 1 4
4 O
LOSS OF REACTOR OR SECONDARY COOLANT E0P 35 E-1 Page 8 Rev. 2
- l LJ STEP ACTION / EXPECTED RESPONSE RESPONDE NOT OBTAINED NOTE Containment recire pumps are sequenced on 660 seconds af ter a CDA.
CAUTION Do not stop containment recirc pumps used for core injection flow.
8 Check If Containment Spray Should Be Stopped a.
Spray pumps - RUNNING a.
Go to Step 9
- 1) Containment recirc spray pumps
- 2) Quench spray pumps b.
Containment pressure b.
Continue with Step 9.
<!3 psia WHEN containment pressure
< 13 p s i a, Tlfe..'i do S t ep s Sc and d c.
RESET CDA signal d.
STOP containment spray pumps and place in AUTO
- 1) STOP ouench spray pumps
- 2) STOP containment recire pumps
- 3) CLOSE CHEMICAL ADDITION ISOLATION valves if
- topping spray pumps O
o f"Vf 4 - 1 3 44 e
LOSS OF REACTOR OR SECvNDARY COOLANT E0P 35 E-1 Page 9 Rev. 2
(
)
LJ STEP ACTK)N/ EXPECTED RESPONSE RESPONSE NOT OSTAINED CAUTION 1.
If offsite power is lost af ter SI reset, operator action may be required to restart safeguards equipment.
- 2. RCS pressure should b'e monitored.. If RCS pressure decreases to <300 psia (450 psia FOR ADVERSE CONTAINMENT), the RHR pumps must be restarted to sup,aly water to the RCS.
9 Check If RER Pumps Should Be Stopped a.
Check RCS pressure
- 1) Pressure >300 psia
- 1) Go to Step 11 7s (450 psia FOR ADVERSE (v)
CONTAIN!tENi
- 2) Pressure - STABLE OR
- 2) Go to Step 10 INCREASING b.
RESET SI, if necessary c.
GTOP RHR pumps and place in AUTO 1 []
QT
_ 10 Check RCS and SG Pressures Go to Step I a.
Check Pressure in All SGs -
INCREASING OR STABLE
-exn-b.
Check RCS Pressure -
DECREASING OR STABLE i
i z,.
LOSS OF REACTOR OR SECONDARY COOLANT E0P S5 E-1 Page 10 Rev. 2
(
)
<j STEP ACTION / EXPECTED RESPONSE l
RESPONSE NOT OsTAINED 11 Check If Diesel Generators Should Be Stopped a.
Verify ac emergency a.
Try to restore offsite busses - ENERGIZED BY power to ac emergency 0FFSITE POWER busses.
IF affsite power can NOT be restored, THEN load following equipment on the ac emergency busses; as loads permit
- 1. Instrument air compressor
- 2.
- al cooling pump
.s a t s. r s
- 4. Fuel b1dg filter system
- 5. Energize MCC 32-3T' atA verifv it is
[s) supplying Inverter 6
\\- '
b.
RESET any LOP, SIS, or CDA signal at MB2 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 3EGS*PNLIA at 32-IT-3H and 3EGS*ENL1B at 32-1U-3H.
Ov ONV41 3 64
-t.
.. ~ _ _ _
l LOSS OF REACIOR OR SEC0hDARY COOLANT E0P 35 E-1 Page 11 Rev. 2 fm I
)
\\
s STEP ACTION' EXPECTED RESPONSE RESPONSE NOT OBTAINED 12 Initiate Evaluation of Plant Status Verify cold leg a.
IF cold leg recirculation a.
recirculation capability capability can NOT be verified, THEN go to
- 1) Power to containment E0P 35 ECA-1,1, LOSS OF recirculation pumps -
EMERGENCY COOLANT AVAILABLE RECIRCULATION, Step 1
- 2) Power to' valves needed for cold leg recirculation -
AVAILABLE as verified by Attachment A b.
Check ESF and Auxiliary b.
