ML20067A936
| ML20067A936 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 10/18/1982 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20067A921 | List: |
| References | |
| PROC-821018-01, NUDOCS 8212030279 | |
| Download: ML20067A936 (17) | |
Text
..
QEP 330-0 Ravision 15 Octobar 1982
- . ID/10,1P ASSESSMENT ACTIONS 330-0 O,/
Assessment Actions Rev. 15 10-18-82 330-1 Abnormal Personnel Exposure Rev. 3 08-10-81, 330-2 Accidental Release of Radioactivity Within the Site Boundary Rev. 2 02-22-81 330-3 SPING Control Terminal Operation Rev. 4 09-23-82 330-4 Estimation of Off-Site Dose from an Unplanned Release of Radioactive Effluents Rev. 1 12-17-80 330-5 Estimating High Activity Releases during Accident Conditions Rev. I 12-17-80 330-6 Air Sampling Under Accident Conditions Rev. 3 10-18-82 330-7 In-Plant Iodine-131 Measurement During Post-Accident conditions Rev. 5 10-18-82 j,
330-8 Handling and Analysis of Post Accident Reactor Coolant Samples Rev. 5 10-18-82 330-9 Estimating Plant Release Using the Stack Gas Monitors Rev. I 12-17-80 330-10 On-Site Environmental Sampling During Emergency Situations Rev. 2 10-18-82 330-T1 Quad-Cities Station Environs Monitoring-Dairy Farms Rev. 1 06-20-80 330-T2 Dose Factors for Gaseous Releases Rev. 2 03-10-82 330-T3 Dose Factors for Liquid Releases Rev. I 12-17-80 gg y y e.u;,,
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QEP 330-0 Rsvisica 15 330-T4 Main Chimney Release Rate Table Rev. I 12-17-80 330-T5 Typi, cal Gas Stack Monitor Calibration Curve Rev. I 12-17-80 330-T6 Sample Cave Rev.-1 05-18-81 330-T7 Sample Dilution Equipment Rev. 1 05-18-81 330-T8 On-Site Environmental Sampling Locations Rev. 1 06-01-82 330-T9 Area Radiation Monitor System Rev. I 10-18-82 i
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QEP 330-6 3
Revision 3 5
AIR SAMPLING UNDER ACCIDENT,_
October 1982 CONDITIONS
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A.
PURPOSE
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This procedure out. lines the methods by which aieborne radioiodine samples and particulate samples are safely obtained under conditions of potentially extremely high radioiodine, noble gas, and particulate airborne concen-trations.
REFERENCEbs B.
1.
GY-130 Silver Zeolite Technical Data Sheets.
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H-809 VII Tecliical Data Sheets.
3.
QCP 800-2.
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QRP 1360-1.
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C.
PREREQUISITES
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1.
Obtain an operable, calibrated, high range exporure rate instrument.
2.
Obtain 0-5R and 0-IR direct-reading dosimeters. [
3.
Obtain finger TLD-rings for both hands.
4.
Obtain RADeC0 H-839 high volume air sampler with combination cartridge-filter head, 47 mm glass fiber filter paper, and GY-130 Silver Zeolite cartridge.
5.
Obtain Self Contained Breathing Apparatus, if necessary.
D.
PRECAUTIONS 1.
Minimize direct contact.between you and the sample.
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l' 2.
Take care to avoid contaminating '.the sampling media.
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3.
Plan all phases of the operation prior to entering any high radiation exposure rate areas.
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Insure that the instrument has been calibrated.
ll 5.
The air sampler should not be used in the variable mode.
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l QEP 330-6 Rsvision 3 E.
LIMITATIONS AND ACTIONS 1.
Take all appropriate steps to insure that the radiation exposure you receive does not exceed 3 and 18-3/4 Rems to the whole body or extrem-
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ities, respectively, per quarter.
2.
This procedure should only be used in such cases when QRP 1360-1, Air Sampling of Suspected Radioactive Airborne Areas, is rendered useless by conditions in the plant.
3.
When using the Cutie Pie ionization survey instrument, it should be bagged to prevent noble gas intrusion into the ionization chamber.
F.
PROCEDURE 1.
Use a 47 mm glass fiber particulate filter. Mark the smooth side of the filter paper. This will serve as the inlet side.
