ML20081K115
| ML20081K115 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 06/28/1983 |
| From: | VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | |
| Shared Package | |
| ML20081K108 | List: |
| References | |
| NUDOCS 8311090260 | |
| Download: ML20081K115 (21) | |
Text
-sNtithliBM?.itochment4+"H8S3 DEP.551ic-Djoeleswe.'
1983 VERMONT YANKEE " EOF-IN" EXERCISE SCENARIO OUTLINE Initial Conditions (This set of information is issued to the Shiit Supervisor prior to the start of the exercise)
As shift turnover begins on August 11, 1983, the Night Shift Supervisor reviews the operations log of events and conditions that have been recorded during the night. The following events were discussed:
1.
The plant has been operating at 100% power on close cycle; 2.
Per order of plant management, the High Pressure Coolant Injection System was taken out of service for maintenance. All check-outs of the back up ECCS Systems have been coupleted; 3.
A local " Fab Shop" was established in the Turbine Building at the 252' level directly above the Condensate Demineralizer location.
Radiography work was initiated in this area commencing at 4:30 AM.
Erratic area radiation monitor readings have been obser'ed whenever the source has been withdrawn; 4
At 4:45 AM, a Moisture Sensitive Tape Alarm was reported by the operations crew. Upon checking the signal, it was reported that the signal indicated leakage in the "A" Recirculatica Loop Pump Suction Weld Area. The Drywell Equipment and Flour Drain Sumps indicated normal leakage; 5.
The last RCS sample results indicated an I-131 dose equivalent level of
~0 5x10 uCi/ce; 6.
At 5:00 AM, a slight increase was noted in the Drywell Equipment Drain Sump discharge. Leakage had increased from 1.6 gpm to 2 gpm; 7.
Within the next 1/2 hour, it was noted that the Drywell Equipment Drain Sump Pumps were increasing their operation period; 8311090260 831031 i
PDR ADOCK 05000271 F
PDR L
Rev. 0 6/28/83 l
Page 2
)
8.
At 5:30 AM, the Drywell Equipment Drain Sump Pumps discharge leakage was estimated to have increased to 3.0 gpm; 9.
At 6:00 AM, a Floor Drain Sump Pump discharge occurred. A review of previous records indicated that the most recent discharge was observed one week prior to this date. A drywell temperature check showed no abnormal response; 10.
At 7:00 AM, the Drywell Floor Drain Sump Pump discharged again, it was estimated that the discharge results indicated a 1 gpm leak rate; 11.
At 7:30 AM, the Drywell Equipment Drain Pump discharged. Leakage was estimated to be 3.5 gpm. The drywell temperature showed no significant increase. The Containment Gas and Particulate Monitors read 800 cpm and 8,000 cpm at this time; 12 Vermont Yankee notified REMVEC that plant conditions may require the plant to drop "off-line".
REMVEC has requested that they be advised of worsening conditions as the existing heat wave has caused a significant power demand. The Operations Superintendent was notified of the request and is presently evaluating the situation.
Exercise Time Exercise Sequence / Emergency Response T=0 min, o Shift turnover has been completed.
0800 o A RCS daily sample was drawn at 8:00 AM, and it is undergoing sample analysis.
o The Drywell Floor Drain Pump has discharged again. The estimated leak rate has increased to 1.8 gpm.
~
Rev. 0 6/28/83 Page 3 Exercise Time Exercise Sequence / Emergency Response o A check of the Drywell Equipment Drain Pump discharge has shown an increase in the estimated leak rate conditions to 4.5 gpm.
o Plant management is discussing a controlled shutdown in light of the present plant conditions.
o De-inerting the containment in order to initiate an inspection of the RCS piping conditions is considered at this time, o A review of AP-3125, " Emergency Plan Classification and Action Level Scheme" indicates that an Unusual Event condition should be declared if the unidentified system leakage exceeds 5 gpm or 2 gpm i
increase over the last 24-hour average, o Refer to Table I for the operational details of the accident sequence for this time frame, o Refer to Table II for the radiological details of the accident sequence for this time frame.
T=15 min.
o Drywell Floor Drain Pumps discharge again, 0815 estimated leakage now exceeds 6 gpm.
(Alarm is registered on Control Room Panel 9-4 Drywell Floor Drain Sump Leakage Hi. )
Rev. 0 6/28/83 Page 4 Exercise Time Exercise Sequence / Emergency Response o Shift Supervisor declares an Unusual Event in accordance with AP-3125 based on the following condition:
" Indication of LOCA evidenced by high containment sump flow indicating unidentified leakage greater than 5 gpm".
