ML20050D411

Public Version of Revised Emergency Plan Implementing Procedures,Including Procedure 330-6 Re Air Sampling Under Accident Conditions & 330-T2 Re Dose Factors for Gaseous Releases.Revised List of Assessment Actions Encl

ML20050D411
Person / Time
Site:	Quad Cities
Issue date:	03/10/1982
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20050D395	List: ML20050D407 ML20050D411
References
PROC-820310-01, NUDOCS 8204120188
Download: ML20050D411 (10)

Text

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QEP 330-0 Rsvision 10

.. Enrch 1982 ID/10,1P ASSESSMENT ACTIONS

/~ 330-0 k-)' Assessment Actions Rev. 10 03-10-82 330-1 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 Procedure Deleted Rev. 3 01-21-82 330-4 Estimation of Off-Site Dose from an Unplanned Release of Radioactive Effluents Rev. I 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. 2 03-10-82 330-7 In-Plant Iodine-131 Measurement During Post-Accident Conditions Rev. 4 03-10-82 330-8 Sampling, Handling, and Analysis -

of Post Accident Reactor Coolant Samples Rev. 2 05-18 330-9 -

Estimating Plant Release Using the Stack Gas Monitors Rev. 1 12-17-80 330-T1 Quad-Cities Statiet Environs Monitoring-Dairy Farms Rev. 1 06-20-80 330-T2 Dose Factors for Gaseous Releases Rev. 2 03-10-82 APPROVED 330-T3 Dose Factors for Liquid Releases Rev. I 12-17-80 MAR 101982 330-T4 p(_)c Main Chimney Release Rate Table Rev. I 12-17-80 Q. C. 0. S. R.

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8204120188 820329 ~I-PDR ADOCK 05000254 F PDR

QEP 330-0

'I Revision 10

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330-T5 Typical Gas Stack Monitor Calibration Curve Rev. I 12-17-80 330-T6 '

Sample Cave Rev. 1 05-18-81 330-T7 . ,

1 Sample Dilution Equipment Rev. 1 05-18-81 l

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QEP 330-6 Revision 2

- ( )) AIR SAMPLING UNDER ACCIDENT February 1982 CONDITIONS ID/3C A. PURPOSE This procedure outlines the methods by which airborne radioiodine samples and particulate samples are safely obtained under conditions of potentially extremely high radioiodine, noble gas, and particulate airborne concen-trations.

B. REFERENCES

1. GY-130 Silver Zeolite Technical Data Sheets.

2. H-809 VII Technical Data Sheets.

3. QRS 200-18.

4. QRP 100-28.

C. PREREQUISITES

1. Obtain an operable, calibrated, high range exposure rate instrument.

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2. Obtain 0-5R and 0-1R direct-reading dosimeters.

3. Obtain finger TLD-rings for both hands.

4. Obtain RADeC0 H-809 high volume air sampler with combination cartridge-filter head, 47 mm glass fiber filter paper, and GY-130 Silver Zeolite cart ridge.

5. Obtain Self Contained Breathing Apparatus, if necessary.

D. PRECAUTIONS

1. Minimize direct contact be tween you and the sample.

2. Take care to avoid contaminating the sampling media.

3. Plan all phases of the operation prior to entering any high radiation exposure rate areas.

4 Insure that the instrument has been calibrated.

5. The air sampler should not be used in the variable mode.

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-ities . respectively, per quarter.

QEr 330-6

1. Revision 2 i

2. This procedure should only be used in such cases when QRP 100-28, Air Sampling of Suspected Radioactive Airborne Areas, is rendered useless

(} by conditions in the plant.

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-13d Silver Zeolite cartridge. Draw an arrow on the side of the cartridge pointing in the direction of the flow.

3. Load the filter paper and the cartridge into the combinations 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 snount 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.

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NOTE A 1 minute ' sample should be adequate to A P P RCTV ED assess radioiodine concentrations that would require respiratory protective measures, if 1 01982 isotopic analysis is available. If conditions allow, a 5-minute sample should be taken to Q' CL O' S* R*

assure more accurate results for bo th radio-iodine and particulate analysis.

8. When the sample is completed note the flow rate and time, and turn the sampler of f.

9. Return the cartridge and filter paper to the designated area for analysis.

10. The CY-130 silver zeolite cannisters display a low retention for nobic 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 specific  :

information on the cannister ef ficiency be needed.