2.
Use a GY-130 Silver Zeolite cartridge. Fraw an arrow on the side of the cartridge pointing in the direction cf the flow.
3.' Load the filter paper and the cartridge into the comb'inations sampler head. The particulate filter is supported by the honeycomb backing, and scaled by the outer aluminum ring.
4.
Preparation of the sampler should if possible, be performed in a low exposure rate area.
5.
To sample, place the VAR-OFF-HI switch in the Hi position.
6.
Note the sample start time, and flow rate.
7.
The sample time should be selected such that an adequate amount of activity is collected, and personnel radiation exposure is minimized.
In areas of suspected extremely high airborne radioactive material concentrations, the sampling time should be limited to avoid sample preparation and analysis problems.
NOTE A 1 minute sample should be adequate to
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require respiratory protective measures, if isotopic analysis is available.
If conditions V"'"
allow, a 5-minute sample should be taken to assure more accurate results for both radio-iodine and particulate' analysis.
8.
When the sample is completed note the flow rate and time, and turn the sampler off.
9.
Return the cartridge and filter paper to the designated area for
- s, analysis.
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QEP 330-6 R: vision 3 10.
The GY-130 silver zeolite cannisters display a low retention for noble gases. Radioiodines of all species should be retained with a high efficiency. The glass fiber particulate filter will be used for the particulate analysis as it has a high efficiency for particulate retention.
11.
The batch number of the cannister should be recorded, should speciric information on the cannister efficiency be needed.
12.
Perform the analysis as specified by QCP 800-2.
For particulate analysis.
13.
The analysis results should be reported to Radiation Protection super-vision promptly.
G.
CHECKLISTS 1.
- None, H.
TECHNICAL SPECIFICATION REFERENCES 1.
None.
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QEP 330-7 Revision S IN-PLANT IODINE-131 October 1982 MEASUREMENT DURING POST-ACCIDENT CONDITIONS ID/3F A.
PURPOSE The purpose of this procedure is to outline the methods for measuring I-131 in the plant following an accident, in order to assess the airborne radiological conditions.
B.
REFERENCES 1.
Quad-Cities Station, Project No. 5954-00 Sargent & Lundy; Post-Accident Radiation Levels, A Review of the Quad-Cities Station in Response to Item 2.1.6.b of NUREG-0578.
C.
PREREQUISITES 1.
Obtain self-contained breathing apparatus, if necessary.
D.
PRECAUTIONS 1.
Verify that while performing this procedure, radiation levels are monitored.
2.
Measure sample cartridges for radiation level to insure samples are safe to handle.
I 3.
Based upon the analyses of Reference 1, exposure rates under post-accident conditionsmayseverelylimitkesidencetimeinmanyplantlocations.
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In particular, the following areas should be carefully assessed prior to I-131 sampling and analysis.
l a.
All of the reactor building.
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b.
Turbine building elevation 639'.
c.
Turbine building between units, elevation 611'6".
i d.
HPCI access tunnel.
E.
LIMITATIONS AND ACTIONS i
l-I.
This procedure is designed for use during a post-accident situation when a "go-no go" decision needs to be made concerning entry into an l:
area where airborne I-131 is present.
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2.
This procedure assumes a sample volume of 30 ft.
If another volume isused,adjustghe4100netpeakareaaccordingly. A 4100 n5t Peak area for a 30 ft sample is equal to 1 MPC for I-131, 9 X 10 uci/cc.
3.
When using the Cutie Pie ionization survey instrument, it should be bagged to prevent noble gas intrusion into the ionization chamber.
F.
PROCEDURE 1.
Equipment needed.
i a.
Post-Accident Radionuclide - Analysis Portable System (PARAPS).
b.
Portable air sampler.
c.
Silver zeolite cartridge.
i d.
Glass fiber filter paper.
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Start up of the detection system.
a.
Turn on the AC line conditioner.
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b.
Turn on the nim bih power supply.
c.
Turn power on to the detector bias supply.
g' d.
Using the 10 turn pot on the bias supply, raise the voltage to l
3,000 volts.
Turn the 11/34 computer power switch to the "DC ON" position.
e.
f.
Turn on the disc drive and put the RUN/ LOAD switch in the run position. The disc ready light should light in a few minutes.
g.
