ML20091J828
| ML20091J828 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 04/01/1984 |
| From: | WISCONSIN ELECTRIC POWER CO. |
| To: | |
| Shared Package | |
| ML20091J821 | List: |
| References | |
| EOP--1-DRFT, EOP-0-01-DRFT, TAC-56311, TAC-56312, TAC-56602, TAC-56603, NUDOCS 8406060211 | |
| Download: ML20091J828 (19) | |
Text
ATTACHMENT 1.1
-t EOP-0
- DRAFT #1 04-01-84 l
1 REACTOR TRIP OR SAFETY INJECTION !
A. PURPOSE 3 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, assess plant conditions, and direct the operator to the appropriate recovery procedure.
B. SYMPTOMS OR ENTRY CONDITIONS
- 1. Reactor Trip a) Any reactor trip b) Rapid decrease in neutron level indicated by nuclear instrumentation.
c) All shutdown and control rods are fully inserted. kod bottom lights are lit.
- 2. Safety Injection a) Any safety injection i
1 8406060211 840601 Page 1 of 16 PDR ADOCK 0S000266 F PDR _
-- - es y -Fy -
f EOP-0 Paga 2 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED j NOTE: STEPS I THROUGH 22 (REACTOR TRIP / AUXILIARY FEEDWATER) ARE IMMEDIATE ACTION STEPS.
' NOTE: THE STEPS OUTLINED WITH BOXES ARE TO BE DONE IF A LOSS OF OFFSITd AC HAS OCCURRED.
NOTE: FOLDOUT PAGE SHOULD BE OPEN.
i NOTE: NOTIFICATION OF DCS, DTA, AND IMPLEMENTATION OF EMERGENCY PLAN, (EPIP 1.I) SHOULD BE PERFORMED AS SOON AS POSSIBLE.
- i. Verify Reactor Trip Manually trip reactor.
(}) IF reactor will not trip, l
- Rod bottom lights lit THEN go to CSP-S.I, " Response to
- Reactor trip breakers open 4
Rod position indicators 3
zero
- Neutron flux decreasing
- (j) Verify Turbine Trip
- a. . Turbine stop valves shut a. Manually trip turbine.
f ([) Verify Safeguards Buses Energized Try to restore power to safeguerds
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- a. Safeguards buses normal a.
voltage buses.
(A05, A06, 803, B04) IF no bus can be energized, l THEN go to EOP-5, " Loss of All AC Power," Step 3 (safeguards bus).
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1 Page 2 of 16
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7 EOP-0 Page 3 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
({) Check if SI is Actuated Check if SI is required.
IF SI is required, THEN manually Low primary coolant actuate.
pressure IF SI is not required, THEN go to
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E0P-0.1, " Reactor Trip Response."
Low steam generator pressure High containment pressure Manual pushbutton Verify Diesels Start Start Diesels
([)
Verify Feedwater Isolation (6)
- a. Feed regulator valves shut a. Shift to manual and shut valves.
- b. Feed regulator bypass b. Shift to manual and shut valves.
valves shut
- c. Steam generator main feed c. Manually trip pumps.
pumps tripped
- d. Steam generator blowdown d. Manually shut valves.
isolation valves shut t
i Page 3 of 16
E0P-0 Page 4 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED verify Containment Isolation
- a. ierify closed indications a. Press containment isolation on isolation status panel manual pushbutton ,
(App. "A", Sect. 1&2)
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0R Shut the valves.
- b. Control room ventilation b. Initiate control room to 100% recirculation recirculation (Mode 2).
- c. Verify manual valves shut:
- 1) Auxiliary charging 1) Shut valve CV-323A
- 2) Any valve which may be 2) Shut valve (s) '
open under ackninistrative control with a designated operator.
< d. Isolate radwaste steam from affected unit:
Unit 1 affected - Shut SA-9 Unit 2 affected - Shut SA-10
@ Verify Auxiliary Feedwater Manually start pumps.
Pumps Running
@ Verify SI Pumps Running Manually start pumps.
