ML20041E946
| ML20041E946 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 01/29/1982 |
| From: | WISCONSIN ELECTRIC POWER CO. |
| To: | |
| Shared Package | |
| ML20041E944 | List: |
| References | |
| PROC-820129-01, NUDOCS 8203150328 | |
| Download: ML20041E946 (80) | |
Text
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l 01-29-82 ts kJ TABLE OF CONTENTS Revision Date 1.0 CLASSIFICATION AND ASSESSMENT 1.1 Initial Classification 0
03-31-81 1.2 Plant Status 0
03-31-81 1.3 Estimation of Source Term..........
0 03-31-81 1.4 Radiological Dose Evaluation 2
09-04-81 1.5 Protective Action Evaluation 1
05-15-81 1.6 Radioiodine Blocking and Thyroid Exposure Accounting 0
03-31-81 2.0 UNUSUAL EVENT IMPLEMENTING PROCEDURES 2.1 Unusual Event - Immediate Actions......
0 03-31-81 2.2 Unusual Event - Plant and Company Personnel Notification...............
1 07-01-81 2.3 Unusual Event - Off-Site Agency Netification 0
03-31-81
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3.0 ALERT IMPLEMENTING PROCEDURES
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3.1 Alert - Immediate Actions.......
0 03-31-81 3.2 Alert - Plant and Company Personnel Notification 1
07-01-81 3.3 Alert - Off-Site Agency Notification 0
03-31-81 4.0 SITE EMERGENCY - IMPLEMENTING PROCEDURES 4.1 Site Emergency - Immediate Actions 0
03-31-81 4.2 Site Emergency - Plant and Company Personnel Notification 1
07-01-81 4.3 Site Emergency - Off-Site Agency Notification 0
03-31-81 5.0 GENERAL EMERGENCY - IMPLEMENTING PROCEDURES 5.1 General Emergency - Immediate Actions.
0 03-31-81 5.2 General Emergency - Plant and Company Personnel Notification 1
07-01-81 5.3 General Emergency - Off-Site Agency Notification 0
03-31-81 6.0 EVACUATION 6.1 Limited Plant Evacuation 0
03-31-81 6.2 Plant Evacuation 0
03-31-81 O
6.3 Exclusion Area Evacuation.
0 03-31-81
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6.4 Energy Information Center Evacuation 0
03-31-81
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8203150320 020309 PDR ADOCK 05000266 F.
PDR j
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s Revision Date 7.0 CHEMISTRY & HEALTH PHYSICS RESPONSE AND PREPAREDNESS 7.1 Internal Chem & HP Group Personnel Notification /
Initial Response 7.1.1 Chem & HP Group Personnel Notification and Initial Response when Chem & HP Personnel are On-Site 0
03-31-81 7.1.2 Chem & HP Group Personnel Notification and Initial Response when Chem & HP Personnel are Off-Site.
0 03-31-81 7.1.3 HP Protective Actions by Operations Personnel Prior to Arrival of Chem
& HP Group Personnel.......
1 05-15-81 7.2 Health Physics Facility Activation 7.2.1 Activation of HP Facilities at Site Boundary Control Center 1
09-04-81 7.2.2 Activation of HP Facilities at Operations Support Center 0
03-31-81 7.2.3 Activation of HP Facilities at...
)
1 09-04-81 f
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7.2.4 Health Physics Communications 0
03-31-81 7.2.5 Control and Use of Vehicles 0
03-31-81 7.3 Radiological Surveys 7.3.1 Airborne Sampling and Direct Dose Rate Survey Guidelines......
2 09-04-81 l
7.3.2 Post-Accident Sampling and Analysis of Potentially High Level Reactor Coolant 3
12-30-81 7.3.3 Post-Accident Sampling of Contain-ment Atmosphere 3
12-30-81 7.3.4 Movement of Required Chemistry Equip-ment and Material to the Technical Support Center Counting Room and Mini-Laboratory 0
12-30-81 7.4 Emergency Equipment 7.4.1 Routine Check, Maintenance, Cali-bration and Inventory Schedule for l
Health Physics Emergency Plan Equipment 3
01-29-82 i
7.4.2 Emergency Plan Equipment Routine l
)
Check, Maintenance and Calibration l
s._s' Instructions.
2 07-01-81 7.4.3 Use of Baird Model 530 Single Channel Iodine Spectrometer to Determine Airborne Iodine Activities...
1 05-15-81
Page 3
)i Revision Data l
7.4.4 AMS-2 Air Particulate, Iodine and Noble Gas Sampler / Detector.
0 03-31-81 8.1 Personnel Assembly and Accountability.
0 03-31-81 9.1 Security 0
03-31-81 10.0 Firefightin]
0 03-31-81 11.0 FIRST AID AND MEDICAL CARE l
11.1 On-Site First Aid Assistance A
10-23-81 11.2 Injured Person's Immediate Care.
1 05-15-81 11.3 Hospital Assistance.
0 03-31-81 11.4 Personnel Decontamination.......
0 01-29-82 12.0 REENTRY AND RECOVERY PLANNING 12.1 Reentry Procedures for Emergency Operations 0
03-31-81 12.2 Personnel Exposure and Search and Rescue Teams.
0 03-31-81 12.3 Recovery Planning..............
0 03-31-81 12.4 Personnel Monitoring Exposure Guidelines.
0 01-29-82 g
N.
13.0 PRESS 1
09-04-81 f
13.1 Crisis Communications...
14.0 COMMUNICATIONS 14.1 Testing of Communications Equipment.
0 03-31-81 15.0 TRAINING, DRILLS AND EXERCISES t
15.1 Employee Training.
1 09-04-81 15.2 Off-Site Personnel Training.........
0 03-31-61 15.3 Drills and Exercises 1
05-15-81 16.0 WISCONSIN ELECTRIC GENERAL OFFICE PROCEDURES l
16.1 Nuclear Engineering Section Notification and
Response
3 09-04-81 I
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EPIP 7.3.2 O
MINOR f
Revision 3 12-30-81 POST-ACCIDENT SAMPLING AND ANALYSIS 0F POTENTIALLY HIGH LEVEL REACTOR COOLANT
?
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1.0 INTRODUCTION
1.1 This procedure outlines the steps necessary to collect, handle and analyze a high level reactor coolant sample which could result from gross fuel failure.
1.2 Equipment Lict Set up the following in the primary sample hood prior to collecting your sample:
1.2.1 The equipment detailed in Figures 2A and 2B, with the exception of the sample bomb.
/'~'g 1.2.2 Two magnetic stirrers and two 50 ml poly beakers and a 50
(
)
ml beaker.
1.2.3 A pH/mv meter, pH probe and chloride / reference elec-trodes.
1.2.4 A piston burette.
1.2.5 A lead brick wall of sufficient size to store residue from analysis.
1.2.6 Chemical transfer pump.
1.2.7 Remote handling tools located in the cabinet below the hood.
1.2.8 Prepare a 1.0 liter sidearm flask with a correctly sized solid stopper and rubber septum over the sidearm.
I 1.2.9 Gas syringe The following equipment is also necessary for this procedure I
and need to be made ready.
1.2.10 The gas partitioner for H2 analysis.
EPIP 7.3.2
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Page 2 1.2.11 The special cart used for transport of the sample bomb.
1.2.12 Tcols for connecting and disconnecting sample bomb; i.e.,
11/16" open end wrench or equivalent.
1.2.13 Remote valve turning tool. This tool as well as those mentioned in Step 1.2.12 are necessary for sampling and should be taken along and placed on the sample bomb transport cart.
The following reagents are also necessary and need to be prepared.
1.2.14 0.1N NaOH for boron. Obtain a supply from normal boron analysis.
1.2.15 2.0M HNO3 for chloride analysis.
1.2.16 Manitol for boron analysis.
1.3 Preliminary Steps Initials 1.3.1 Standardize the pH meter.
f 1.3.2 Organize as much of the equipment as possible
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behind lead brick walls in an arrangement that allows for unobstructed view of all operations with the aid of the convex mirror.
(See Figure 2.)
1.3.3 Put new rubber septum on gas bomb.
1.3.4 condition and check out chloride / reference electrodes.
1.3.5 Check out and prime the piston burette with fresh 0.1N NaOH solution.
1.3.6 Check out the operation and calibration of the chemical transfer pump by pumping chloride free deionized water through the pump.
2.0 PRELIMINARY EVALUATION l
NOTE: THIS EVALUATION SHALL BE COMPLETED PRIOR TO ANY ATTEMPT TO ENTER THE AUXILIARY BUILDING OR SAMPLE ROOM TO OBTAIN A REACTOR COOLANT SAMPLE UNDER EMERGENCY CONDITIONS.
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2.1 Possible Indication of Fuel Damage Initials t
Some or all of the following would be present if fuel damage had occurred:
2.1.1 The letdown radiation monitor (R9) would be unusually high or offscale.
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l EPIP 7.3.2
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Page 3 2.1.2 The containment radiation monitors (R11 and R12) would be unusually high or offscale.