Turn on the 7050 MCA.
h.
Turn on the line printer.
3.
Proceed with the air sampler and sample media,to the area where the sample is to be taken.
Place a silver zeolite cartridge in the sample holder, and a glass fiber filter paper in the filter holder. Turn the air sampler on, note the flow rate, sample time, and sample for 10 minutes.
4.
Remove cartridge and filter from sampler.
Place samples in separate plastic sample bags; label each sample. Place cartridge, in'the sample bag on the 10 cm shelf.
5.
Steps 6 through 10 is the primary method to determine the samples activity.
If either the 11/34 computer or the disc drive is not working, steps 11 through 26 can be used to determine if the area sampled may be entered.
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Initialize the system using the Automated Analytical Instrumentation System's (AAIS) Central System Procedure (CSP).
1 7.
Set the system prime using the AAIS's CSP.
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8.
Log on the sytem using th? AAIS's CSP.
9.
Determine the lodine activity by running the AAIS's Central Chemical Procedure for iodine radionuclide analysis.
10.
If another sample is to be analyzed, repeat step 13.
11.
On the Ortec 7050 MCA, depress "LT".
12.
Depress "600" on the data entry pad.
13.
Depress " ENTER".
14.
Depress "STOP".
i 15.
Depress both " ERASE" buttons at the same time.
16.
Depress " START".
The 7050 MCA will now start a count for 10 minutes.
17.
Check the deadtime.
If over 30%, stop count. Call a chemist.
18.
Observe the MCA screen and find the cursor.
19.
Move the cursor to channel 729.
20.
Depress horizontal expand button 5 times.
If a peak is present, it is Iodine 131.
21.
After the count is over depress " SET" on the region of interest pad so that the " SET" light comes on.
The. cursor will become brighter.
22.
Move the cursor to highlight the entire peak. As you highlight each j
channel it will become brighter.
If you make a mistake depress'" CLEAR" and remove the highlight i
a.
from the affected channels. Then repeat step 20.
23.
Depress " SET" so that the "0FF" light goes on.
24.
Depress the " GROSS-NET" button so that " NET" is lit.
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Observe the net peak area in the upper right hand corner of the screen, second row down.
It will say: AREA (N)=
(net peak area).
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'a.
If the net peak area after a ten minute count is less than 4100 counts, it is safe to enter the area without supplied air.
b.
If the area is greater than 4100 counts, do not enter the area unless supplied air is used.
c.
If the net peak area exceeds 4,100,000 counts, do not enter the area and contact the Radiation Chemical Supervisor.
26.
If another sample is to be analyzed, repeat steps 14 through 25.
G.
CHECKLISTS 1.
None.
H.
TECHNICAL SPECIFICATION REFERENCES i
1.
None.
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.m4 QEP 330-8 Revision 5
(' I HANDLING AND ANALYSIS OF POST October 1982
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ACCIDENT REACTOR COOLANT SAMPLES ID/3D A.
PURPOSE This procedure outlines the methods by which high activity reactor coolant samples may be analyzed with minimal personnel radiation exposure.
B.
REFERENCES 1.
CCP-0031..
2.
QEP 330-T6.
3.
QEP 330-T7.
C.
PREREQUISITES 1.
Obtain an operable, calibrated, high range exposure rate instrument.
2.
Obtain 0-5R and 0-1R direct-reading dosimeters.
3.
Obtain finger TLD-rings for both hands.
D.
PRECAUTIONS 1.
Minimize any direct contact between you and the sample.
2.
Sample hood flows should be maximized.
Close all hoods to 18 inches or less.
E.
LIMITATIONS AND ACTIONS 1.
Take all appropriate steps to insure that the radiation exposure you receive does not e:tceed 3 and 18-3/4 Rems to the whole body or extrem-ities, respectively, per quarter.
2.
Samples may be counted in the counting room on Ge(Li) detector //1 if the room is habitable or they may be counted on PARAPS located at the TSC.
3.
Shielded handling areas should be in readiness at the hot lab in case further dil.ution of samples is needed.
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4.
When using the Cutie Pie ionization survey instrument, it should be bagged to prevent noble gas intrusion into the ionization chamber.
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F.
