ML20204F417
| ML20204F417 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 04/11/1983 |
| From: | CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML20204F404 | List: |
| References | |
| PALEX-83, NUDOCS 8305020083 | |
| Download: ML20204F417 (18) | |
Text
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o CONSUMERS POWER COMPANY
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I PALISADES NUCLEAR PLANT SITE EMERGENCY PLAN.
i PALEX-83 Emergency Preparedness May 24-25, 1983 Exercise Scenario I
)
FOR CONTROLLERS ONLY 8305020083 830411 PDR ADOCK 05000 "g F
PALEf-83 PALISADES PLANT SEP Exercise Scenario Initial Conditions j
1.
The Palisad'es Nuclear Plant has been at steady state power of I
100% for forty-five days.
The core is at middle-of-life with I
equilibrium xenon.
2.
The 1A charging Pump is out of service for replacement of seal packing.
The Maintenance Order has been prepared and issued, (simulated) tags have been prepared and are ready to hang.
The job is expected to take ten hours.
3.
The daily Primary Coolant System inventory check is in progress as per TS 4.2.2-8 in D/WO-1.
4.
The bi-weekly Surveillance Test for Control Rod Exercising is in progress as per SOP 6, Attachment 2, Section 4.
5.
The Quench Tank drain valve, CV0148, is failed closed due to an inoperable solenoid.
A Maintenance Order has been issued and red tags hung, however, to complete the work, parts are needed Which are on order.
The parts are not due to arrive for several days.
6.
The electric-driven fire pump, P9A, is out of service due to an open winding in the motor coils requiring removal of the motor.
Tags have not been hung and no work has commenced on this task.
7.
Diesel Generator 1-1 is inoperable due to a leak in the starting air system creating insufficient starting air pre ssure.
A maintenance investigation is in progress.
W lding is in progress on Level 625' for hand rail reparation 8.
e j
near the Main Steam Relief Valve stacks.
9.
The cooling coils in Containment Air Cooler VlA are isolated due to leakage from the coils.
Isolation was performed.two days earlier, which allows five days before an LCO is reached per T.S.
3.4.2.
10.
No other evolutions are in progress and all other plant systens are considered operable.
11.
Forecast meteorological conditions are:
a.
Wind speed is 2.5 mph b.
Wind direction is from 2800 to 1000 (WNW to ESE) c.
Ambient temperature is 650F d.
Stability class is "F"
1 4
PRLEf-83 SEP EXERCISE SCENARIO Narrative Summary Actual Scenario Time Time Key Events (May 24, 1983) 1200 00/00 The plant is simulated to be running at 100% power.
1210 00/10.
During the surveillance test for control rod exercising, rod B-18 is declared inoperable.
It is found to be stuck in the fully withdrawn position.
The Shift Supervisor is informed by the operator performing the test.
NOTE:
The Shif t Supervis,or should check T. S. 3.10.4, which states that operation can continue with one inoperable rod.
However, during the time a control rod is declared inoperable, procedure EM-04-09, i
which is a shutdown margin calculation, should be carried out.
1215 00/15 The Shift Supervisor informs the Plant I
General Manager who requests that the control rod surveillance test be con-tinued and that the plant remain at power.
1225 00/25 A small fire is discovered in the plant chemistry lab. The Control Room is notified.
l 1226 00/26
. The Fire Protection Plan is imple-mented and fire brigade personnel are notified to respond.
The Property Protection Supervisor is also notified.
i NOTE:
This is to be regarded as a small fire of insufficient magnitude to require declara-l tion of an Unusual Event.
2
PA'EK-83 L
SEP EXERCISE SCENARIO Narrative Summary (Cont.)
i Actual Scenario 4
Time Time Key Events 1235 0035 The Fire Brigade arrives at the scene,
l of the fire.
The fire brigade captain informs the Control Room that of fsite assistance is not required.
1237 00/37 '
The fire is out and personnel return their equipment to storage.
It is i
determined that due to the nature of the fire a re-flash watch is not required.
1250 00/50 During continuation of the Control Rod Testing, an additional control rod (1-
- 25) is found to be stuck in the fully withdrawn position and is declared inoperable.
1252 00/52 The Shift Supervisor checks the plant Technical Specifications (T.S.
3.10.4.b) and determines that the i
plant is in a limiting condition for 3
operation requiring the plant be i
placed in a hot shutdown condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
j 1254 00/54 The Shift Supervisor informs the Plant General Manager.
Additional attempts are made to free the stuck rod.
A second shutdown margin calculation is performed.
1300 01/00 An Unusual Event is declared (plant shutdown required by a T.S.L.C.O. ).