2.1.3 The containment area monitors (R2 and R7) would be reading unusually high or offscale.
2.1.4 The auxiliary building stack monitor (R14) would f
show a significant increase due to auxiliary building airborne activity fron the letdown and charging pump areas.
2.1.5 Evaluation of Sample Room Conditions a.
The sample room area monitor (R6) and charging pump area monitor (R4) would give an indication of conditions in the auxiliary building and sample room.
b.
After evaluation of the radiation monitoring system readouts, Health Physics will determine what airborne and radiation surveys would be appropriate before auxiliary buildir g entry.
t c.
Verify the requirements for auxiliary building sample room entry, i.e.,
(1) RWP requirements, (2) clothing requirements, (3) respiratory requirements, and (4) dosimetry requirements including extremity dose monitoring requirements, and (5) health physics coverage requirements including timekeeping.
3.0 REACTOR COOLANT SAMPLING PROCEDURE NOTE: THIS PROCEDURE SHALL NOT BE INITIATED UNTIL THE EVALUATIONS DIS-CUSSED IN SECTION 2.0 HAVE BEEN COMPLETED AND REVIEWED BY DUTY &
CALL SUPERINTENDENT (COORDINATOR), DUTY HEALTH PHYSICS SUPERVISION AND THE DUTY SHIFT SUPERVISOR, AND THEIR APPROVAL HAS BEEN GRANTED.
3.1 Collecting a Pressurized Sample (Refer to Figure 1)
Initials NOTE:
THE FOLLOWING STEPS WILL BE ACCOMPLISHED UNDER THE DIRECTION OF HEALTH PHYSICS SUPERVISION AND ONLY AFTER COMPLETING SECTION 1.0 0F THIS PROCEDURE.
i 3.1.1 The following steps (a through f) must be accomplished before opening the incontainment sample isolation valve 955 (Step 3.1.2) and the hot leg sample isolation valve 966C (Step 3.1.3).
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EPIP 7.3.2
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a.
Verify that the demineralized water header pressure is approximately 100 to 120 psi.
i NOTE:
THIS STEP MAY BE DELETED IF REACTOR MAKEUP WATER IS USED FOR THE FLUSH.
b.
Proceed to the sample room and install the shielded sample bomb on the outside wall of the sample room using the fittings provided.
CAUTION: BEFORE REMOVING THE SWAGE LOCK CAPS
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TO INSTALL THE BOMB,~OPEN VALVES 939, 940 AND 941 TO RELIEVE SYSTEM PRESSURE.
CLOSE VALVES 939, 940 AND 941.
PLACE A WASTE BUCKET DIRECTLY UNDER THE BOMB. USE A PAPER TOWEL SHIELD AND RUBBER GLOVES WHEN REMOVING CAPS.
After installing the bomb verify that the dimineralized water line is connected from valve 945 to the demineralized water manifold. Open demineralized H O valves 2
' v 945, 947, and 948 and check for leaks on the bomb fittings.
Shut valves 945, 947, and 948.
c.
Enter the sample room and close the following valves on the sample panel.
- 1. 961C - Normal hot leg sample bomb inlet.
- 2. 964C - normal hot leg sample bomb outlet.
- 3. 965C - normal hot leg sample bypass.
- 4. 968 - normal hot leg return valve.
- 5. 971 - normal hot leg sink sample valve.
r d.
Open the following valves on the sample panel.
- 1. 969A - sample system purge to volume control tank.
- 2. 956C - normal hot leg sample supply valve.
[V) 3.
990 - residual heat removal sample supply valve.
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EPIP 7.3.2 Page 5
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\\d e.
Open valve 938 (high level hot leg sample valve) located on the wall behind the sample panel.
f.
Leave the sample room and open the following valves on the sample roem wall.
- 1. 939 - sample bomb inlet.
(Wide Open)
- 2. 940 - sample bomb bypass. (Wide Open)
- 3. 941 - sample bomb outlet. (Wide Open)
NOTE:
FOR DRILLS AND PRACTICE OPEN VALVE 941 ONLY ONE-QUARTER TURN TO ELIMINATE N-16 GAMMAS.
3.1.2 Open the incontainment hot leg sample isolation valve (valve 955) and the residual heat removal 5 ample isolation valve (valve 959) by means of the switches located outside the No. 1 pipeway for Unit 1 or No. 4 pipeway for Unit 2.
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If the valve No. 955 will not open because of containment isolation, perform the following steps (1 through 3).
1.
Request that the Control Room reset the con-tainment isolation signal.
e t
2.
Turn the local control switch positions for i
valves 951, 953, and 955 to the "close" position.
3 3.
Turn the local control switch for valve 955 to the "open" position.
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NOTE: SECTION 3.1.2 MUST BE ACCOMPLISHED BEFORE
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SAFETY INJECTION RECIRCULATION HAS BEGUN.
l 3.1.3 Leave the area and request control room supervision to open the hot leg sample isolation valve (966C).
3.1.4 Verify sample flow b'y radiation level.
l 3.1.5 After a recirc time of 30 minutes, return to the sample station and using the remote valve
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operating tool, fully open valves 9B and 9A and
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8A and 8B.
l a.
Slowly and completely close valve 940.
i EPIP 7.3.2 Page 6 r
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b.
Leave the primary auxiliary building.
NOTE: THE VALVE OPERATING TOOL SHOULD BE USED TO OPERATE ALL VALVES EXCEPT 945, 946, 947 AND 948 (FLUSH VALVES).
3.1.6 After 15 additional minutes, return to collect the sample. Close valves 9B and 9A and then valves 8B and 8A using the remote valve operating tool. Make "ete of the sample collection time.
NOTE: DO NOT DISCONNEC1 N SAMPLE BOMB UNTIL SAMPLE FLOW IS SECehED AND THE DI FLUSH IS COMPLETE AS EVIDENCED BY REDUCTION IN RADIATION LEVELS.
3.1.7 Request control room supervision to immediately close the hot leg sample isolation valve 966C.
NOTE:
IT IS VERY IMPORTANT THAT THE HOT LEG SAMPLE ISOLATION VALVE 966C IS CLOSED PRIOR TO STARTING THE DI FLUSH. WAIT FOR CONFIRMATION FROM THE CONTROL ROOM.
4.0 SAMPLE LINE FLUSHING 4.1 Leave valve 939 open, and fully open valves 940 and 941.
Open valves 945 and 946. Allow the lines to flush for at least 15 minutes. Do not remain in the area of the sample station during this flush.
4.2 After about 15 minutes return and measure radiation levels.
If a chemistry & Health Physics Supervisor determines that the levels are satisfactory, close valve 946 and valve 939 using the remote valve tool.
Then open valve 947 and valve 948 and allow about a 15-minute DI flush.
4.3 After about 15 minutes, close valves 940 and 941 with the remote valve tool and then close valves 945, 947, and 948.
Disconnect valve 945 from the demineralized water manifold and cap both ends. Disconnect the sample bomb from the l
fittings using a paper towel to prevent spraying.
Remove the shielded saruple bomb from its support.
Remove excess liquid from the top and bottom bomb fittings with a syringe and dispose behind lead shielding. Replace the Swagelok caps on the wall fittings and on the bomb.
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EPIP 7.3.2 Page 7 i
Transport the bomb, remote valve tool and wrenches to the chemistry lab on a cart.
NOTE:
AFTER DRILLS AND PRACTICE RUNS, RETURN ALL
[
EQUIPMENT AND VALVE LINEUPS TO NORMAL AS FOLLOWS:
CLOSE VALVES:
1.
966C - Containment hot leg sample isolation t
valve 2.
961C - Normal hot le ; sample bomb inlet i
i 3.
964C - Normal hot leg sample bomb outlet j
4.
965C Normal hot leg sample bypass 5.
971 - Normal hot leg sink sample valve 6.
938 - High level hot leg sample valve j
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7.
939 - High level sample bomb inlet r
E 8.
940 - High level sample bomb bypass x-4 9.
941 - High level sample bomb outlet
- 10. 945, 946, 947, 948 - Demineralized water p
flush valves NOTE:
DISCONNECT VALVE 945 FROM THE DEMINERALIZED WATER MANIFOLD. ADVISE CONTROL TO REDUCE DEMINERALIZED WATER HEADER PRESSURE TO l
NORMAL.
OPEN VALVES:
1.
956C - Normal hot leg sample supply valve.
2.
968 - Normal hot leg return valve f
3.
969A - Sample system purge to volume control tank 5.0 SEPARATION OF THE PRESSURIZED SAMPLE AND ANALYSIS OF THE GASEOUS l
AND LIQUID COMPONENT (Refer to Figures 2A and 2B) 5.1 Collecting the Gaseous Sample From the Pressurized Sample 5.1.1 Place the shielded sample bomb in the sample t
holder in the primary sample hood.