@ Verify RHR Pumps Running Manually start pumps, ,
Page 4 of 16.
F EOP-0 Pcga 5 L-STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED h Verify SW Pumps Running
- a. At least four SW pumps a. E less than four pumps start, running THEN start additional pumps, g
- verify non-essential seirvice water loads isolated (Appendix "A", Section 3).
h Verify Containment Accident Fans Running Manually start fans (WIA1, W1B1, W1C1, W1D1) h Verify Safeguards 60 V Bus Lockout Relays Tripped
- a. See Appendix "A", Section 4. a. Trip non-essential loads per
. Appendix "A", Section 4.
h Verify Generator Output and Field Breakers Open E one minute has elapsed, THEN manually trip generator output and field breakers.
h Verify Auto Dus Transfer Manually transfer buses h Ensure Proper Valve Positions
- a. MOV-826A, B, C open a. E valves are not open, THEN (BAST to SI suction) manually open g ensure flow from RWST.
- b. HOV-852A, B open b. Manually open valves.
(core deluge)
- c. MOV-2907, 2908 open c. Manually open valves.
(containment vent coolers) ,
Page 5 of 16
E0P-0 Page 6 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
() Check If Main Steam Line Isolation is Actuated ,
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'a. IF high steam flow, and a. Manually shut main steam RCS temperature <543'F isolation valve.
THEN verify that affected loop has isolated. ,
- b. IF high-high steam flow, b. Manually shut main steam THEN verify affected loop isolation valve.
has isolated.
- c. IF containment pressure c. Manually shut both main steam
>l5 psig, THEN verify both isolation valves.
main steam isolation valves shut.
() Check If Containment Spray is Required
- a. IF containment pressure has a. Manually start pumps and align gone above 25 psig, valves as required.
THEN verifyr Containment spray pumps start Spray pump discharge valves open (MOV-860A, B, C, D)
NaOH addition after two minutes
- b. IF containment spray is actuated and a large loss of coolant has not occurred, THEN transfer controllers to manual and shut the spray additive tank discharge valves (MOV-836A, 8) prior to the elapse of two minutes.
Page 6 of 16 E
r E0P-0 Page 7 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: USE VISUAL VERIFICATION RATHER THAN INSTRUMENTATION PRIOR TO ISOLATING A FAULTED SI PATH.
(hh~VerifySIFlow
- a. RCS pressure <1550 psig a. Go to Step 20, (auxiliary feedwater).
- b. Verify high-head SI flow b. Manually start pumps and align valves as necessary,
- c. RCS pressure <140 psig c. Go to Step 20, (auxiliary feedwater).
- d. Verify RHR pump flow -
- d. Manually start pumps and align valves as necessary.
Verify Auxiliary Feedwater Isolate auxiliary feedwater flow (Eh Flow Isolated to Unaffected to unaffected unit.
Unit Manually start pumps and align (h Verify Total Auxiliary Feedwater Flow at Least 200 arm valves as appropriate.
IF total auxiliary feedwater flow remains <200 gpm, THEN go to CSP-H.1, " Response to Loss of Secondary Heat Sink."
(b) Verify CCW Pumps Running Turn switch to off and then on to manually start pumps.
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Page 7 of 16
r EOP-0
- Page 8 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 23 Check RCP Seal Cooling
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TEEN trip the RCP.
- b. ' Seal injection normal. b. Verify adequate power available to run one charging aump.
and Start one charging pump at minimum speed for seal injection.
24 Verify RCS Temperature Stable IF RCS temperature <547*F and at or Trending to 547*F decreasing, THEN:
- a. Stop dumping steam
- b. IF cooldown continues, THEN control total feed flow.
Maintain total feed flow >200 gpm until level >5% in at least one steam generator.
- c. IF cooldown continues, THEN close main steam isolation valves.