Shift Supervisor / Plant Emergency Director o
notifies Vermont, Massachusetts, and New Hampshire State Police via the Nuclear Alert System indicating the event type and off-site radiologict.1 conditions produced by the event.
o The TSC Coordinator and EOF Coordinator ccntact the Control Room while all other plant persennel resume normal work activities, o The operations crew has initiated actions to decrease power level at a rate of approximately 5%/ minute.
o Refer to Table I for the operational details of the accident sequence for this time frame, o Refer to Table Il for the radiological details of the accident sequence for this time frame.
I
\\
l l
~
Rev, 0 6/28/83 Page 5 Exercise Time Exercise Sequence / Emergency Response T=25 min.
o A slight increase has been noted in the 0825 Drywell Equipment Drain Sump Pump frequency. Discharge indicates that the system is experiencing a 5 gpm 1eak rate.
o Floor drain leakage appears to be stabilizing at approximately 6.0 gpm.
o The operators have reduced power level to 75%.
o REMVEC requests and management agrees to hold power level at approximately 60% power level for at least 30 minutes due to sicw start of replacement power station.
o The NRC Resident Inspector is notified of the ongoing situation, o The radiogrepher notifies the Control Room that while attempting to reshield the source, a problem occurred which resulted in the source falling from the shield. A radiation survey indicates a general area dose rate of 10.0 R/hr near the doorway to the HP Heater Bay Area.
(The radiographer indicated that a 100 Ci Co-60 source, which was rated at 1,400 R/hr at 1 foot, was being used.)
The exposure rate is 3.0 R/hr at the o
Post-Accident Sampling Panel.
~
Rev. 0 l
6/28/83 Page 6 Exercise Time Exercise Sequence / Emergency Response o A Chemistry and Health Physics Technician is instructed to survey and post the area.
o The TSC Coordinator consults AP-3125 and may determine that an Alert condition should be declared based on the uncontrolled source, o Refer to Table I for the operational details of the accident sequence for this time frame, o Refer to Table II for the radiological details of the accident sequence for this time frame.
T=30 min.
o The Shift Supervisor in concert with the
-0830 TSC Coordinator may declare an Alert based on the following condition:
" Unexpected area radiation levels 1000 times normal",
o The State Police of Vermont, Massachusetts, and New Hampshire are notified via the Nuclear Alert System.
State Health Department personnel o
immediately call back Vermont Yankee to determine the nature of the radiation levels.
o All Vermont Yankee Emergency Centers are being activated.
O Rev. 0 6/28/83 Page 7 Exercise Time Exercise Sequence / Emergency Response o The operators continue to reduce reactor power level via Recirculation Pump flow i
~
- control, o The drywell pressure has increased to 2.05 psig.
o Having reached 60% power level, the operators stop one Circulation Water and Circulation Water Booster Pump to control condenser vacuum.
o Simultaneously, as the Circulation Water and Circulation Water Booster Pump are stopped, the Recirculation Gate drops off its lead screw and closes off the recirculation path back to the intake, o Both remaining Circulation Water Pumps trip on low level and 15 seconds later the Turbine trips on low condenser vacuum (21' Hg ),
o The reactor scrams on Turbine Stop Valve closure. The bypass valves open and condenser vacuum continues to decrease due to the bypass valve still steaming to it.
T=30 min.
o A slight increase in Containment Gas and 0830 Particulate Monitor readings has been recognized, o MSIV isolation occurs due to condenser vacuum decrease to 19" Hg.
9 Rev. O
^
6/28/83 Page 8 Exercise Time Exercise Sequence / Emergency Response o Estimates of the total leak rate conditions indicate that the leakage now approaches 60 gpm.
o At this time, an Alert must be declared due to the following condition:
" Coolant leakage within the primary containment greater than 50 gpm as indicated by continuous sump pumping."
o An ECCS high drywell pressure signal has started both Diesel Generators, Core Spray Pumps, and LPCI.
T=31 min.
o Both Reactor Feedpumps trip on high water 0831 level on scram recovery.
o Reactor Building ventilation isolation occurs on Group III isolation. Standby Gas Treatment System starts.
o Refer to Table I for the operational details of the accident sequence for this time frame.
o Refer to Table II for the radiological details of the accident sequence.