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t EPIP 7.3.2 q
Page 8 (0
i 5.1.2 connect the sample bomb to the shielded gas collection bomb by means of the fittings provided.
Place lead bricks in the area of this connection for shielding.
5.1.3 Connect the valve manifold to the opposite end of i
the sample bomb and verify that valve 11 on the manifold is open.
5.1.4 Make sure that the vacuum line is attached to the gas collection bomb at the valve 1 location.
Open valves 1 and 2.
Secure valve 3.
Evacuate the gas bomb and connecting lines. With vacuum still on, secure valve 1.
Secure vacuum.
5.1.5 Before proceeding, make sure no inleakage has occurred into the gas bomb by observing the vacuum gauge reading.
Using the remote valve tool, fully open valves 9A and 9B.
Open valve 8A one-quarter turn.
Crack open valve 8B and control degassing by throttling valve 8B.
Allow the system to degas for 5 minutes.
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Fully open valves 9A and 9B, 8A and 8B.
Close valve 2.
(s NOTE: OBSERVE THE VACUUM GAUGE.
IT SHOULD RISE VERY SLOWLY.
IF THE RISE IS TOO RAPID, CLOSE VALVE 8B SLIGHTLY.
RISE SHOULD BE i
5" HG/ MIN.
5.2 Analysis of Gaseous Sample l
5.2.1 Hydrogen t
Use a syringe to draw a 1 cc sample.
Use the injection port on the gas partitioner for this analysis.
5.2.2 Radioactive Noble Gas Use a syringe to draw a 1/2 cc sample and inject this into the flask prepared in Section 1.2.8.*
Allow 30 minutes for thermal mixing. Draw a 1/2 cc sample of this dilution and proceed as normal.
l
- Additional dilution should be performed if i
the contact reading is >l mr/ hour.
t k _,,
NOTE:
SEE SECTIONS 7.0 AND 8.0.
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EPIP 7.3.2 m
Page 9 a
5.3 Collecting the Liquid Sample From the Pressurized Sample 5.3.1 Add one drop of 2 M nitric acid (per 10 ml of sample) to the chloride beaker for pH adj us bnent.
NOTE:
IT IS EXTREMELY IMPORTANT TO VERIFY THAT VALVE 2 HAS BEEN CLOSED BEFORE PROCEEDING.
5.3.2 Open valve 3 slowly. Allow the liquid sample to drain into the 50 ml beaker.
Direct a slow stream of air through the vent line on valve 3 if necessary to recover the total liquid sample.
5.3.3 Close valves 8A and 8B, 9A and 9B, and valve 3.
5.4 Analysis of Liquid Samples 5.4.1 Boron /pH Analysis a.
Transfer a 5 ml sample using the chemical transfer pump into a 50 ml poly beaker containing a stir bar.
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NOTE: OBSERVE THE TRANSFER PUMP OPERATION.
WHEN SAMPLE BEGINS TO ENTER THE BEAKER', THE TRANSFER RATE IS 0.5 ML/SECOND OR 10 SEC = 5 ML.
b.
After transfer is complete, record the pH.
c.
Plug in the magnetic stirrer, add mannitol, and proceed with the boron analysis.
NOTE:
IF THE PRIMARY SYSTEM HAS BESN BORATED, 5 ML OR MORE OF TITRANT MAY BE NEEDED TO REACH AN ENDPOINT.
NOTE: AFTER DRILLS AND PRACTICE RUNS, THE l
BORON TITRATOR MUST BE FLUSHED WITH DEIONIZED WATER AND PUT IN DRY LAY-UP.
ALL ELECTRODES SHOULD BE PLACED l
IN LAYUP SO THEY ARE CONDITIONED FOR IMMEDIATE USE.
5.4.2 Chloride Analysis Transfer the remainder of the sample to the l' }
second poly beaker containing the chloride
( _,/
electrode. Start the stirring action and record l
l
EPIP 7.3.2 Page 10 the potential. Use the calibration curve for the chloride electrode to determine chloride concentration.
NOTE: CHLORIDE SAMPLE MUST BE pH ADJUSTED.
SEE STEP 5.3.1.
NOTE: HIGH LEVELS OF RADI0 ACTIVE IODINE IN THE COOLANT WILL INTERFERE WITH THE CHLORIDE ANALYSIS. REFER TO THE ATTACHED IODINE /
CHLORIDE CORRECTION CURVE (ATTACHMENT 7.3.2-1) TO MAKE THE PROPER ADJUSTMENT TO THE CHLORIDE ELECTRODE ANALYSIS.
5.4.3 Iodine Analysis and Gamma Scan Using the specially prepared 2 cc syringe, with-draw 0.3 cc of the sample from the poly beaker used for the chloride analysis and inject this sample into a 1000 ml poly bottle containing demineralized water. Make additional dilutions in the same manner.* Count as normal.
- Additional dilution should be performed until the contact reading is <1 mr/ hour.
NOTE: SEE SECTIONS 7.0 AND 8.0.
5.5 Reporting of Results Complete and forward Reactor Coolant Post-Accident Sampling Analysis Report (EPIP-30).
6.0 SAMPLE RESIDUE Place all sample residue in the specially prepared lead pig for l
disposal.
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7.0 SAMPLES TAKEN TO KEWAUNEE NUCLEAR PLANT FOR COUNTING 1
Reference:
Post-accident counting agreement with Wisconsin Public Service, Kewaunee Nuclear Plant.
l Kewaunee Nuclear Plant does not utilize the 5 cc glass vial and 1 cc test l
tube geometries. Therefore, " normal" samples will have to be diluted and placed in one liter poly bottles if they are sent to the Kewaunee Nuclear Plant for analysis.
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EPIP 7.3.2 Page 11 l
l 8.0 LABELING OF SAMPLES Label all chloride, noble gas, iodine and gamma scan samples with all pertinent information such as:
sample number, name of sample, date and l
time of sampling, sample volume and dilution (s).
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I EPIP 7.3.2 p
Page 12 i
ATTACHMENT 7.3.9.-1 CORRECTION FOR REACTOR COOLANT IODINE INTERFERENCE WITH CHLORIDE ELECTRODE RESPONSE
1.0 INTRODUCTION
Chloride as determined by the chloride specific ion electrode is subject to interference caused by the presence of high levels of other halogens, specifically iodine. The following procedure outlines the method used to estimate the correction for this interference.
2.0 PROCEDURE 2.1 Measure the chloride concentration using the chloride specific ion electrode.
2.2 Perform the iodine analyses as outlined in Section 5.4.3 of this procedure.
2.3 Convert the iodine concentration to ppm using the following conversion factors.
i Isotope pCi/cc + ppm Conversion Factor r&
I-130 2.54 X 10 5 I-131 3.85 X 10 4 I-132 4.71 X 10 6 I-133 4.23 X 10 5 I-134 1.78 X 10 8 I-135 1.38 X 10 5 2.4 Sum the concentration, in ppm, of each iodine isotope and use the attached curve to determine the estimated chloride concentration i
correction factor.
3.0 EXAMPLE Reactor Coolant Analysis Estimated i
Isotope Concentration (pCi/cc)
Conversion Factor Concentration (ppm) pCi/cc X
3.85 X 10 4 9.86 X 10 1 I-131 2.56 X 103 pCi/cc X
4.23 X 10 5 6.13 X 10 3 I-133 1.45 X 102 l
pCi/cc X
1.38 X 10 5 7.80 X 10 2 i
I-135 5.65 X 103 TOTAL 1.07 ppm i
Chloride concentration from correction curve (ppm) = 0.42 ppm j
i s _,-
Subtract this value from the chloride concentration determined by the s
chloride electrode.
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f EPIP 7.3.3 MINOR Revision 3 12-30-81 POST-ACCIDENT SAMPL7.NG OF CONTAINMENT ATMOSPHERE
1.0 INTRODUCTION
This procedure outlines the steps necessary to collect, handle and analyze a potentially high radioactive containment atmosphere sample resulting from gross fuel failure and loss of reactor coolant system integrity to determine hydrogen and radioactive gas concentrations.
2.0 PRELIMINARY EVALUATION NOTE: THE FOLLOWING EVALUATION SHALL BE COMPLETED PRIOR TO ANY ATTEMPT TO ENTER THE FACADE OR R11/R12 CUBICLE TO PERFORM A VALVE LINEUP OR COLLECT A CONTAINMENT ATMOSPHERE SAMPLE.
2.1 Indications of Possible Fuel Damage Some or all of the following would be present if fuel damage or loss of reactor coolant system integrity had occurred:
2.1.1 The letdown radiation monitor (R9) would be unusually high or offseale.
2.1.2 The containment radiation monitors (R11 and R12) would be unusually high or offscale.
2.1.3 The containment area monitors (R2 and R7) would be unusually high or offscale.
2.1.4 The automatic actions of E0P-1A have caused containment isolation.
2.2 Evaluation of Radiological Hazards in Access Areas Required for Sampling Initials 2.2.1 After evaluation of the radiation monitoring system readouts, verify with Health Physics that the appropriate airborne and radiation surveys have been made before entering the facade.