. The Shift Supervisor directs that notification be made to Consumers Power Company duty personnel, the Jackson Power Controller, the NRC, the Van Buren County Sherif f and Michigan State Police.
1310 01/00 A subsequent notification is made to the Plant Public Af fairs Director and an event report is initia ted.
3
PALER-83 SEP EXERCISE SCENARIO Narrative Summary (Cont.)
Actual Scenario Time Time Key Events 1322 01/22 The daily PCS inventory check is completed with no indications of abnormal leakage.
1330 01/30.
The Control Room Operators commence a unit shutdown at 6-12% per hour to reach hot shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
1345 01/45 Unit shutdown continues.
1400 02/00 A primary coolant chemistry sample is taken to verify shutdown margin boron concentration in the primary coolant system.
1430 02/30 A turbine trip occurs due to a thrust bearing wear signal.
This causes a reactor trip, however, the inoperable control rods do not insert.
Reactor power remains at approximately 15%.
1431 02/31 The Pilot Operated Relief Valve on the Pressurizer lifts and discharges to the Quench Tank.
Also, the "B" Pressurizer Code Safety Valve starts to weep at approximately 2 gpm.
1432 02/32 The Control Room operators begin emergency boration using the two available Charging Pumps.
NOTE:
It will take approximately 20 minutes to bring the reactor suberitical using boron injection.
1433 02/33 The operators respond to the transient
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as per the Reactor Trip Procedure, EOP-1.
t 4
PALEf-83 SEP EXERCISE SCENARIO Narrative Summary (Cont.)
Actual Scenario Time Time Key Events 1335 02/35 A high activity alarm is received in the Control Room on the Failed Fuel Monitor.
Another PCS chemistry sample is taken to determine the primary coolant activity levels.
1440 02/40 The Shif t Supervisor re fers to pro-cedure EI-1, Activation of the Emer-gency Plan, and declares an Alert (failure of RPS to initiate and complete a scram such that the reactor is not made subcritical).
Follow-up notifications are directed to be made.
A public address system announcement is made at the plant.
1445 02/45 Personnel assembly and accountability is initiated.
1447 02/47 The Quench Tank rupture disk ruptures due to the discharge of the PORV and code safety.
1500 03/00 The operators initiate a second PCS leak rate check in accordance with D/WO-1.'
Unit shutdown continues.
1510 03/10 The Technical Support Center and Operations Support Center are activated.
1515 03/15 Personnel accountability is completed satisf actorily with no identified
. missing persons.
1525 03/25 The Consumers Power Company General Office Control Center (GOCC) is activated in Jackson, Michigan.
1530 03/30 The reactor building sump level alarm is received in the Control Room.
5
PALEX-83 SEP EXERCISE SCENARIO Narrative Summary (Cont.)
Actual Scenario Time' Time Key Events 1600 04/00 End of first day of the exercise.
Events in progress are frozen unti$
the exercise begins on the followid morning.
(May 25, 1983) 0800 04/00 Previous plant conditions are established to begin today's exercs activities.
0830 04/30 The "B"
Pressurizer code safety fa8 creating a loss of coolant accident The operators respond using Emergel Operating Procedure 8.1.
0835 04/35 Primary Coolant System Pressur.e drq steadily.
The Site Emergency Direc declares a Site Area Emergency (LOC exceeding charging pump capacity).
0840 04/40 All non-essential personnel are evacuated from the site.
0845 04/45 Containment rad levels, temperature pressure, and humidity show an increase.
0850 04/50 The operators place the plant in natural circulation and attempt to maintain pressure and control plant cooldown.
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0900 05/00 An improperly stored welding unit b; causesanexplosionthatshearsbot]l the Main Steam Relief Valve stacks Containment purge exhaust lines between Containment and the first purge exhaust valve.
This opens a potential release path from Containment to the environment.
6
PALEf-83 SEP EXERCISE SCENARIO Narrative Summary (Cont.)
Actual Scenario Time
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Time Key Events 0905 05/05 The near-site Emergency Operations Facility is activated.
0910 05/10 Initial dose projections indicate 3.6 rem /hr at the site boundary will be reached.
A General Emergency is declared by the Site Emergency Director.
Offsite authorities and agencies are updated.
0915 05/15 Field Monitoring Teams are dispatched to track the plume.
Emergency Repair Teams prepare to isolate the Containment purge lines.
0925 0525 The Field Monitoring Teams verify that a radiation release is occurring from the plant.
0930 05/30 Of fsite protective actions are recommended to evacuate in a two mile radius and a five mile downwind sector in an east-south-east direction of the plant.
0935 0535 Enginedring Safeguard Systems are activated on low Primary Coolant System pressure.
0936 05/36 A low flow alarm, 1347, is received on the Service Water System header supply to the Containment air coolers.