T=33 min.
o Increasing reactor pressure causes a 0833 reactor pressure alarm as pressure reaches 1035 psig.
c.
g Rev. 0 6/28/83 Page 9 4
Excrcise Time Exercise Sequence / Emergency Response t
o If the Automatic Depressurization System is manually initiated, the initiation will be l
stopped by the Control Room Controller.
T=35 min.
o A guillotine break occurs in the "A" 0835 Recirculation Pump Suction Pipe (i.e.,
break size equivalent to 3.65 ft2),
(Recirculation Loop Discharge Valves close. )
o The reactor vessel depressurizes rapidly.
o It is postulated that 5% of the fuel rods in the core are assumed to be perforated due to the rapid depressurization.
T=35-45 min.
o It is assumed that 1.8% of the core noble 0835-0845 gas activity and.32% of the halogen activity contained in the fuel rod is in the plenums and available for release upon perforatien of the clad, o The Reactor Vessel is voided of water in 40 seconds as a result of the guillotine break i
event.
Drywell pressure spikes to 42 psig and o
decreases to 26 psig within approximately 1 minute.
I o The torus pressure increases to 26 psig in 1 minute.
L
Rev. 0 6/28/83
(
Page 10 l
Exercise Time Exercise Sequence / Emergency Response l
o RCIC isolates on low steam pressure. Core spray and LPCI flow are injecting to the l
- vessel, o The Operators may shutdown the Core Spray Pumps and the "B" loop LPCl pumps due to core flooding considerations.
o The containment ARM readings are increasing rapidly.
o The TSC staff are discussing:
a) Stabilizing options such as torus and drywell cooling; b) Flooding of the Drywell; and c) Acquisition of a RCS sample and
~
containment air sample considering imposed radiation levels due to the dropped radiography source.
o The OSC staff are discussing exposu:e concrol measures associated with the acquisition of a coolant sample.
o The EOF /RC is coordinating the off-site agency interface with the State officials.
Rev. 0 6/28/83 Page J1 i
Exercise Time Exercise Sequence / Emergency Response o Refer to Table I for the operational details of the accident sequence for this time frame, o Refer to Table II for the radiological details of the accident sequence for this time frame.
T=45 min, o The Containment ARMS have stabilized:
0845 a) The Containment ARM "A" response is reported as 500 R/hr; and b) The Containment ARM" B" response is reported as 1600 R/hr.
o The TSC Coordinator, in conjunction with the Plant Emergency Director, discuss the possibilis. of escalating the emergency class based on the containment high range monitor reading of 1600 R/hr.
o The Plant declares a Site Area Emergency condition based on tne following condition:
" Indication of actual or potential significant in-core fuel damage evidenced by containment high range radiation monitor readings greater than lx10 R/hr."
o A site evacuation is ordered by the Plant Emergency Director.
s Rev. 0 6/28/83 Page 12 Exercise Time Exercise Sequence / Emergency Response o The TSC Coordinator requests the OSC staff to verify the containment high range ARM readings.
o An OSC Team has been dispatched to re-shield the radiography source.
o An OSC Team has been dispatched to obtain both a RCS sample and a containment air sample from the Post-Accident Sample Panel, o An I&C Technician reports to the Control Room to check the electrical circuitry associated with the Containment ARMS.
o Refer to Table I for operational detail associated with this time frame.
o Refer to Table II for radiological details associated with this time frame.
T=60 min, o The drywell pressure has decreased to 15 0900 psig.
o The drywell temperature is reported as 210 F.
o The core is covered at this time, o Refer to Table I for operational details associated with this time frame.
s l
Rev. O 6/28/83 Page 13 Exercise Time Exercise Sequence / Emergency Response o Refer to Table II for radiological details associated with this time frame.
.T=75 min.
o The post-accident coolant sample has been 1
0915 drawn, and it was reported that the OSC Sample Team accrued an exposure of 1.2 R.
o The OSC Team dispatched to reshield the source has successfully completed this task but a team member accrued an exposure of 2.5 R.
o Refer to Table I for operational details associated with this time frame, o Refer to Table II for radiological details associated with this time frame.
T=90-135 min.
o Sample analysis of the RCS sample indicated 0930-1015 the following activity levels:
a) 100 uCi/cc I-131 dose equivalent; and b)
.6 uCi/cc total noble gas, o The I&C Technician reports that the containment high range monitor B response was erroneous due to a faulty PC board.