A.
I f
I l
. 1
EPIP 7.3.3
~~ N Page 2 l
t 2.2.2 Verify the requirements for facade and R11/R12 cubicle entry.
a.
Radiation work permit requirements b.
Clothing requirements i
c.
Respiratory requirements d.
Dosimetry requirements including extremity dose monitoring e.
Health physics coverage requirements including timekeeping
[
f 3.0 CONTAINMENT ATMOSPHERE SAMPLING PROCEDURE NOTE: THE FOLLOWING PROCEDURE SHALL NOT BE INITIATED UNTIL THE EVALUATION DISCUSSED IN SECTION 2.0 HAS BEEN COMPLETED.
THE DUTY & CALL SUPERINTENDENT (COORDINATOR), THE DUTY AND CALL HEALTH PHYSICS SUPERVISOR AND THE DUTY SHIFT SUPERVISOR O
SHALL APPROVE THE IMPLEMENTATION OF THIS PROCEDURE. THE FOLLOWING STEPS WILL BE ACCOMPLISHED UNDER THE DIRECTION OF HEALTH PHYSICS SUPERVISION.
3.1 Valve Lineups 3.1.1 The containment atmosphere sample will be collected using the R11/R12 sampl,ing system.
i 3.1.2 Entry to the facade shall be from the potable water room (Unit 1) or the non-nuclear room (Unit 2).
3.1.3 Verify with the control room that the contain-ment isolation valve is secured and the A0V's (3200A&B) in the R11/R12 cubicle are closed and the pump i.s secured.
3.1.4 Enter the R11/R12 cubicle:
(Refer to Figure 1.)
a.
Open valves 3200J and 3200L and close 3200M.
l b.
Verify that the continuous vent valve l
32005 and 3200W is closed.
c.
Close valve 3200K.
't SPIP 7.3.3
[
Page 3 3.1.5 Hook the 100' service air hose to the Chicago fitting on the elevator side of the R11/R12 cubicle established for sampling line purging.
Verify that valve 3200Y is close,d.
NOTE: THE 100' HOSE IS STORED INSIDE THE UNIT 1 R11/R12 CUBICLE ALONG WITH THE PRESSURE REGULATOR.
3.1.6 Return to the room mentioned in Step 3.1.2 with the air hose and pressure regulator.
3.1.7 Hook up the service air hose to an available outlet in the turbine hall using the pressure regulator designed for this procedure.
Use suitable pins to lock the Chicago fitting in place.
3.1.8 Verify with the control room that the R11/R12 monitor is lined up to monitor and discharge to containment atmosphere.
3.1.9 Request control room supervision to open the suction and discharge (A0V's) isolation valves and start the pump.
3.1.10 Verify sample flow by increased radiation levels.
3.1.11 Allow five minutes for sample recircing.
Request control room supervision to stop the pump and close all suction and discharge (A0V) isolation valves.
3.2 Sample Collection 3.2.1 Enter the facade and proceed to the sample point.
Take along two 2 cc gas syringes in a hollowed-out lead brick.
CAUTION:
CONTAINMENT PRESSURE COULD THE0RETI-CALLY BE AS HIGH AS 60 PSIG. HOLD THE SYRINGE PLUNGER SECURELY. ALSO, LOCK THE GAS SYRINGES BEFORE WITH-DRAWING FROM THE SAMPLING SEPTUM, USING THE BUILT-IN LOCKING DEVICE i
ON THE SYRINGE.
l 3.2.2 Remove the set screw and take one 1/2 cc and l
one 1 ce gas sample.
Place the syringes in the lead brick.
k
EPIP 7.3.3 Page 4
^
(
3.2.3 Replace the set screw and open valve 3200Y.
3.2.4 Leave the facade and return to the room mentioned in Section 3.1.2.
3.3 Sample Line Purging 3.3.1 Open service air valve and adjust the pressure to a setting of 10 psig greater than measured containment pressure.
3.3.2 Request control room supervision to open the i
pump discharge isolation valve (3200A).
3.3.3 Request control room supervision to start the R11/R12 pump.
3.3.4 Verify purge effectiveness by measuring the reduction in radiation levels after approximately 15 minutes of purging.
f
's 3.3.5 Request control room supervision to close the e~
pump discharge isolation valve, secure the pump, and open the pump suction isolation valves.
i 3.3.6 Continue the purge for 10 more minutes.
3.3.7 Request control room supervision to close all pump discharge and suction isolation valves and secure the pump.
3.3.8 Secure the service air valve.
NOTE: AFTER DRILLS AND PRACTICE RUNS, RETURN ALL EQUIPMENT AND VALVE LINEUPS TO AS FOUND CONDITION.
4.0 CONTAINMENT ATMOSPHERE ANALYSIS 4.1 Volume Adjustments 4.1.1 Before proceeding with the hydrogen, radioactive nobel gas and radioactive iodine analyses, the sample centente of both syringes must be brought to atmospheric pressure. Use the shielded sacrificial glass bomb for this purpose.
4.1.2 Insert the syringe through the rubber septum of the glass
)
bomb. Unlock the syringe locking device and let the l
sj syringe and bomb equilibrate for approximately 30 seconds.
Relock the syringe and withdraw from the septum.
Store the j
syringe in the lead brick.
l
I EPIP 7.3.3 Page 5 4.1.3 Repeat Step 4.1.2 for the other syringe.
4.2 Hydrogen Assuming normal equipment setup and preparations are complete, use the cample injection port on the gas partitioner, inject a 1 cc gas sample and proceed using normal hydrogen analysis procedures.
4.3 Radioactive Noble Gases and Iodines 4.3.1 couple the silver zeolite column and the evacuated glass bomb as shown in Figure 2.
4.3.2 Inject the 1/2 cc containment atmosphere sample into the column through the septum. Remove the syringe and store in the lead brick.
4.3.3 Using a second syringe tip (without the plunger) puncture the column septum and fully insert the syringe tip.
f
's 4.3.4 crack open the upper glass bomb valve between the bomb and e~
the column. Allow air to slowly bleed through the column to the bomb.
Flow can be verified by observing the gentle reflux of the siver zeolite surface. When flow has ceased, momentarily open the upper valve wide open and then close completely.
4.3.5 Remove the column from the bomb and store the bomb behind shielding in the hood.
Iodines 4.3.6 Remove the septum from the column and pour the silver zeolite into a counting test tube and cap.
(
4.3.7 If the silver zeolite / iodine sample is less than one mR/hr contact, count the simple directly on the MCA using the test tube geometry and a multiplying factor of two.
j 4.3.8 If the iodine activity is too high to count directly, determine l
the radiation level in mR/hr at one foot.
Also, determine the percent isotopic composition using the MCA and attenu-f ating the sample if necessary.
Determine the total iodine activity using the following equation:
s R/hr @ l'
(-
)
c(ci) 6E
=
T
r EPIP 7.3.3 Page 6 The following table can be used as an aid in determining the
" Total Average Energy /y" (E )
r the above equation.
T (1/
(2)
(1) x (2)
Average y
% Composition Weighted y Isotope Energy (Fraction)_
Energy 131 I
0.380 I
0.731 I
I 0.530 134 I
0.857 I
1.238 Total Energy /y (E )
T Each individual iodine isotopic concentration (pCi/cc) is calculated as follows:
pCi/cc I 1) = C(Ci) x 2 x 10 x (Fractional % Composition)
Noble Gases 4.3.9 Withdraw a 1/2 cc gas sample from the glass bomb in Step 4.3.5.
If the contact reading on the syringe is less then one mR/hr, inject the sample into a 5 cc vial and count as normal.
If the contact reading is greater than one mR/hr, further dilutions are necessary.
Dilution procedure:
Inject the 1/2 cc sample into a.one liter poly bottle and allow to equilibriate. Withdraw 1/2 cc from the poly bottle.
If the contact reacing is less then one mR/hr, inject into a 5 cc vial and count as normal.
If the contact reading is greater than one mR/hr, dilute further.
NOTE:
FOR EACH DILUTION, USE A NEW SYRINGE OR MAKE CERTAIN THE OLD SYRINGE IS COMPLETELY PURGED. LABLE NOBLE GAS SAMPLES AND IODINE SAMPLES WITH ALL PERTINENT INFOR-MATION SUCH AS:
SAMPLE NUMBER, NAME OF SAMPLE, DATE AND TIME OF SAMPLE, SAMPLE VOLUME AND DILUTION (S).
5.0 CALCULATIONS 5.1 Pressure and Temperature Correction Ask control room supervision for the temperature and pressure in containment (psig and *F).