EE IF RCS temperature >547'F and increasing, THEN Dump steam to condenser SE
- Use atmospheric steam dump l
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Page 8 of 16
r EOP-0 Page 9 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION: E OFFSITE POWER IS LOST AFTER SI RESET, THEN MANUAL ACTION MAY REQUIRED TO RESTART SAFEGUARDS EQUIPMENT.
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NOTE: AFTER 51 RESET REINITIATION OF SI WILL NOT OCCUR AS LONG AS ANY SI SIGNAL IS CONTINUOUSLY PRESENT.
25 Reset SI Go to Step 27 (instrument air).
CAUTION: DO NOT OPEN ANY CONTAINMENT ISOLATION VALVE WITHOUT DUTY SHIFT SUPERINTENDENT AUTHORIZATION.
26 Reset Containment Isolation CAUTION: REESTABLISHING INSTRUMENT AIR TO CONTAINMENT COULD CAUSE LOSS OF INSTRUMENT AIR HEADER PRESSURE TO THE OTHER UNIT IF NOT DONE CAUTIOUSLY.
27 Reestablish Instrument Air to Containment
- a. Start other compressor, if available.
- b. Open instrument air b. Manually hold open valves isolation valves, CV-3047 if required.
or CV-3048.
e Page 9 of 16
- EOP-0 Page 10 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 28 Check Pressurizer Pressure Control ,.
- a. Pressurizer pressure stable a. IF pressurizer pressure between 1950 and 2050 psig <1950 psig and decreasing, THEN:
- 1) Verify pressurizer spray valves shut.
IF not shut, THEN manually shut.
IF valves can not be shut, THEN stop RCP(s) supplying failed spray valves.
- 2) Verify pressurizer PORV!s shut.
IF not shut, THEN manually shut.
IF any PORV can not be shut, THEN manually shut its block valve.
IF block valve can not be shut, THEN go to E0P-1, " Loss of Reactor or Secondary Coolant."
2R IF pressure >2050 psig, and increasing, THEN:
- 1) Verify pressurizer heaters off.
IF not off, THEN manually turn off.
- 2) Control pressure using pressurizer spray, auxiliary spray, or PORV in this preferred order, as necessary.
Page 10 of 16
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E0P-0 Page 11 d
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 29 Check if RCP's should Be Stopped ,
-a. Verify at least one SI a. Go to Step 30 (secondarf pump running with flow. integrity).
30 , Check Secondary System Integrity
- a. Both steam generator a. Go to EOP-2, " Faulted Steam pressures being controlled Generator Isolation."
and Not completely depres-surized 31 Check if Steam Generator Tubes are Intact
- a. No condenser air ejector a. Go to E0P-3, " Steam Generator RMS alarms Tube Rupture."
- b. No steam generator blow- b. Go to E0P-3, " Steam Generator down RMS alarms Tube Rupture."
- c. No main steam line c. Go to E0P-3, " Steam Generator RMS alarms Tube Rupture."
Page 11'of 16
EOP-0 Page 12 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 32 Check if RCS is Intact
- a. No containment radiation a. Go to EOP-1, " Loss of ' Reactor
- alarms or Secondary Coolant."
- b. Containment pressure b. Go to E0P-1, " Loss of Reactor
<3 psig or Secondary Coolant."
- c. No containment recircu- c. Go to E0P-1, " Loss of Reactor lation sump "B" or or Secondary Coolant."
keyway level.
33 Check If SI Should be Terminated
- a. RCS subcooling based on a. Do not stop SI pumps. Go to core exit thermocouples Step 35 (status trees).
>15*F
- b. Secondary heat sink b. IF both conditions not satisfied,
- 1) Total feedwater flow to THEN do not stop SI pumps. Go intact steam generators to Step 35 (status trees).
>200 gpm SE
- 2) Narrow range level in at least one intact steam generator >5%
- c. RCS pressure >1600 psig c. Do not stop SI pumps. Try and stable or increasing to stabilize RCS pressure with normal spray. Go to Step 35 (status trees).
) d. Pressurizer level >5% d. Do not stop SI pumps. Go to Step 35 (status trees).