The PC board has been replaced and both monitor responses are reported to be the same.
e s
Rev. 0 6/28/83 Page 14 Exercise Time Exercise Sequence / Emergency Response o The TSC Coordinator discusses de-escalation with the Site Recovery Manager as a result of the verification that core degradation is not as significant as initially postulated.
o The TSC Coordinator recommends that the plant maintain an Alert status until the leak condition has been corrected. The leak rate is still greater than 50 gpm.
o The EOF may dispatch a Site Boundary Team to determine if the present plant conditions have produced a release, o A decision is made to flood the Drywell up to the break.
o Refer to Table I for the operational details associated with this time frame, o Refer to Table Il for the radiological details associated with this time frame.
T-135 min, o Reactor Building radiation levels are 1015 observed to be increasing.
o Discussions concerning Reactor Building re-entry are in progress.
.. _ _ ~. - -... _ - _,, _ ~..,..
-..-.-__.m,_.
=
Rev. 0 6/28/83 Page 15 Exereire Time Exercise Sequence / Emergency Response o Discussions concerning venting the drywell atmosphere to Standby Cas Treatment System are being considered.
o Refer to Table I for the operational details associated with this time frame.
o Refer to Table II for the radiological details associated with this time frame.
t T=180 min.
1100 o A recovery plan has been established.
1 o A close-out of the emergency status is in
- progress, o The exercise is terminated.
l
-~
~~
TABLE 1 Liv. 0 6/28/83 PROJECTED OPERATIONAL DETAILS OF ACCIDENT SEQUENCE pig 2 1 of 3 Pre -Sc ram Pos t -Sc ram Clock Time 0800 0815 0825 0830 0830 0831 Listed Parameters 1.
Rx Vessel Coolant Level 160" 160" 167 16T 145" -Inc reasi ng.
177*
2.
Total Core Flow (mil. #/hr) 48 48 35 24 11 11 m
3.
RCS Pressure (psig) 1005 1005 990 980 925 -Increa sing 950-Increasing G
4.
Drywell Pressure (psig) 1.9 1.91 1.92 2.05 2.16 2.45 5.
DW Equipment Drain Sump 4.5 4.5 5.0 5.0 5.0 Grp. 11 Iso.
Latest Leakage Rate (gpa) 6.
DW Floor Drain Surp Latest 1.8 6.0 6.0 Pump Increase 2nd FD Pump Grp. 11 Iso.
C Leakage Rate (gpm)
Freq.
Starts with 1st Still Operating 7.
In-Plant Power Supplied From Aux. Trans.
Aux. Trans.
Aux. Trans.
Aux. Trans.
Start-Up Trans.
Both DG Transformer /SU Start 8.
Mn. Con. Bk. Pres. (" Hg ab.) 2.3 2.3 1.7 1.5 8.5 -Inc rea sing Grp. I Iso.
9.
Suppression Pool Water Level 11.2 11.2 11.2 11.2 11.2 11.2 (wide range - it.)
- 10. Main FW Flow (million f/hr) 6.4 6.4 4.8 3.84 2.5 0
=<
- 11. Cond. Stor. Tank Level (%)
61 61 61 61 61 61
- 12. Suppr. Pool Water Temp. (OF) 84 84 84 84 84 84 s
- 13. Drywell Atmos. Temp. (OF) 148 148 148 149 149 150
- 14. RCIC Flow (gpm)
- 15. Core Spray Flow (gpm)
Start Min. Flow g
- 16. LPCI Flow (gpm)
Start Min. Flow (Grp. IV 1so.)
17 kx Bldg. Diff. Press. (" H O)
-0.8
-0.8
-0.8
-0.8
-0.8
-0. 4 -Dec rea si ng 2
- 18. SbGTS Purge Flow (cfa)
A & B 61,000 each (Grp.111 e
Iso.)
- 19. Control Rnd Position Normal Normal Normal Normal All Rods in (Green) All Rods in (Green)
.s
- 20. Nuc. Instr. Readings 100% Power 100% Power 75%
60%
0%
Driving SRMs in APRM or SRM Readings q
- 21. Pertinent Alarms Moist. Sens.