Determine atmospheric pressure (mm Hg) and O
l
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i l
EPIP 7.3.3 Page 7 i
3 l
temperature (*F) from the barometer in the laboratory.
Convert this to i
psia. Apply the following correction factor to all results:
Initials t
Concentration (pCi/cc) X (Peont + 14.7)
Tcont + 459 P
Tg + 459 g
l Plab (mm Hg) lab (psia)= 14 7 Psi x 760 mm Hg P
4
)
5.2 Complete and forward Containment Atmor.pheric Post-Accident Sampling j
Analysis Report (EPIP-31).
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EPIP 7.3.4 l
/"'
MINOR 7
Revision 0 12-30-81 MOVEMENT OF REQUIRED CHEMISTRY EQUIPMENT AND MATERIALS TO THE TECHNICAL SUPPORT CENTER COUNTING ROOM AND MINI-LABORATORY 1.0 GENERAL The purpose of this procedure is to provide a series of actions on the part r
of Chemistry personnel for the movement of required Chemistry equipment and materials to the Technical Support Center (TSC) Counting Room and Mini-Lab in the event this becomes necessary.
This procedure may be implemented in the event that the Controlled Side Chemistry Lab is declared radiologically uninhabitable or unfit for MCA analyses.
I 2.0 ATTACHMENTS 2.1 Appendix "A":
Ortec Geli Detector Transport Procedure.
2.2 Appendix "B":
Gas Chromatograph Transport Procedure.
O 2.3 Appendix "C":
Chemistry-Related TSC Equipment and Reference Material Inventory List.
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EPIP 7.3.4 Page 2
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APPENDIX "A" ORTEC GELI DETECTOR TRANSPORT PROCEDURE 1.0 PURPOSE To provide a readily available reference for the timely removal and transport of the Ortec Geli detector to the Technical Support Center Counting Room.
2.0 REFERENCES
2.1
" Operating and Service Manual" for Ortec 120 Series Preamplifier and Ortec Model 119 High Voltage Filter, Ortec Inc., 1970 2.2
" Operating and Service Manual" for Ortec Model 451 Spectroscopy Amplifier, Ortec Inc., 1969 2.3
" Operating and Service Manual" for Ortec Model 459 5 KV Detector Bias Supply, Ortec Inc., 1971.
3.0 PROCEDURE
(,)
3.1 Dismantling From Canberra Series 80 MCA 3.1.1 Slowly remove the bias voltage applied to the Geli detector by " stepping down" the gair '" the Canberra Model 3105 High Voltage Power Supply. Whe.. r.
voltage has been reduced to zero, turn the power supply,ff.
3.1.2 Disconnect the black high voltage cable at the high voltage connector of the Ortec Model 119 high voltage filter which is attached to the Ortec Geli detector.
l 3.1.3 Disconnect the Ortec Model 120-4 PREAMP power supply grey cable from the 7-pin connector protruding from the floor mounted cable tray.
i 3.1.4 Disconnect the black cable at the Model 120-4 PREAMP " OUTPUT-E" connector.
3.1.5 Disconnect the LN detector cable at the Ortec Detector.
i 2
3.1.6 Carefully remove the Ortec Detector from the lead shielded
" PIG" by pulling horizontally on the liquid nitrogen (LN )
2 dewar.
3.1.7 Cover the exposed detector face to protect it from physical
)
damage. A cut-off poly bottle stuffed with Kimwipes would be
/
adequate protection.
l
EPIP 7.3.4 O
Page 3 3.1.8 Carefully transpor. the Ortec Detector and LN2 dewar to the Technical Support Center Mini-Lab.
If transporting by cart, t
go slowly over bumps to minimize jarring of the sensitive detector.
3.2 Setup to Packard Series 900 MCA 3.2.1 Connect the grey power supply cable from the Model 120-4 PREAMP to the 7-pin connector on the back of the Ortec Model 451 Spectroscopy Amplifier.
3.2.2 Connect the black cable from either the " UNI" connector on the back of the Model 451 or the " UNIPOLAR INPUT" connector on the front of the Model 451, to the " OUTPUT-E" connector on the Ortec Model 120-4 PREAMP.
3.2.3 Connect the black cable from the "0-5 KV" connector on the back of the Ortec Model 459 Bias Supply to the "HIGH VOLTAGE" l
connector on the Ortec Model 119 High Voltage Filter.
l 3.2.4 The LN2 detector does not require connection in order for the system to operate. However, in order to supply adequate l
protection to the detector, either a rigorous fill schedule
(
should be initiated or the Ortec Model 729 LN detector 2
should be " pulled" from the Canberra Series 80 rack and in-stalled in the Packard rack.
3.2.5 Turn on the " POWER" switch to the Packard MCA and let it warm up.
3.2.6 Turn the "HIGH VOLTAGE" switch on the Ortec Model 459 Bias Supply to the "0N" position.
l 3.2.7 Apply detector bias voltage by slowly turning the " OUTPUT VOLTAGE" pot on the Model 459 to 2.40 (2400 V).
l i
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EPIP 7.3.4 Page 4 APPENDIX "B" GAS CHROMATOGRAPH TRANSPORT PROCEDURE 1.0 PURPOSE To provide a readily available reference for the timely removal ?nd transport of the Fisher Model 29 or 1200 Gas Chromatograph (GC) to the Technical Support Center Mini-Lab.
2.0 REFERENCES
2.1 Fisher Model 29 Instruction Manual, Fisher Scientific Co., April, 1974 2.2 Fisher Model 1200 Instruction Manual, Fisher Scientific Co., May, 1979 3.0 PROCEDURE 3.1 Turn off the " CELL POWER" and " HEATER" on the GC Model 29 or the
" BRIDGE POWER" and " MAIN POWER" on the GC Model 1200. Unplug the AC line cord.
3.2 Secure the Helium and/or Argon carrier gas at the cylinder and Y
disconnect the carrier gas line at the CG inlet.
3.2 Disconnect the tygon vent tubing from the "T" fitting that connects to the " CARRIER GAS OUTLET" and " SAMPLE OUTLET."
3.4 Disconnect the VARIAN AER0 GRAPH recorder cable from the + and - jacks on the RECORDER TRANSFER SWITCH box. Unplug the AC line cord on the Varian Aerograph recorder.
3.5 Disconnect the +, - and ground wires on the back of the GC that lead to the RECORDER TRANSFER SWITCH.
3.6 Carefully transport the GC and recorder units to the Technical Support Center Mini-Lab.
NOTE:
TAKE ALONG ANY OTHER NECESSARY ITEMS SUCH AS CALIBRATION j
CURVES, CALIBRATION GASES, SILICON RUBBER INJECTION STOPPERS, l
DRIRITE, ETC.
3.7 Setup the GC close to the VENT HOOD and connect a tygon line from the SAMPLE and CARRIER OUT to the VENT HOOD.
3.8 Plug in the AC line cord and turn on the " HEATER" on the GC Model 29 or the " MAIN POWER" on the GC Model 1200.
C/
3.9 Connect the appropriate carrier gas line to the GC and establish the i
correct pressure and flow rate.
l
. - - - - -. -. -. _ -. - - - - _ ~ -
i l-EPIP 7.3.4 Page 5 1
I 3
3.10 Turn on the " CELL POWER" on the GC Model 29 or the " BRIDGE POWER" on i
l the GC Model 1200 after allowing sufficient carrier gas purge time.
i 3.11 Connect the Varian Aerograph recorder cable directly to the jacks j
on the back of the appropriate GC.
Plug in the recorder AC line cord.
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l EPIP 7.3.4 Page 6 APPENDIX "C" TECHNICAL SUPPORT CENTER, MINI-LAB AND COUNTING ROOM CHEMISTRY-RELATED EQUIPMENT AND REFERENCE MATERIAL INVENTORY LIST 1.0 GAS CHROMATOGRAPH RELATED 1.1 Tygon vent line to vent hood 1.2 Burret Stand and clamps, 250 m1 separatory funnel, latex tubing 1.3 Carrier Gasses (He & Ar), regulators, hoses, cylinder brackets or stands.
1.4 Glass sample bombs 1.5 Syringes (gas tight and liquid) l 1.6 Leak detector
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1.7 Drierite 1.8 Silicon rubber injection stoppers 1.9 Hose pinch clamps 1.10 Varian recorder paper r
- 1.11 Calibration curve book
- 1.12 Calibration gas cylinders l
- Not stocked in Technical Support Center, Mini-Lab or Counting Room; bring from Chemistry Lab.