34 Go to E0P-1.1, "SI Termination" Page 12 of 16
E0P-0 Page 13 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 35 Initiate Monitoring of Critical Safety Function .
Status Trees ,
1 CAUTION: IF CST LEVEL IS <4 FEET, THEN ALTERNATE WATER SOURCES FOR AUXILIARY l FEEDWATER PUMPS MAY BE NECESSARY.
36 Control Feed Flow to Maintain IF level in any steam generator Steam Generator Levels Between continues to increase uncontrollably, 5% and 50% THEN go to ECP-3, " Steam Generator Tube Rupture."
37 Verify No Secondary Radiation IF conditions appear to indicate Ala rms a steam generator tube rupture, THEN, go to EOP-3, " Steam Generator Tube Rupture."
- No condenser air ejector RMS alarms No steam generator blow-down RMS alarms No main steam line RMS alarms 38 verify No Auxiliary Building Evaluate cause of abnormal conditions.
Radiation Alarms I_F,the cause is a loss of RCS inventory outside containment, THEN go to E0P-5.1, "LOCA outside containment."
39 Verify No Pressurizer Relief Evaluate cause of abnormal conditions.
Tank Alarms
- Level / temperature / pressure 1
Page 13 of 16
a EOP-0 Page 14 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION: E RCS PRESSURE DROPS BELOW 140 PSIG AT ANY TIME, THEN RHR PUMPS MUST BE MANUALLY RESTARTED TO SUPPLY WATER TO THE RCS.
~ . S 40 _ Check if RHR Pumps Should be Stopped
- b. H RCS pressure is stable b. E pump does not stop because or increasing, THEN stop of SI signal, THEN go to RHR pumps pullout.
l Page 14 of 16
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E0P-0 Page 15 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: DIESEL GENERATOR CAPABILITY IS 2850 KW CONTINUOUS, 3050 KW FOR 30 MINUTES.
NOTE:- AVOID SERVICE WATER ISOLATION BY MAINTAINING FOUR SERVICE WATER PUMPS RUNNING IF POSSIBLE.
, 41 Load Diesels l
l a. Restart a CCW pump if needed.
i b. Restart an instrument air compressor.
- c. Verify Diesel voltage and c. If necessary, take manual frequency normal. control per OP-11A, " Emergency Diesel Operation," and control the output to 4160 V and 60 Hz.
- d. Secure unnecessary plant equipment.
42 Prepare to Start Charging Pumps
- a. Verify adequate Diesel a. Shed non-essential loads.
capacity to run charging pumps.
Page 15 of 16
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EOP-0 '
Page 16 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: LETDOWN ORIFICE ISOLATION VALVES (A0V-200A, B, C) SHUT WITH LOSS OF ALL CHARGING PUMPS.
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43 -Verify Charging Flow
- a. At least one charging pump a. Perform the following:
running.
- 1) IF CCW flow to RCP(s) thermal barrier is lost, THEN isolate seal injection to affected RCP's before starting charging pumps.
- 2) Start charging pumps, as necessary.
- b. Establish charging and seal injection flow as necessary.
44 Check if Diesels should Be Stopped IF safeguards buses _ are energized by offsite power, THEN stop Diesels.
45 Return to Step 28 (Pressurizer PORV's)
- END -
Page 16 of 16 e-
EOP-0 Appendix "A"
- Page 1 1.0 A CONTAINMENT ISOLATION SIGNAL WILL SHUT THE FOLLOWING ISOLATION VALVES (A BRIGHT LIGHT ON THE SAFEGUARDS ISOLATION MONITOR PANEL INDICATES WHEN EACH VALVE IS IN THE SAFEGUARDS POSITION).