NOTE:
This is simulated to be caused by a mechanical shock to valve CV0847, which twists the valve disc and partially blocks flow.
The mechanical shock is simulated to be the increase in service water flow (by a factor of 3) during the engineered safeguards actuation.
7
PALES-83 SEP EXERCISE SCENARIO Narrative Summary (Cont.)
Actual Scenario Time Time Key Events 0940 05/40 The prompt alerting system sirens and emergency broadcast systems are utilized to notify the public.
0945 05/45.
Press briefings are established at the Joint Public Information Center.
1015 06/15 Chemistry personnel don protective.
clothing and take a primary coolant sample using the Post Accident Sample Monitors.
1030 06/30 The release continues, however, High Pressure Safety Injection maintains Primary System pressure and prevents further core degradation.
Of fs ite authorities are updated.
1045 06/45 Containment pressure steadies out at approximately 3,5 psig at a temperature of 1700F.
I 1100 07/00 Primary System conditions remain relatively stable.
Of fsite author-ities are continued to be updated.
1125 07/25 Emergency Repair Teams are able to block off the severed Containment purge exhaust lines, terminating the release.
1130 07/30 Plant conditions remain stable.
1200 08/00 Plant conditions continue to improve with greater assurance over control of the ' reactor.
1215 08/15 Through discussions with the leading facility and organization managers, the emergency classification is de-escalated.
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8
PALEf-83 SEP EXERCISE SCENARIO Narrative Summary (Cont.)
Actual Scenario Time
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Time Key Events 1230 08/30 Reentry activities are initiated both,
onsite and offsite.
1300 09/00 Recovery organizations are established as final reentry activities are comple ted.
1330 09/30 Plans are prepared for temporarily increasing the radwaste handling facilities.
Control of the plant is main tained.
Of fsite authorities are updated.
1400 10/00 Following notification to all personnel involved,.the exercise is ended.
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CONSUMERS POWER COMPANY PALISADES NUCLEAR PLANT PALEX-83 1
May 24-25, 1983 Exercise Scenario Initial Offsite RadiolN ical Data'and Example Message Sheets e
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i SCENARIO NO.
PALEX-83 TIME =
MESSAGE NO.
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PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISh MESSAGE FORM Initial Dose Projection Information Stability Class F-Wind Speed 2.5 mph' to 100o (WNW to ESE) 0 Wind Direction 280 l
Release Rates Noble Gas - 137 ci/sec i
.015 ci/sec E-Bar 0900 - 0.3 1000 - 0.28 Release Duration 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ('0900 to 1130)
At time 0900 on the second day, the projected offsite doses will be:
l l
Distance Whole Body Child Thyroid l
0.5 miles CONCEN N GAS 5.77E-2 CONCEN IODINE 6.31E-6 MREM /HR 3.59E3 MREM /HR 1.17E4 1.0 miles CONCEN N GAS 2.73E-2, CONCEN IODINE 2.99E-6 MREM /HR
'.37E3 MREM /HR 5.53E3 l
1.5 miles.
CONCEN N GAS 1.66E-2 CONCEN IODINE 1.82E-6 MREM /HR 1.66E3 MREM /HR 3.37E3 2.0 miles CONCEN N GAS 1.16E-2 CONCEN IODINE 1.27E-6 MREM /HR 1.26E3 MREM /HR 2.35E3 5.0 miles CONCEN N GAS-3. 67E-3 CONCEN IODINE 4.01E-7 MREM /HR 4.94E2 MREM /HR 7.43E2 10.0 miles CONCEN N GAS 1.55E-3 CONCEN IODINE 1.70E-7 MREM /HR 2.39E2 MREM /HR 3.15E2
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PALEX-83 TIME =
MESSAGE NO.
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PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM
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PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Plume Progress' ion Palisades (Release Begins) l i
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EXAMPLE SCENARIO NO.
PALEX-83 TIME =
1210 MESSAGES NO.
2 T=
10 min.
PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM MESSAGE FOR:
CONTROL ROOM SIMULATED PLANT CONDITIONS:
See Data Sheet MESSAGE:
Rod B-18 is fully withdrawn and will not move.
FOR CONTROLLER USE ONLY i
CONTROLLER NOTES:
1.
This message is provided during the j
surveillance te, sting for exercising control l
rods.
t l
2.
The drag brake on rod B-18 has malfunctioned and the rod will not operate.
All efforts to free this rod will fail.
A containment entry will be required to repair the rod.
The rod is inoperable throughout the scenario.
ACTION EXPECTED:
1.
Operator-informs SS of the problem with rod B-18 2.
SS to check TS 3.10.4 to verify operation can continue with one (1) inoperable rod.
3.