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t QEP 330-6 Revision 2

12. Perform the analysis as specified by QRS 200-18. 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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APPROVED' MAR 101982 Q.C.O.S.R.

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QEP 330-7 ,

Revision 4 )

February 1982

( ') IN-PLANT 10 DINE-131 MEASUREMENT DURING POST-ACCIDENT CONDITIONS ID/3F A. PURPOSE The pa rpose of this procedure is to outline the methods for meas 2 ring 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 NUREU-0578.

C. PREREQUISITES

1. Obtain self-contained breathing apparatus, if necessary.

D. PRECAUTIONS

, 1. Verify that while perfonning this procedure, radiation levels are

(_ monitored.

\l 2. Measure sample cartridges for radiation level to insure samples are safe to handle.

3. Based upon the analyses of Reference 1, exposure rates under post-accident conditions may severely limit residence time in many plant locations.

In particular, the following areas should be carefully assessed prior to I-131 sampling and analysis.

a. All of the reactor building.

b. Turbine building elevation 639' .

APPF0DVED

c. Turbine building be tween units, elevation 611' 6".

NU;R 101982

d. HPCI access tunnel.

Q.CL O.S. R.

E. LIMITATIONS AND ACTIONS

1. 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 area uhere airborne I-131 is present.

2. This procedure assumes a sample volume of 30 f t3 If another volume

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is used, adjust jhe 4100 net peak area accordingly. A 4100 ngt peak

(~T area for a 30 ft sample is equal to 1 MPC for I-131, 9 X 10 uci/cc.

b)

, QEP 330-7 R: vision 4 I

F. PROCEDURE

l j 1. Equipment needed.

a. Post-Accident Radionuclide - Analysis Portable System (PARAPS).

b. Portable air sampler.

c. Silver zeolite' cartridge.

d. Glass fiber filter paper.

2. Start up of the detection system.

a. Turn on the AC line conditioner.

b. Turn on the nim bin power supply. f f

c. Turn power on to the detector bias supply.

d. Using the 10 turn pot on the bias supply, raise the voltage to 3,000 volts. ,

e. Turn the 11/34 computer power switch to the "DC ON" position.

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.

6. Initialize the system using the Automated Analytical Instrumentation System's (AAIS) Central System Procedure (CSP).

7. Set the system prime using the AAIS's CSP. APPROVED

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MAR 101982 Q. C. O. S. H.

r QEP 330-7 Revision 4 l

i 8.~ Log on the sytem using the AAIS's CSP.

() 9. Determine the iodine 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".

APPRCn/ED

12. Depress "600" on the data entry pad.

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13. Depress " ENTER".

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14. Depress "STOP".

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. l

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 channel it will become brighter.

a. If you make a mistake depress " CLEAR" and remove the highlight 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.

25. 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).

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.

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1. ' QEP 330-7 lL Revision 4 1 .

26. If another sample is to be analyzed, repeat steps 14 through 25.

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G. CHECKLISTS 1." None.

i H. TECHNICAL SPECIFICATION REFERENCES i

i 1. None.

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APPROVED MAR 101982- i Q.C.O.S.R.

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-J QEP 330-T2 Revision 2 ID/2U DOSE FACTORS FOR GASEOUS RELEASES February 1982 Total Dose (mrem) = Dose Factor (mrem)

Ci X Release (Ci) X Distance Correction Factor Dose Factors (mrem /Ci) (1)

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Release Type Organ Rx. Bldg. Vent or (Characteristic Radionuclides) of Interest Chimney Release Ground Level Release Noble Gases Whole Body 0.001 0.02 Iodine Thyroid 8. 355.

l Distance Correction Factors i Site Boundary Release Mode ( mi) 1/2 1 mi 2 mi _5 mi 10 mi i

Chimney 1.0 0.4 .07 .04 0.02 0.01 Rx. Bldg. Vent / Ground Level 1.0 0.6 .3 .2 0.07 0.03 4

(1) Total dose at site boundary for short term release assuming worst case meteorology.

(2) Factors are for inhal stion pathway. Milk pathway is significantly higher if contamined milk is drunk over a two week period.

APPRCh/E D MAR 101982

.Q.c.o.s.a (final)

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