2.0 MCA RELATED l
- 2.1 Calibration cyrve book
- 2.2 Ortec detector
- 2.3 LN2 dewar and fill system l
2.4 Detector pig and geometry positioner /hol' der i
2.5 Spacer to position detector at proper height relative to counter top.
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2.6 Sample bottles, vials and septums 2.7 Teletype i
EPIP 7.3.4 Page 7 t
3.0 MISCELLANEOUS 3.1 Poly bottles (assorted) 3.2 Pipettes (assorted) and rack 3.3 Bunsen burners, tripods, screens, torch lighter 3.4 Condenser columns, drilled cords, glass tubing 3.5 Volumetric flasks, beakers, volumetric cylinders 3.6 Decon soap and Sparkleen
".7 Tygon, latex tubing and cutter 3.8 Vacuum hose p
3.9 Tuck tape
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t
- 3.10 Tools (assorted) l
- 3.11 Vacuum pump l
3.12 Eye droppers 4.0 POST-ACCIDENT SAMPLING SYSTEM RELATED
- 4.1 Ramp / Gas expansion chamber (gas collection bomb)
- 4.2 Valve manifold
- 4.3 Lead shielding i
- 4.4 Mirror
- 4.5 Specially prepared 2 cc syringes
- 4.6 Current CI" electrode calibration curve
- 4.7 Chloride standards and micro liter syringes l
l
- 4.8 CAMP procedure book l
- 4.9 All " Equipment List" items from EPIP 7.3.2, Section 1.2.
)
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EPIP 7.4.1
- O MINOR Revision 3 01-29-82 i
ROUTINE CHECK, MAINTENANCE, CALIBRATION & INVENTORY SCHEDULE FOR HEALTH PHYSICS EMERGENCY PLAN EQUIPMENT f
1.0 PURPOSE The purpose of this procedure is to establish the routine checks, i
maintenance, calibration and inventory schedules for health physics related material and equipment applicable to the Emergency Plan.
l 2.0 EMERGENCY PLAN EQUIPMENT STORAGE LOCATIONS 2.1 Emergency Plan equipment is normally maintained in a state of operational readiness at the following locations.
2.1.1 Health physics station l
2.1.2 Technical support center (TSC) 2.1.3 Operations support center (OSC) g 2.1.4 Site boundary control center (SBCC) 2.1.5 Control room j
2.1.6 Two Rivers Community Hospital (NFAR and triage area) 2.1.7 Point Beach Nuclear Plant first aid room (see EPIP 11.0) 2.1.8 Other items of Emergency Plan equipment such as first aid kits, burn kits, stretchers, and the emergency vehicle are maintained at specified locations throughout the plant.
t 3.0 ROUTINE CHECK, MAINTENANCE AND CALIBRATION SCHEDULES Routine checks, maintenance and calibration of Emergency Plan equipment will be consistent with the schedule outlined in Attachment "A" and the instructions contained in EPIP 7.4.2, " Emergency Plan Equipment Routine i
Check, Maintenance & Calibration Instructions."
4.0 INVENTORY SCHEDULE l
4.1 Inventory of health physics related Emergency Plan equipment will be c
consistent with the schedules provided in Attachment "A".
I I
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EPIP 7.4.1 Page 2 4.2 Inventory of Emergency Plan equipment will be accomplished utilizing l
the inventory checklists listed below and attached to this procedure.
Missing or deficient items noted by the inventory will be promptly l
replaced. The results of all inventories will be reviewed by the Health Physics Supervisor who will ensure that all discrepancies are i
corrected. The completed inventory forms will then be forwarded to i
the Superintendent - Technical Services and the Health Physicist.
i 4.2.1 Inventory Checklists a.
Site boundary control center (form EPIP-24a) b.
ISC and OSC (form EPIP-24b) c.
Two Rivers Community Hospital (form EPIP-24c) d.
Control room (form EPIP-24d) e.
Emergency vehicle (form EPIP-24e) i f.
First aid kits (form EPIP-24f)
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j g.
Burn kits (form EPIP-24g) h.
PBNP first aid room (form EPIP-24h) i.
Stretchers (form EPIP-24i) k t
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ATTACHMENT "A"
EMERGENCY PLAN EQUIPMENT ROUTINE CHECK, MAINTENANCE, CALIBRATION AND INVENTORY SCHEDULE Y
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Y a
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No.
Item Cross Ref.
0
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1.
Emergency Vehicle a.
Radio operational test X
b.
Vehicle visual inspection and X
engine start c.
Emergency equipment inventory X
I 2
d.
Vehicle test drive X
X
(~~'X,
- 1. November through March (J
j
- 2. April through October 2.
First Aid Burn Kits and Stretchers a.
Inventory X3
- 3. January, April, July, September 3.
Vamp Portable Area Monitors a.
Functional check X
b.
Calibration X
4.
Emergency Center Air Samplers 1115 V AC) a.
Functional test X
b.
Preventive maintenance X
(where applicable) c.
Flow rate calibration X
5.
SBCC Air Sampler (Battery 12 V DC) a.
Functional test X
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b.
Flow rate calibration X
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8 E
No.
Item Cross Ref.
3 of m
4 6.
SBCC Air Sampler (Gasoline Powered) a.
Functional test X
b.
Flow rate calibration X
c.
Spare gasoline changed X
7.
Batteries - Replacement a.
Traffic warning lights X
b.
Survey / counting instruments 3
X c.
Flashlights o
X f"
d.
Portable radios (KRQ 717)
X e
e.
Dosimeter chargers g
x
- 4. Alkaline type batteries to be used where possible and to be replaced yearly.
Standard carbon cells, if used, to be replaced quarterly.
8.
Potable Water (Stored) a.
Water changed x
9.
Counting Instruments a.
Functional test X
b.
Calibration x
c.
Counting efficiency determination x
10.
Frisker Type Instruments a.
Functional test X
b.
Calibration X
c.
Efficiency determination X
11.
Portable Survey Instruments l
a.
Functional test X
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b.
Calibration
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No.
Item Cross Ref.
3 i
12.
Pocket Dosimeters and TLD's 1
a.
Dosimeter drift / response check X
b.
TLD's changed X
13.
Respirators a.
Inspection X
j 14.
a.
Inspection X
l b.
Functional test X
15.
Bio-Paks (Oxygen Rebreathers) a.
Inspection X
b.
Functional test X
i i
c.
Periodic maintenance X
r 16.
Inventory of Emergency Plan 5
Equipment - Complete X
^
- 5. This inventory includes all equipment listed for each center on forms EPIP-24a, l
b, c, d and h.
I t
j 17.
Portable Radio (KRQ 717) l Functional Check X
l 18.
Traffic Warning Light Functional l
Check X
19.
Technical Support Center AMS-2/RM-14 Air Monitoring System N
).
a.
Calibration X
20.
Silver Ziolite (AgZ) Moisture i
Indicator Check X
EPIP 11.4 gs MINOR
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Revision 0 i
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11-29-82 I
PERSONNEL DECONTAMINATION 1.0 GENERAL The purpose of this procedure is to provide guidelines for the decontami-nation of individuals who become contaminated with radioactive material.
The procedures that follow are primarily guidelines, since each case of personnel contamination is unique in itself and may require variations in the methods given.
2.0 REFERENCES
2.1 Point Beach Nuclear Plant Emergency Plan j
3.0 PRECAUTIONS 3.1 The use of the steps outlined in this procedure does not infer that the Emergency Plan is being implemented. This procedure can be used for any contamination and will be used as appropriate during Emergency
)
Plan implementation.
d 3.2 Personnel who are suspected or known to be contaminated should not be allowed to. smoke, eat, or drink until the contamination has been stabilized and/or removed.
3.3 Personnel who are suspected or known to be contaminated should use care to prevent the spread of contamination to other parts of their body and to surrounding areas, i
3.4 contaminated protective clothing and/or personal clothing is to be removed in such a manner as to minimize the possible spread of contami-nation.
3.5 Personnel assisting in decontamination will utilize protective clothing and equipment to prevent contamination of themselves and/or the sur-rounding areas.
4.0 PERSONNEL FRISKING REQUIREMENTS l
During routine plant operating conditions, personnel friskers are located i
at the Health Physics Station and at the exit points from the Controlled l
Zone. Personnel should utilize the Health Physics Station friskers to j
check themselves for contamination after exiting contaminated areas or l
l after working on contaminated equipment.
All personnel will frisk
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EPIP 11.4
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Page 2 U
themselves with the friskers located at the Controlled Zone exit points prior to leaving the Controlled Zone. Personnel who find themselves contam1-nated should notify Health Physics and obtain assistance. During plant emergency conditions, the extent and nature of the emergency will determine i
the location of personnel friskers. In the event that it is necessary to move the friskers from the controlled Zone Checkpoints, other areas shall be designated as personnel frisking points.
4.1 Frisking Procedure d
4.1.1 Items of clothing that are known or suspected of being contaminated should be removed prior to attempting to deter-mine body contamination.
4.1.2 Prior to handling the frisker probes, ensure that the hands
[
are not contaminated.
If the hands are contaminated, assis-l tance should be requested.
~l NOTE: DO NOT HANDLE THE FRISKER PROBE WITH CONTAMINATED HANDS.