PROCEDURE
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If the dose cate on the sample is minimal and no further dilution is
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needed; count che sample immediately at the TSC using PARAPS or in the
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counting room using Ge(Li) detector #1.
2.
Initiate procedure CCP-003,1 (BWR Coolant Radionuclide Analysis).
3.
After the isotopic analysis is complete, properly dispose of all refuse.
4.
If further dilution is required to perform the isotopic, take the sample to the hot lab using the freight elevator.
Complete steps F.5.
thru F.8 before performing an isotopic analysis.
5.
Equipment.
a.
Tongs.
b.
Lead bricks.
c.
Two hypodermic needles (about 18G x 2").
d.
Separatory funnel 100^ 31.
e.
Funnel.
f.
Flask with tabulation, 1000 al.
g.
Flask with tabulation, 500 ml.
h.
Erlenmeyer flask 1000 ml.
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J.
Tygon tubing, 1/4" ID.
k.
Hamilten connectors, Iver lock and male.
1.
One size 8 one hole stopper.
m.
One size 7 one hole stopper.
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One size 6 no hole stopper.
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Pipette, 1 ml.
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Pipette suction bulb.
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Ring stand with ring cla,mp.
6.
Build a sample cave made out of lead bricks in a radioisotope hood in the hot lab.
Use QEP 330-T6 as a guide. Set up the sample dilution 1
equipment as sho,wn in QIP 330-T7 (sample vial will be added later).
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Pour 1000 ml of demin water into both the separatory funnel and Erlen-meyer flask.
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Analysis.
..s a.
Place the two hypodermic needles into'the septum of the vial.
Make sure the needles touch the bottom of the vial.
b.
Turn on the lab vacuum pump and open the hood vacuum valve.
c.
Oper the stopcock on the separatory funnel. The demin water will.
move into and cut of the vial into the 1000 m1 flask.
d.
Turn off the lab vacuum pump and close the hood vacuum valve after the separatory funnel is empty of the 1000 ml I remin water, e.
Remove the stopper from the flask with the sample.
l f.
Pipette 1 ml of the diluted sample into the Erlenmeyer flask that l
it in compartment C (the Erlenmeyer flask should contain 1000 ml-of demin water).
g.
Place the size 8 no hole stopper on the Erlenmeyer flask and mix the contents. Use this dilution as the stock solution in further analyses.
9.
Follow-up.
(;3 a.
Insure that the Radiation-Cheniral Supervisor is promptly notified J
of:
(1) The results of the analysis.
(2) Personnel radiation exposure received.
(3) The disposition of associated material.
(4) The exposure rates observed in the various procedure phases.
G.
CHECKLISTS 1.
None.
H.
TECHNICAL SPECIFICATION REFERENCES 1.
None.
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QEP 330-10 Revision 2 C
ON-SITE ENVIRONMENTAL SAMPLING October 1982 DURING EMERGENCY SITUATIONS ID/5D A.
PURPOSE The purpose of this procedure is to outline the steps necessary to assure proper on-site environmental sampling during emergency situations.
B.
REFERENCES 1.
QEP 330-T8, On-Site Environmental Sampling Locations.
2.
EG-11, Environmental Sample Collection Procedures and Transport of Low-Specific Activity (<.002 pCi/g) Environmental Radiological Samples.
3.
QEP 550-T2, Operational Support Center Emergency Supplies Cabinet.
4.
Post Accident Radiation Levels - Quad-Cities Station, Sargent and Lundy.
C.
PREREQUISITES 1.
Only instruments calibrated within the frequency designated for those instruments should be used. The calibration due date shall be indicated on the instrument.
D.
PRECAUTIONS v
1.
Environmental dose rates during accident situations may be higher,than usual.
E.
LIMITATIONS AND ACTIONS 1.
The Radiation-Chemistry Director will instruct on-site health physics teams on which samples are needed.
2.
The equipment stored in the Operational Support Center (designated in QEP 550-T2) may be used for on-site environmental sampling if deemed necessary by the Radiation-Chemistry Director.
3.
When using the Cutie Pie ionization survey instrument, it should be bagged to prevent noble gas intrusion into the ionization chamber.