Train -
CV-371 Letdown line isolation A&B CV-371A Letdown line isoaltion SC-966A & Sample line isolation (pressurizer steam) A&B SC-951 SC-966B & Sample line isolation (pressurizer steam) A&B SC-951 SC-966C & Sample line isolation (hot leg)
- A&B SC-955 RC-538 Gas analyzer isolation from pressurizer relief tank A ,
RC-539 Gas analyzer isolation from pressurizer relief tank B W'L-1003A RCDT pump suction isolation A WL-1003B RCDT pump suction isolation A WL-1721 RCDT pump common suction isolation B WL-1698 RCDT pump suction line to -19'3" sump A CV-1296 Auxiliary charging line isolation A WL-1723 Sump "A" to -19'3" sump isolation A WL-1728 Sump "A" to -19'3" sump isolation B WL-1786 ' Vent header isolation from RCDT A WL-1787 . Vent header isolation from RCDT B WL-1788 Gas analyzer isolation from RCDT' A WL-1789 Gas analyzer isolation from RCDT B n
E0P-0 Appendix "A" Page 2 l
l Train j CV-313 & Reactor coolant pump seal return line
.CV-313A isolation A&B RC-508 Reactor makup water to PRT A&B SI-846- Accumulator nitrogen fill isolation A&B CC-769 Component cooling water return from excess letdown heat exchanger A&B CV-3200B R211/R212 radiation monitor supply B CV-3200C R211/R212 radiation monitor supply A
'CV-3200A R211/R212 radiation monitor supply A&B CV-3047 Instrument air isolation A&B CV-3048 Instrument air isolation A&B SV-4852 Shifts control room ventilation to 100%
recirculation (Hode 2) A&B CV-2083 Blowdown sample isolation A&B CV-2084 Blowdown sample isolation A&B CV-2042 Blowdown isolation A&B 4
CV-2045 Blowdown isolation A&B 2.0 A.CONTAINHENT VENTILATION ISOLATION SIGNAL WILL SHUT THE FOLLOWING ISOLATION VALVES (A BRIGHT LIGHT ON THE SAFEGUARDS ISOLATION HONITOR PANEL INDICATES WHEN EACH VALVE IS IN THE SAFEGUARDS POSITION)
HV-3244 Containment purge supply isolation-- A HV-3245 Containment purge supply isolation B HV-3212 Containment purge exhaust isolation A.
HV-3213 Containment purge exhaust isolation B v-d W f ~
r v . -
E0P-0 Appendix "A" o
Page 3 3.0 COOLING LOADS ISOLATED IF LESS THAN FOUR OR SIX SERVICE WATER PUMPS START 3.1 Train "A" 3.1.1 SW-2816, service building air conditioning -
a 3.1.2 SW-2930A, spent fuel pit heat exchanger 3.1.3 A0V-LW-61, service water to overhead condensers of blowdown evaporators and steam generator blowdown tank vent condensers.
3.2 Train "B" 3.2.1 ISW-2880, Unit 1 turbine building feeder (Unit 1 SI only) 3.2.2 25W-2880, Unit 2 turbine building feeder (Unit 2 SI only) 3.2.3 SW-2817, water treatment area 3.2.4 A0V-LW-62, service water from overhead condensers of blowdown evaporaotr and steam generator blowdown tank vent condenser and R11/R12 pump 3.2.5 SW-2930A, spent fuel pit heat exchanger 4.0 NON-ESSENTIAL EQUIPMENT STRIPPED FROM SAFEGUARDS BUSES-B03/B04 LOCKOUTS 4.1 Component cooling water pumps are tripped if safety injection is coincident with an undervoltage on the safeguards buses.
4.2 Pressurizer heater backup groups "C" and "D" and the control group "E".
4.3 Electric fire pump (Unit 1 SI only) (1B03).
4.4 480 volt bus tie breakers B52-15C, B52-16C, B52-18C (B52-26C, B52-39C, B52-40C).
4.5 Auxiliary and service building motor control centers (Unit 1 - 1831, B43; Unit 2 - 2B31, B21. B33) 4.6 Service air compressor K3A (Unit 1 SI only) (1B04)
Service air compressor K3B (Unit 2 SI only) (2B04) 4.7 ' Turbine _ building crane (Unit 2 SI only).
w_