DW FD Sump TB AkM CW Pump Auto Scram A & B Feed Pump Trip Tape Leak 02 Leakage High High Alarms Trip Alarm Turbine Stop Valve MSIV Low Vac. Isolation a
Low Cond. VAC Fast Closure Scram High DW Pressure Alarm Blowdown AC Interlock UPS A & B g
Feed Breaker Trip
)
TABLE I (continued)
Rav. 0 6/28/83 PROJECTED OPERATIONAL DETAILS OF ACCIDENT SEQUENCE Page 2 of 3 During Blowdown After Bloscown am Clock Time 0833 0835 0835 0840 0845 0900 Listed Parametars C
1.
Rx Vessel Coola nt Level 170" F (Grp. V lso.) No Level Ind.
10*(increasing) 60"
- 100"*
2.
Total Core Flos (mil, t/hr) 10 0
0 0
0 0
3.
RCS Pressure (psig) 1040 400(decreasing) 42 26 24*
15*
cd 4.
Drywell Pressure (psig) 2.7 30 42 26 24*
15*
e 5.
DW Equipment Drain Sump Grp.11 Iso.
Grp. 11 Iso.
Grp. 11 Iso.
Grp. 11 Iso.
Grp. 11 Iso.
Grp. 11 Iso.
Latest Leakage Rate (gpm) c 6.
DW Floor Drain Sump Latest Grp. 11 Iso.
Crp. 11 Iso.
Grp. 11 Iso.
Grp. II Iso.
Grp. II Iso.
Grp. 11 Iso.
Leakage Rate (gpm) c 7.
In -Plan t Power Supplied From Both DG Both DG Both DG Both DG Both DG Both DG Running Start-Up Running Running Running Running Running Transformer Start-Up Start-Up S ta r t -Up Start-Up Star t -Up a
Transformer Transformer Transformer Tra ns forme r Transformer 8.
Mn. Con. Bk. Press. (" Hg ab.) 11.5 11.5 11.5 15.0 17.0 22 9.
Suppress 1oo Pool Water Level 11.2 12.5 w/
Erratic 11.5 (wide range - f t.)
Variation
- 10. Main FW Flow (million t/hr) w
- 11. Cond. Stor. Tank Level (Z) 60 60 60
- 12. Suppr. Pool Water Temp. (OF) 84 86 110 120 130 125*
- 13. Drywell Atmos. Temp. (OF) 152 160 240 225 222*
210*
- 14. RCIC Flow (gpe)
Increases to 400 Then Isolates (Grp. VI Iso.)
- 15. Core Spray Flow (gpm)
Min. Flow Min. Flow 4,000 Each
- 16. LPCI Flow (gpm)
Min. Flow Min. Flow 7,300 Each 17 Rx Bldg. Diff. Press. (" H O) 0.22 0.20 0.20 0.21 0.21 0.21 2
- 18. SBGTS Purge Flow (cfm)
A & B at 1,000 A & B at 1,000 A & B at 1,000 A & B at 1,000 A & B at 1,000 A & B at 1,000 Each Each Each Each Each Each
- 19. Control kod Position All in at 00 All in at 00 All in at 00 All in at 00 All in at 00 All in at 00 w
- 21. Pertinent Alarms High Rx Press. Lolo Water Suppression Level Chamber Trouble Alarm CRD Circum.
Temp. High
TABLE I (continu1d)
Riv. O e
6/28/83 PWOJECTED OPERATIONAL DETAILS OF ACCIDENT SEQUENCE Prga 3 of 3 Clock Time 0915 1000 1030 4
Listed Parameters a
1.
Rx Vessel Coolant Level 11(f*
90" 100"*
2.
Total Core Flow (mil. #/hr) 0 0
0 e
3.
RCS Pressure (psig) 10*
7*
7*
a 4.
Drywell Pressure (psig) 10*
7*
7*
S.
DW Equipment Drain Sump Crp. 11 Iso.
Grp.11 Iso.
Grp. 11 Iso.
m Latest Leakage Rate (gpm) 6.
DW Floor brain Sump Latest Crp. 11 Iso.
Grp. 11 Iso.
Crp. 11 Iso.
Leakage Rate (gpe) 7.
In-Plant Power Supplied From Both DC Both DG Both DC c
Running
- Runninp, Running Sta rt -Up S ta rt -Up S ta rt -Up Transformer Trans f o rme r Transformer em 8.
Mn. Con. Bk. Press. (" Hg ab.) 27.0 30.0 30.0 9.