Contamination of the probe reduces its effectiveness for the
'"'N detection of low levels of contamination.
4.1.3 If the hands are clean or assistance has been obtained, frisk by holding the detector probe approximately one inch from the body or clothing and slowly move the detector over all parts of the body while observing the countrate meter.
NOTE: TO PREVENT CONTAMINATION OF THE PROBE, DO NOT ALLOW THE FRISKER PROBE TO TOUCH THE CLOTHING OR CONTAMINATED AREAS OF THE BODY.
4.1.4 If clothing is found to be contaminated, it should be re-moved and the body should then be frisked to determine whether nr not body contamination has occurred.
If the body is found to be contaminated, notify Health Physics personnel at once.
5.0 EVALUATION OF PERSONNEL CONTAMINATION I
Each case of personnel contamination must be individually evaluated.
Localized areas of contamination should be identified and the countrate I
recorded on form CHP-39. When evaluating for personnel contamination the following should be considered.
l a.
The nature of the work performed and the radiological environment of the work area.
i l
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b.
Is the contamination restricted to small localized ares of the body, f
excluding the head and face area?
EPIP 11.4 i
Page 3 c.
Does the contamination cover a major portion of the body or is the head and face contaminated?
d.
Is the cause of the contamination known? Was the work environment i
wet or dry?
What was the potential for the contamination, either wet or dry, to e.
be airbornei f.
Was respiratory protection equipment worn? If yes, what type was utilized?'
g.
Do nasal and mouth swabs indicate the presence of contaminated i
material? What nuclides are present?
5.1 External Contamination Most cases of external body contamination can be easily addressed by utilizing the personnel decontamination methods in this procedure.
For cases where the contamination cannot be removed, and the contami-nation levels are significant, the individual should be referred for medical tr eatment.
5.2 Internal contamination The uptake of radionuclides into the body may be evaluated by use of the whole body counter or through other bioassay methods.
Some con-siderations for evaluating the potential uptake of radionuclides by an individual are as follows:
a.
Radiological environment:
Knowledge of the radiological environment of the work area provides the best means of evaluating a potential uptake.
b.
Gross contamination of the body, especially of the upper half of the body and the head and face areas, is an indi-cation that a potential uptake has occurred.
c.
The presence of radionuclides on swabs taken from the breathing air passages (nose and mouth) will also indicate the potential for an uptake to have occurred.
d.
Radioactive noble gas may create problems in making an initial determination of an uptake since a residual level of the gas will remain in the lungs for a period of time after exposure.
I e.
Whole body counting is the most rapid and effective means of i
[N determining an uptake of radionuclides into the body.
It
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should be remembered that external contamination is also detected by the whole body counter and will, in most cases, invalidate the results of the whole body count.
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A person exposed to an environment of tritium must be evalu-ated by the use of bioassay (urinalysis) methods.
6.0 PERSONNEL DECONTAMINATION METHODS The decontamination of personnel should be accomplished at the Health Physics Station, operations support Center, or the Site Boundary Control Center depending on the extent and nature of the emergency and the level of personnel contamination encountered. Personnel decontamination should be accomplished under the supervision of health physics personnel.
6.1 Precautions 6.1.1 Decontamination should be performed in a manner that will not spread the contamination to other parts of the body or into wounds.
6.1.2 When washing, caution must be exercised to prevent breaking the skin or forcing contaminated particles into the pores of the body.
6.1.3 Hot water should not be used for washing. The hot water (greater than body temperature) may cause the body p~.es to e and allow the contamination to become embedded in the 6.1.4 When drying, blot dry; do not rub the body as this may cause the contamination to become embedded in the skin.
6.2 Localized Skin Contamination a.
Localized areas of contamination that can be washed without spreading the contamination to other areas of the body or into breaks in the skin may be washed with soap and water.
)
b.
Where the spread of the contamination to other parts of the body or into skin breaks is possible, the following initial methods should be used:
1.
If the area is dry, press tape onto the contaminated area. Remove the tape carefully to prevent extracting hair. Check the tape for the effectiveness of this method and repeat as often as effective.
2.
If the contamination remains or tape is not practical, wash the area with a cotton-tipped swab and soap and water. Remove the soap with a clean swab and water.
Dry and check the area. Repeat as often as effective, d
m
l EPIP 11.4 Page 5 3.
If (1) and (2) are not effective, sprinkle powdered soap on a gauze pad, moisten, and make into a paste. Gently wash the affected area, rinse with a clean gauze pad dipped in water. Dry and check the area.
Repeat as often as effective.
c.
If the above methods are not effec:.ive, the potassium perman-ganate/ sodium bisulfite method may have to be used. This
]
method will only be utilized by trained Health Physics su~per-visory personnel.
1.
Reagent Preparation a.
Prepare a aaturated solution of potassium perman-ganate by mixing 6.4 grams of KMnO4 in 100 mls of water.
b.
Prepare a 100 ml solution of 0.2N sulfuric acid.
c.
Mix (a) and (b) thoroughly.
d.
Prepare a solution of sodium acid sulfite by disol-ving 5 grams of NaHSO in 100 mls of water.
s NOTE:
IF THE REAGENT CAUSES ANY ADVERSE EFFECTS, THE s
TREATMENT WILL BE STOPPED IMMEDIATELY.
THE KMn04 SOLUTION WILL REMOVE A LAYER OF SKIN IF ALLOWED TO REMAIN IN CONTACT WITH THE SKIN FOR MORE THAN TWO MINUTES.
2.
Apply the potassium-permangante solution to the contami-nated area with cotton-tipped swabs.
NOTE:
DO NOT USE THIS METH3D NEAR THE FACE OR OTHER BODY OPENINGS.
Allow to dry and then make two more applications using a clean swab for each application.
3.
After the third application is dry, the solution may be neutralized and the stain removed with the sodium acid sulfite solution.
4.
Wash the area with soap and water and check for contami-nation.
NOTE: THIS METHOD MAY ONLY BE USED TWICE ON ANY GIVEN AREA.
5.
If the contamination still remains, contact the Health Physics Director or the Chemistry / Health Physics Super-visor.
4 I
EPIP 11.4
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6.3 General Body Contamination
~
f Individuals with general overall body. contamination sh9uld decontami-nate themselves, under health physics direction, using one of the shower areas noted below.
If conditions allow, all personnel decon-l tamination should be accomplished at the Health Physics Station.
Should conditions not allow the use_of the' Health' Phys'ics Station, l
other shower areas will be designate'd.
i 6.3.1 Individuals with moderate body contamination levels'should use the controlled zcne showers.
-7 l
6.3.2 Individuals with high levels of body contamination should use the " hot shower facilities" located in the Health Physics
~~
Station.
6.3.3 Depending upon the existing conditions other shower areas that may be used for decontamination ere' located at the Operations Support Center.
f
6.3.4 Procedure
Ijq a.
Caution must be observed to prevent contamination from 1
entering any body openings or skin breaks.
1 m
b.
Washing should start from the' head and, proceed downward.
i c.
Dry and check to determine if any contamination remains.
f d.
Repeat showering as long as it is effective.
i e.
Localized areas of contamination not removed by-
}
showering should be removed using the sc+ hods described j
in paragraph 6.2 (c) above.
g 1
>t 6.4 Hair Contamination Contamination of the hair can normally be removed by washing with -
~
3 soap and water.
If washing is required, the individual should use j
care to ensure that the contamination does not spread to the face.
l After washing, the hair should be dryed and checked for contami-
}
nation.
If three washings do not remove the contamination, notify the Health Physics Director or the Chemistry / Health Physics Super-i visor or their designated alternates. Removal of the contaminated j
hair by cutting should be used only when all other efforts fail.
i 6.5 Contamination of the Eyes or Mouth i
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6.'4.1 Contamination of the eyes or mouth requires that immediate l
/
notification be made to the Health Physics Director or the l
Chemistry / Health Physics Supervisor.
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EPIP 11.4 Page 7 6.4.2 The eyes or mouth may be flushed with tap water but no other action shall be taken. When flushing the mouth, the~indivi-i dual should be cautioned not to swallow the water.
6.4.3 Further action will be taken only under the direction of a physician.
5.5 contamin'atioh o'f the Nose l
s 6.5.1 Contamination of the nose reqqires immediate notification of i
the Health Physics Director *or the Chemistry / Health Physics Supervi,sor.
s i
6.5.2 Have the individual blow his nos,e lightly into a facial tissue or soft paper towel.
Check >for further contami-nation.
jj f
6.5.3 If contamination remains,l a damp cotton swab may be used.
l a.
Insert the swab carefully intc the nostril as far as
~
possible (the individual himself should do this).
Exer-cise caution so the swab does not touch the side of the ncstrils during insertion.
b.