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PROCEDURE
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The health physics teams should be chosen by the Radiation-Chemistry
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-Lirector or his alternate from the Radiation Chemistry personnel
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assembled in the Operational Support Center (OSC). After completing assigned sampling, the teams will return to the 0.S.C.
2.
Sample locations will be chosen by the Radiation-Chemistry Director or his alternate using QEP 330-T8, On-Site Environmental Sampling Locations.
Sampling points are designated by a capital "X".
3.
All samples should be obtained using the procedures outlines in EG-11 unless otherwise specified by the Radiation-Chemistry Director. The Sample Collection Data Sheet in EG-11 should be used tc log all samples.
4.
Samples will usually be transported to the Technical Support Center, where they will be analyzed using the PARAPS analytical equipment located in the TSC storeroom.
G.
CHECKLISTS 1.
EG-11, page 8 - Sample Collection Data Sheet.
H.
TECHNICAL SPECIFICATION REFERENCES 1.
None.
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AREA RADIATION MONITOR SYSTEM QEP 330-T9 Revisiop 1 UNIT ONE October 1982
[
t STATION BUILDING ELEV COLUMN DETECTOR LOCATION RANGE READING j
NO.
t (MR/HR)
(MR/IIR) 739-1 Rx Bldg 690-6 Reactor Bldg Crane 0.1-1000 L
Rx Bldg 690-6 11 - 1 5 Refueling Floor Low Range
.01-100 2
Rx Bldg 690-6 H-15 Refueling Floor High Range 10-1,000,000 3
Rx Bldg 690-6 N-14 Refueling Floor Equip. Hatch 0.01-100 4
Rx Bldg 666-6 N-14 New Fuel Storage Area 0.0-1000 5
Rx Hldg 666-6 L-18-19 Contaminated Equipment Storage 0.01-100 6
Rx Bldg 647-6 M-15 Fuel Pool Pump Area 0.01-100 l
7 Rx Bldg 647-6 M-18 Control Rod Drive Storage & Repair Room 0.01-1000 8
Rx Bldg 647-6 J-17 Cleanup Instrument Rack Area 0.01-100 9
Rx Bldg 623-0 J-18-19 Clean:ip Pump Area 0.01-100 10 Rx Bldg 623-0 M-13-41 Mezzanine Floor Access Area 0.01-100 11 Rx Bldg 595-0 K-18-19 South CRD Module Area 0.01-100 12 Rx Bldg 595-0 K-13-14 North CRD Module Area 0.01-100 13 Rx Bldg 595-0 J-il-13 TIP Drive Area 0.01-100 14 Rx Bldg 595-0 11-14-15 TIP Cubicle 1-10,000 15 Rx Bldg 554-0 N-17 Torus Area 1-10,000 16 Rx Bldg 554-0 G-15 IIPCI Cubicle 1-10,000 17 Rx Bldg 554-0 G-14 RCIC Cubicle 1-10,000 18 Turb Bldg 639-0 E-25 Operating Floor Access - South 0.01-100 19 Turb Bldg 639-0 D-14 Operating Floor Elevator Area 0.01-100 20 Turb Bldg 626-6 C-20-21 Air Ejector Area - IB 0.01-100 21 Turb Bldg 626-6 C-18-19 Air Ejector Area - lA 0.01-100 22 Turh Bldg 623-0 G-25 Reactor Control Room 0.01-100 23 Turb Bldg 595-0 C Feedwater IIcater Area W. Itallway 0.01-1000 24 Turb Bldg 595-0 G-21 Feedwater Pump Area 0.01-100 25 Turb Bldg 572-6 D-18 Control Rod Drive Feed Pump Area 0.01-1000 j
26 Turb Bldg 547-0 D-E-19 Condensate / Booster Pump 0.01-100 27 Radwaste 597-0 C-14 Radwaste Control Room 0.01-100 l
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AREA RADIATION HONITOR SYSTEM QEP 330-T9 Revisio,n 1 UNIT ONE STATION BUILDING ELEV COLUMN DETECTOR LOCATION RANGE READING NO.
(HR/IIR)
(MR/IIR) i j
28 Radwaste 597-0 B-13-14 Radwaste Operating Area - South Wall 0.01-100 l
29 Radwaste 572-0 Radwaste Pump Room Access 0.01-100 30 Radwaste 620-0 Radwaste Centrifuge Access 0.01-100 l
1-1743A Rx Bldg.