Suppression Pool Water Level (wide range - f t.)
x
- 10. Main FW Flow (million f/hr)
- 11. Cond. Stor. Tank Level (%)
- 12. Suppr. Pool Water Temp. (OF) 124*
123*
122*
- 13. Drywell Atmos. Temp. (OF) 190*
180*
180*
- 14. RCIC Flow (gpm) 0 0
0
- 15. Core Spray Flow (gpm)
- 16. LPCI Flow (gpa) 17 Rx Bldg. Diff. Press.
0.21 0.21 0.21
- 18. SBGTS Purge Flow (cfa)
A & B at 1,000 A & B at 1,000 A & B at 1,000 Each Each Each 2
2 2
- 19. Control Rod Position 8 x 10 7 x 10 6 x 10
- 21. Pertinent Alarms
- Depends on operator action. Information will be issued by the CR Controller dependent upon operator action.
. ~
TABLE 11 key. 0 6/28/f3 PROJECTED RAD 10 LOC 1 CAL MONITORING DETAILS OF THE ACCIDENT SEQUENCE P gs I cf 3 c
Prw -Sc r v4 Pos t -Sc ram j
Clock Time 0800 0815 0825 0830 0830 0831 c:
Listed Parameters l
1.
Cont. Gas Monitor (cpa) 800 800 800 850 875 900 c
I l
2.
Cont. Particulate Hon. (cpm) 8,000 8,000 8,000 10,000 11,000 12,000 C
3.
R.B. Vent. Hon. (g/p) (cpe) 100/3,000 100/3,000 100/3,000 100/3,000 175/3,500 200/4.0C0 4.
SJAE Monitor (cpe) 30-40 30-40 20-30 15-25 Downscale Downscale c
5.
MSL Rad. Mon. (ak/hr) 180 180 130 100 Downscale Downscale 6.
Cont. ARM " A" (R/hr) 4.0 4.0 2.0 1.5 0.2 0.2 4
7.
Cont. ARM "r (R/hr) 6.0 6.0 4.0 3.0 1.0 1.0 8.
T.B. Moisture Separator 200 200 100 70 10 10 ARM (#13) (ak/hr)
- 9..T.B. North Personnel Access 2.5 2.5 25 25 25 25 ARM (#20) (mR/hr)
- 10. T.B. RR Entrance ARh (#26) 0.05 0.05 105 105 105 105 (mR/hr)
- 11. T.B. Steam Stops ARM (#21) 300 300 220 180 20 20 (mR/hr)
- 12. Primary Coolant Crab Sample 10 uC1/cc 2 x 10 " uC1/cc 5 x 10 uC1/cc 5 x 10 uC1/cc 5 x 10 uct/c 5 x 10 uC1/cc 4
Results (1-131 equiv.)
- 13. Prim. Cont. Air Crab NC Grab Sample Results 1-131
- 14. R.B. 280' Elev. ARM 76 5
5 5
4 3
3 (mR/hr)
- 15. R.B -S. Equip. R.R. AkM #3 0.7 0.7 0.7 0.6 0.5 0.5 (mR/hr)
- 16. R.B. Water CU ARM #9 (mR/hr) 5 5
5 4
3 3
- 17. R.B. 34b' Elev. ARM #12 3
3 3
3 3
3 (ak/hr)
- 18. Stack Gas 1 (cpm) 70 70 70 65 40 40
- 19. Stack Cas 11 (cpm) 110 110 110 105 90 90
- 20. Hi Range Stack Gas (mR/hr) 0.1 0.1 0.1 0.1 0.1 0.1 I
TABLE 11 Rev.'O 6/28/83
'..d PROJECTED RADIOLOGICAL MONITORING DETAILS OF THE ACCIDENT SEOUENCE Prge 2 of 3
- During Blowdown' Af ter Blowdown clock Time 0833 0835 0835 0840 0845 0900
.' C Listed Parameters i
1.
Cont. Cas Monitor (cpm)
Isol. on Crp. 111 1 sol. on Crp. 111 1 sol. on Crp. 111 Isol on Crp. 111 Isol. on Grp.111 Isol. on Crp. 111 2.
Cont. Particulate Hon. (cpa) leol. on Crp. 111 Isol. on Crp. Ill Inol. on Crp. 111 Isol. on Crp. 111 Isol. on Crp. 111 Isol. on Crp. 111 C
3 R.B. %ent. Hon. (g/p) (cpa) 200/4,000 220/4.300 260/5,000 300/10,000 400/15,000-800/30,000 C
l 4.
SJAE Monitor (cpe)
Downscale 4
5.
MSL Red. Hon. (mR/hr)
Downscale j
6.