Calculate shutdown margin per EM-04-09.
4.
SS notifies the Plant General Manager of the problem.
L
t 4
U Hessage Time To Scenario No.
C 03 C-02 C-01 i
OW Pumps X P-7A X, P-7B P-7C Intermediate Press Letdown Temp
/ 73' 0F MFP Suction Press "T 70 psig CCW Pumps X P-52A I P-52B
_ P-52C Charging Line Temp 1/00 'F-t FP A Dsch Press 7 Fo psig FPC Pumps K P-51A
_ P-51B Letdown Line Temp 4230 'r MFP B Dsch Press 9 FO psis 0F AN Pump B Steam Press O psig SDCS from PCS (R)
Containment Cooler Recirc Fans SDCS to PCS (R)
F A W Pump A Amperes O amps 0
1 V1A.
d V2A A V3A 1 V44 VCT Temp
/f o 0F A N Feed Pump Dsch Press O psig R V1D V2D X V3B X V42 VCT Press Sa psi Holsture Sep Dr Tank M5 s
VCT Level' 7A 5 Condenser llotwell Level I1
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IIPSI Pumps _ P-66A
_ P 668 _ P-66C PCP Control Bleedorf Press 70 psig Condenser Vacuum 17 7 in hg.
. LMI Pumps _ P 67A _ P 678 Letdown Flow -
- O GPM Gland Seal Cond Yacuun
/7 _ in hg.
Containment Spray Pumps
. Charging Flow SO C'M.
Atm. Ste. Dumps cwJe'O P-54A P-54B P-54C Quench Tank Temp
/Jf 'T AW Feed Pumps
- P 8 A ----- P8B i
Quench Tank Press O.6' psig floater Drain Pumps X P10A X PICD Quench Tank Level 73'_. $
Condensate Pumps K P2A X P2D Heteorological Data Pzr Press (R)
- C/d pata Generator Watts, 2/OMW Pzr Level (R)
SO $
Wind Speed (mph)
PCS T,,,(R) fle.7 'F
- PIP, (m/sec)
Charging Pumps 1P55A,__,_ P558 _ PSSC l
Winit Direction PCPs 1 P50A 3 P50B,_ &_,P50C 1 P500 Gross HW MO l
From To Pzr litr Amps L.C.15 /Jo L.C.16 /.5~D Not HW
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.itability Class Control Bod Position Control Rod Position Temperature CPA /J_21n. GPB /.7{1n. G,P1/ @ n.
GP 1 fff. GP 2 3 GP 3 / y GP,4 Q GP2 [ffin. GP3 /d. tin. GP4 /[Ain.
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Part length L.IAin.
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Message:
Time:
T Scenario No.
EbMb e
C 13 C 12 C It CM Level N'O $
B. A.S.T. 14 vel 97 %
Instrument A!r Press
/ n 5~~ psig Renetoe Yessel DP 4T( psid AFW Flow D O GPM
~
Containment Du11 ding Press 0,3_psig PORY Discharge Temp jd *F Condenser Yacuus (R)
,1 / in lig.
S/C A Compartment Te n
/p['F Pzr Safety Yalve Dsch Temp PCP A Leak-off Fl u (R)
/,0 CPM S/G A Compartment Ifumidity
'O_$
A
/.2f'~ 'F B /AS~ 'F C fj5F PCP B Leak-off Flow (R)
/,7 GPM S/G D Cornartment Temp
/ D1' 'F Prr Press
/C/O psia PCP C Leak-off F?ow (R)
/, 3 C111 S/G Il Compartment liumidity O_$
PCP Current 4/C emps PCP D Leak-off Flow (R)
PCS Flow
~2( %
0,3 psia T
ffj F
Equipement Status:
WR Containment Press (R) e H
Containment Sump Level O %
T O~I C
Containment Water Level (R)
(5 %
TC "8 III f30 'F 1.
Significant Equipment Outages I" perable Equipment)
SI Tank Level Yf f PCS WR Press (R)
,74 /O psia SI Tank Press cP/ C psig PCS NR Press (R) fo/O psia 2.
Surve113ance Due or in Progress S/G A Level WR 70 %
3.
Abnormal Electrical Lineups or tinit Status:
S/G A Level (R) 70 $
Ntages Operating finde
['O = t A*
OAV//Th/y S/G A Press 700 psia
, 5 1106 ppig S/G A Steam Flow (R)
S!Entff cant Activities in Progress 6
S/G A Feed Flow (!!)
f (, 110 ppig i
S/G B Level VR 70 5 S/G B Level (R) 7C %
S/G B Press
- 70 0 psia
~
S/G D Steam Flow (R)
[,6 It06 ppy 6
S/G B Feed Flow (R)
CC.110 pp3,
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