690-6 N-15 Refueling Floor West Wall 1.0-1,000,000 1-1743B Rx Bldg.
690-6 11 - 1 4 Refueling Floor East Wall 1.0-1,000,000 1-1735A Turb Bldg.
658-10 G-H-16 Rx Bldg Vent System
.01-100 l-1735B Turb Bldg 658-10 G-II-6 Rx Bldg Vent. System
.01-100 31 Filter 574-6 Carbon Bed Vault 1.0-1,000,000 32 Turbine 648-6 CD-18 Recombiner Area Level 1
.01-100 33 Turbine 668-0 CD-18 Recombiner Area Level 2
.01-100 1
34 Hadwaste 605-0 Radwaste Catwalk Shield - East Wall 1-10,000 l
35 Radwaste 595-0 Radwaste North Truckbay - North Wall 0.1-1,000 l
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Revision 1 I
UNIT TWO STATION BUILDING ELEV COLUMN DETECTOR LOCATION RANGE READING NO.
(MR/HR)
(MR/llR)
?
I Rx Bldg.
690-6 11 - 1 1 Refuel'ng Floor Low R=.nge 0.01-g00 2
Rx Bldg.
690-6 11-11 Refue.iug Floor ifigh Range 10-10 l
3 Rx Bldg.
647-6 M-11 Fuel Pool Pump Area 0.01-100 l
4 Rx Bldg.
647-6 J-9 Cleanup Inst. Rack Area 0.01-100 5
Rx Bldg.
623-0 J-7-8 Cleanup Pump Area 0.01-100 6
Rx Bldg.
595-0 K-13 South CRD IIYD Area 0.01-100 7
Rx Bldg.
595-0 K-7 North CAD IIYD Area 0.01-100 j
9 Rx illdg.
595-0 11-11-12 Tip Cubicle 1-10,000 i
8 Rx Bldg.
595-0 H-13 Tip Drive Area 0.01-100 10 Rx Bldg.
554-0 N-9 Torus Area 1-10,000 11 Rx Bldg.
554-0 G-11 HPCI Cubicle 1-10,000 12 Rx Bldg.
554-0 G-12 RCIC Cubicle 1-10,000 13 Turb. Bldg.
639-0 F-1 Operating Floor 0.01-100 14 Turb. Bldg.
626-6 C-5 Air Ejector Area 0.01-100 15 Turb. Bldg.
626-6 C-8-9 Air Ejector Area 0.01-100 16 Rx Bldg.
666-6 N-17 Standby Gas Treatment Unit 1 0.01-100 17 Turb. Bldg.
595-0 C-7 Feedwater lleater Area 0.1-1000 18 Turb. Bldg.
595-0 G-5 Feedwater Pump Area o 61-100 19 Turb. Bldg.
595-0 D-13 Condensate Demin. Panel u.ol-100 20 Serv. Bldg.
595-0 Machine Shop Area
. -1000 21 Turb. lildg.
572-6 D-8 CRD Feedwater Pump Area 0.1-1000 22 Turb. Illdg.
547-0 E-7 Condensate Booster Pump Area 0.01-100 23 Rx illdg.
666-6 N-9 Standby Gas Treatment Unit 2 0.01-100 3
24 Serv. Bldg.
Service Bldg. Office 0.01-100 1-1743A Rx Bldg.
690-6 Refueling Floor 1.0-1,000,000 1-1743B Rx Bldg.
690-6 Refueling Floor 1.0-1,000,000 1-1735A Turb. Bldg.
658-10 Rx Bldg. Vent System
.01-100 1-1735B Turb. Bldg.
658-10 Rx Bldg. Vent System
.01-100 25 Filter Bldg.
574-6 Charcoal Vault 1.0-1,000,000 26 Turb. Bldg.
648-6 Recombiner Level 1
.01-100 27 Turb. Bldg.
668-0 Recombiner Level 2
.01-100 28 Filter Bldg.
Filter llouse Level 1
.01-100 29 Filter Bldg.
Filter llouse Level 2
.01-100 30 Fil ter lildg.
Filter llouse Level 3 Y d t>
.01-100
, (final)
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