Cont. AkN " A" (R/hr) 0.2 0.4 270 450 500 400 t
i 7.
Cont. AkM " B" (R/hr) 1.0 1.5 600 900 1.600 00C l
8.
T.B. Moisture Separator 10.0 10.0 10.0 10.0 10.0 10.0 l
ARM (#13) (mR/hr) l
- 9.
T.B. North Personnel Access 25.0 25.0 25.0 25.0 25.0 25.0 l
ARM (#20) (mR/hr)
- 10. T.B. kk Entrance ARM (#26) 105 105 110 105 105 105 (mR/hr)
- 11. T.B. Steam Stops ARM (#21) 15 15 15 15 15 15 (mR/hr) i
- 12. Primary Coolant Crab Sample 5 x 10'3 uC1/cc 5 x 10-2 uct/cc 5 x 10+2 uti/cc 5 x 10+2 vC1/cc 5 x 10+2 uC1/c 5 x 10+2 uC1/cc l
Results (1-131 equiv.)
i
[
- 13. Prim. Cont. Air Crab hC 18 uC1/cc 17.2 uCi/cc 17.2 uC1/cc 16.5 uC1/cc l
Grab Sample Results 1-131
.16 uC1/cc
.16 uCf/cc
.16 uC1/cc
.15 uC1/cc
- 14. R.B. 280' Elev. ARM #6 3.0 3.5 5.0 5.5 6.0 7.0 (mR/hr)
- 15. R.B -S. Equip. k.R. ARM #3 0.5 1.0 4.0 4.0 5.0 6.0 (mR/hr)
- 16. R.B. Water CU ARM #9 (ak/hr) 3.0 3.0 4.0 4.0 5.0 6.0
- 17. R.B. 348' Elev. ARM #12 3.0 3.0 3.0 3.0 4.0 5.0 (mR/hr)
- 18. Stack Gas 1 (cpe) 40 40 50 60 70 140
- 19. Stack Gas 11 (cpe) 80 80 90 100 110 190
- 20. Hi Range Stack Cas (ak/hr) 0.1 0.1 0.1 0.1 0.1 0.1 e'
TABLE 11 Rev. O fr/28/83 PROJECTED RADIOLOGICAL MONITORING DETAILS OF THE ACCIDENT SEQUENCE Page 3 of 3 Clock Time 0915 1000 1030 Listed Parameters 1.
Cont. Cas Monitor (cpm)
Isol. on Crp. 111 1 sol on Crp 111 1 sol. on Crp. 111 2.
Cont. Particulate Hon. (cpm)
Isol. on Crp. 111 1 sol. on Grp. 111 1 sol. on Crp. 111 3.
R.B. Vent. Mon. (g/p) (cpa) 2,000/50,000 4,000/75,000 8,000/150,000 4.
SJAE Monitor (cpe)
Downscale Downscale Downscale 5.
MSL Rad. Mon. (aR/hr)
Downscale Downscale Downscale 6.
Co nt. ARM " A" (R/hr) 340 220 190 7.
Cont. ARM " B" (R/hr) 00C 220 185 8.
T.B. Moisture Separator 10.0 10.0 10.0 ARM (#13) (mR/hr) r<
9.
T.B. North Personnel Access 2.7 2.7 2.7 ARM (#20) (aR/hr)
C
- 11. T.B. Steam Stops AkM (#21) 15 15 15 (aR/hr) x;
- 12. Primary Coolant Crab Sample 5 x 10+2 uC1/cc 5 x 10+2 uC1/cc 5 x 10+2 uC1/cc Results (1-131 equiv.)
+t
- 13. Prim. Cont. Air Grab NC 16 uC1/cc 15 uC1/cc 14 uC1/cc Crab Sample Results 1-131
.15 uCi/cc
.148 uC1/cc
.145 uC1/cc s
- 14. R.B. 280' Elev. ARM #6 12 16 19 (mR/hr)
- 15. R.B -S. Equip. R.R. ARM #3 11 15 18 (aR/hr)
- 16. R.B. Water CU ARM #9 (aR/hr) 11 15 18
- 17. R.B. 348' Elev. ARM #12 10 14 17 (mR/hr)
- 18. Stack Gas 1 (cpm) 440 700 950
- 19. Stack Gas 11 (cpe) 500 750 1,000
- 20. Hi Range Stack Gas (mR/hr) 0.1 0.1 0.1 eDepends on OSC actions.