Try to identify and Building Radiation -
isolate leakage NORMAL
- 1) Particulate h,
- 2) Gaseous G
- 3) SLCRS c.
Obtain samples using post accident sampling systems
m CPDW1 3 84
\\
LOSS OF REACTOR OR SECONDARY COOLANT E0P 35 E-1 Page 12 Rev. 2 f'
i8
\\_,
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAIN2D d.
Evaluate plant equipment for contiaued long term usage can *stlities
- 1) Charging pumps
- 2) SI pumpo
- 3) Containment recirc spray pumps
- 4) AFW pumps
- 5) Containment air recirr-fans
- 6) Control room ventilation system
- 7) Reactor plant component cooling water pumps e.
Start additional plant f-~s (s_-}
equipment as needed for plant recovery recombiners -
- 1) USE containment purge
- 1) Start H2 as directed by Director system only under of Station Emergency direction of the Organization (D5EO)
Director of Station Emergency Organization (DSEO)
- 2) Water treating systems
- 3) i;adwaste systems 13 Check If RCS Cooldown And Depressurization Is Required 1
IF RHR pump flow a.
RCS pressure >;00 psia a.
(450 psia FOP. ADVERSE
>200 gpm, THEN CONTAINMENT) go to Step 14 b.
Go to E0P 35 ES-1.2, POST LOCA C00LDOWN AND DEPRESSL'RIZATION, Step 1 i
~
ONcu-t 3 44
LOSS OF REACTOR 08 SECONDARY COOLANT E0P 35 E-1 Page 13 Rev. 2
(
l
' w)
ST2P ACTION / EXPECTED RESPONSE RESPONSE NOT 087AINED 14 Check If Transfer To Cold Leg Recirculation Is Required a.
RWST level a.
Return to Step 12
<520,000 gal.
b.
Go to E0P 35 ES-1.3 TRANSFER TO COLD LEG RECIRCULATION, Step 1 15 Check If SI Accumulators Should Be Isolated.
a.
At least two RCS hot leg a.
Continue with Step 16.
temperatures <375*F WHEN at least two RCS hot leg temperatures
<375'F, TREN do Steps 15b and c.
b.
Restore power to isolation valves (32-2R-R5F, 32-2W-R3J. 32-2R-F4M, 32-2W-F4M)
[
)
\\ s_
/
c.
CLOSE all SI accumulator c.
Vent any unisolated' isolation valves, accumulators d.
Remove power from the isolation valves
(
)
1 s_-
E hY$ ' l ) O4
LOSS OF REACTOR OR SECONDARY COOLANT E0P 35 E-1 Page 14 Rev. 2
,\\
(
)
v RESPONSE NOT OBTAINED STEP ACTION < EXPECTED RESPONSE 16 Check If Intact SGs Should de Depressurized To RCS Pres,ure a.
Go to Step 17 PRESSURES b.
Check SGs radiation -
b.
Do not dump steam NORMAL from a SG with high radiation.
Isolate
- 1) Main steam line feed flow to a SG with radiation monitors high radioactivity
- 2) Blowdown line radiation monitor
- 3) Condenser Air Ejector radiation monitor
- 4) IF the radiation monitoring computer is NOT available, THEN have an HP technician 7~_s
(
manually determine
\\
main steam line radiation - NORMAL, c.
Dump steam to condenser c.
Dump steam to atmosphere from intact SGs until SG until SG pressure less pressure less than RCS than RCS pressure pressure 17 Determine If Reactor Vessel Head Should be Vented a.
Consult Director of Station Emergency Organization (DSEO)
O OPE 541 1 84
LOSS OF REACTOR OR SECONDARY COOLANT E0P 35 E-1 Page 15 Rev. 2 (V)
~
STEP ACTION /tXPECTED RESPONSE RESPONSE NOT OBTAINED 18 At 14 Hours After Event Initiation Prepare For Hot Leg Recirculation a.
Check the following valves a.
Place valves in proper
- CLOSED position.
Power lockouts may have to be energized
- 1) SI pump A hot leg injection
- 2) SI pump B hot leg injection
- 3) RHR hot leg irjection
- 4) hMR pump A hot leg injection
- 5) RER pump B hot leg injection b.
Check the followirg valves b.
Place valves in proper
,-S)
- OPEN position.
Power lockouts (V
may have to be energized
- 1) SI pump A cold leg injection
- 2) SI pump B cold leg injection
- 3) SI cold leg injection
- 4) RER purnp A cold leg injection
- 5) RHR pump B cold leg injection 19 At 15 Hours After Event Initiation, Go To E0P 35 ES-1.4 TRANSFER TO HOT LEG RECIRCULATION, Step 1
(
(
CPK44-1 3 44
LOSS OF REACTOR OR SECONDARY COOLANT E0P 35 E-1 Page 16 Rev. 2
,n t
%.,/
STEP ACTION EXPECTED RESPONSE RESPONSE NOT OBTAINED 20 Evaluate Long Term Plant Status a.
Consult Director of Station Emergency Organization (DSEO)
- FINAL -
/"N a
e
'u)
- (
OPK44-1
- 3. $4
a LOSS OF REACTOR OR SECONDARY COOLANT E0P 35 E-1 Page 1 of 1 Rev. 2 s
ATTACHMENT A 1 RAIN A VALVE DESCRIPTION POWER SUPPLY RSS MOV23A Recirc Spray Pump A Suction Isol 32-4T-F8E RSS MOV23C Recire Spray Pamp C Suction Isol 32 4T-F8H SWP MOV54A Pecirc Spray HX SWP Inlet 32-4T-F5H RSS MOV8837A
.ecirc Spray RRR Isolation 32-4T-F9E RSS MOV8838A Recire Spray RHR Isolation 32-4T-F9H RSS MOV20A Recire Spray Header Isolation 32-4T-F7E SIH MOV8835*
SI Cold Leg Injection 32-47-R3E SIH MOV8821A*
SI Pump A Cold Leg Injection 32-4T-R2K SIH MOV8920 SI Pump B Mini Flow 32-4T-R9H SIH MOV8814 SI Pump A Mini Flow 32-4T-F3M SIH MOV8807A~
SI/CHG Pumps Suction X-Conn 32-4T-F7H SIL MOV8804A RHR/CHG Isolation 32-4T-R 111 RMS MOV8716A*
RHR Pump A Hot Leg Injection 32-4T-R3K SIL MOV8812A RWST/RHR Pump A Suction 32-4T-RIE CHS LCV112D RWST to Charging Pump Suction 32-lR-R4J TRAIN B VALVE DESCRIPTION POWER SUPPLY RSS MOV23B Recire Spray Pump B Suction Isol 32-4U-R3E RSS MOV23D Recirc Spray Pump D Suction Isol 32-4U-R3H SWP MOV54B Recire Spray HX SWP Inlet 32-4U-F5E RSS MOV8837B Rectre Spray RHR Isolation 32-4U-R3L RSS MOV8838B Rectre Spray RHR Isolation 32-4U-R2E RSS MOV20B Recire Spray Header Isolation 32-4U-F1H S!H MOV8821B*
SI Pump B Cold Leg Injection 32-3U-RIE S!H MOV8813*
St Pumps Master Miniflow 32-30-F5E Sill MOV8806*
RWST/SI Pump Suction 32-3U-F3E SIH MOV8807B SI/CHG Pumpn Suction X-Conn 32-3U-R5H SIL MOV8812B RWST/RHR Pump B Suction 32-3U-R3H PHS MOV8716B*
RHR Pump B Hot Leg Injection 32-30-F3R SIL M0V8804B RHR/SI Isolation 32-30-R3E CHS LCV112E RWST to Charging Pump Suction 32-lW-R4J
- Turn ON Power Lockout switches for these valves oevss t us