Press-the swab lightly against the sides of the nostril 7
and~ withdraw in a circular motion so that all sides of the nostril are wiped. Check for further contamination.
l Continue as'long as effective and nose does not become c.
tender.
d.
Further action, if required, will be taken only under the direction of a physician.
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EPIP 12.4 MINOR
}
Revision 0 01-29-82 O
PERSONNEL EXPOSURE GUIDELINES 1.0 GENERAL The purpose of this procedure is to establish personnel exposure guidelines and responsibilities for exposure control in the event activation of the Point Beach Nuclear Plant Emergency Plan makes it necessary to deviate from normal operating procedurer.
2.0 REFERENCES
2.1 Point Beach Nuclear Plant Emergency Plan 2.2 10 CFR 20, Standards for Protection Against Radiation 2.3 Health Physics Administrativa Control Policies & Procedures Manual 3.0 PRECAUTIONS
[
}
3.1 All personnel performing emergency evaluation or recovery activities
( _,/
where the potential exists for exposure to ionizing radiation will be provided with personnel menitoring devices consisting of thermo-luminescent dosimeters (T';D) and the self-reading dosimeters (SRD).
3.2 All personnel will ensure that their SRD is set to zero when picked up at the issuing station.
3.3 All personnel will verify that they have the correct TLD (their own)
+
when it is picked up at the issue station.
3.4 Each individual worker will ensure that exposures authorized under this procedure are not exceeded and that all SRD rezeros.?re docu-mented for entry into the individual exposure accounting records.
r 4.0 EMERGENCY PERSONNEL EXPOSURE GUIDELINES 4.1 Point Beach Nuclear Plant Administrative Exposure Limits l
During a plant emergency condition, the administrative exposure limits to ionizing radiation will apply unless suspended by the Site Manager or'his designated alternate upon recommendation of the Health Physics t
Director or Chemistry / Health Physics Supervisor or their designated alternates.
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EPIP 12.4 Page 2
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4.1.1 In the event of a major radiation emergency, circumstances may require exposures in excess of the Point Beach Nuclear Plant adninistrative limits.
Under these circumstances the following guidelines apply.
a.
When circumstances allow for detailed planned actions to be taken, the expressed approval of the Health Physics Director or Chemistry / Health Physics Supervisor and the Site Manager or their designated alternate will be ob-tained prior to allowing einergency workers to exceed the Point Beach Nuclear Plant administrative expcsure limits.
b.
When circumstances do not allow for detailed planned actions due to the urgency of the situation, an attempt should be made to obtain approval from the Duty Shift Supervisor and a senior manager prior to allowing emergency workers to exceed the Point Beach Nuclear Plant admini-strative limits.
NOTE:
SEE TABLE 1 FOR A
SUMMARY
OF THE POINT BEACH NUCLEAR PLANT ADMINISTRATIVE EXPOSURE LIMITS.
4.2 10 CFR 20 Exposure Limits
)
\\y_ j Upon suspension of the Point Beach Nuclear Plant administrative exposure limits as outlined in Section 4.1, the exposure limitations of 10 CFR 20.101 and 103 will apply.
4.2.1 In the event of a major radiation emergency, circumstances may require exposures in excess of the established limits
)
of 10 CFR 20.101 and 103. Under these circumstances, the following guidelines apply.
a.
When circumstances allow for detailed planned actions to be taken, the expressed approval of the Health Physics Director or Chemistry / Health Physics Supervisor and the Site Manager or their designated alternates will be ob-tained prior to allowing emergency workers to exceed the 10 CFR 20.101 and 103 exposure limits.
b.
When circumstances do not allow for detailed planned actions due to the urgency of the situation, an attempt should be made to obtain approval from the Duty Shift Supervisor and a senior manager prior to allowing emergsncy workers to exceed the exposure limits of 10 CFP 20.101 and 103.
c.
Where necessary, for the protection of personnel or the l
f'~'s substantial protection of plant property, the management
(
I personnel noted in paragraphs (a) and-(b) above may
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authorize individual exposures in excess of 3 Rem whole body but less than 25 Rem whole body.
EPIP 12.4 Page 3
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4.2.2 Lifesaving Exposur7 Limits 4
Lifesaving exposures in excess of 25 Rem but less than i
100 Rem whole body may be authorized on a volunteer basis only. The decision to authorize exposures in this type of situation will be left to the judgement of the Health Physics Director and the Chemistry / Health Physics Supervisor, L
if available.
If the above are not available, approval TQ9) should be obtained from the Duty Shift Supervisor and a senior manager.
a.
Volunteers will be made aware that whole body exposures in the order of 100-200 Rem may result in radiation sickness and that whole body exposures in excess of 200 Rem involve a risk of fatality.
8 b.
Volunteers should avoid risk where the victim's exposure is known to be at a fatal level or where it is known that l
the victim is already fatally injured.
NOTE:
SEE TABLE 1 FOR A
SUMMARY
OF 10 CFR 20 EXPOSURE LIMITS.
/'~'
5.0 LOCATION OF PERSONNEL MONITORING DEVICES Personnel monitoring devices (thermoluminescent dosimeters (TLD) and self-reading dosimeters (SRD)) are available for use by emergency workers at the following locations.
LOCATION TYPE AVAILABLE i
1.
Site Boundary Control CO. tar TLD and SRD o
3.
Operations Support Center SRD 4.
Technical Support Center SRD 5.
Control Room SRD 6.
Health Physics Station SRD 7.
Emergency Vehicle TLD 8.
Two Rivers Hospital (Nuclear First Aid Room)
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EPIP 12.4 Page 4 O
.0 r
6 LOCATION OF PERSONNEL EXPOSURE SUMMARIES In addition to the individual copies of the Weekly Dosimeter Summary provided to each Group Head complete copies are maintained at the following locations.
6.1 Health Physics Station 6.2 Operations Support Center 6.3 Main Office Files 6.4 Health Physics Office (Extension Building) 6.5 Southgate (current Daily Dosimeter Summary Sheets) 7.0 EXPOSURES IN EXCESS OF ADMINSTRATIVE GUIDELINES 7.1 Perscnnel who have received whole body exposures in excess of 25 Rem shall be removed from emergency duty and referred to a physician for medical evaluation.
7.2 Personnel who hasc received whole body exposures in excess of 3 Rem shall be removed from normal work activities in the control area.
}
Although it is extremely unlikely that there will be any detectable
' '/
health effects, the Site Manager may refer the exposed person to a physician.
7.3 Any medical evaluation should be forwarded to the company Medical Department.
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TABLE 1 EMERGENCY PLAN EXPOSURE LIMITS ADMINISTRATIVE EXPOSURE LIMITS (1)
CATEGORY WHOLE BODY SKIN EXTREMITIES AIRBORNE DAILY LIMIT 300 mrem (100 mrem) 600 mrem 1500 mrem WEEKLY LIMIT 600 mrem 1200 mrem 3000 mrem 40 MPC-HOURS 10 CFR 20.101 AND 103 EXPOSURE LIMITS "A"
QUARTERLY LIMIT 1250 mrem 7500 mrem 18750 mrem 40 MPC-HOURS "B" QUARTERiY LIMIT 3000 mrem 7500 mrem 18750 mrem 40 MPC-HOURS EMERGENCY EXPOSURE LIMITS (PBNP EMERGENCY PLAN)
PROTECTION OF PERSONNEL OR PLANT PROPERTY (9) 3000 but < 25000 mrem 1200 MPC-HOURS (10)
LIFESAVING 25000 but < 100,000 mrem 1200 MPC-HOURS 10000 MPC-HOURS NOTES:
(1)
Limits are derived from the Health Physics Administrative Control Policies and Procedures Manual.
(2)
Exposures in excess of the daily or weekly administrative limits require the approval of the Health Physicist or his designated alternate.
(3)
Exposure in excess of the 100 mrem daily limit require the approval of the group supervisor.
(4)
Whole body exposure is defined as exposure to the whole body, head and trunk, blood forming organs, lens of
%yes'and gonads.
(5)
Skin exposure is defined as exposure to the skin of the whole body.
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s (6)
Extremeties include the hands, forearms, feet and ankles.
(?)
May be authorized after receiving signed statement that individual has received no exposure during the current quarter.
Otherwise, one-fourth (1/4) of these values apply for non-plant employees.
(8)
May be authorized when the doce 'to the whole body, when added to the accumulated occupational dose to the whole body, will 'not exceed 5 (N-18) Rems and the individual's accumulated occupational dose to the whole body has been determined on NRC Form-4 or similar document containing the same information.
(9)
Requires the approval of the Health Physics Director or Chemistry / Health Physics Supervisor and the Site Manager or his designated alternate when circumstances allow time for planned actions. Otherwise, in urgent circumstances, an attempt should be made to obtain approval from a group supervisor or Duty Shift Supervisor who is trained in Health Physics Procedures and a senior manager prior to authorizing exposures in excess of 10 CFR 20.101 and 103.
(10)
Integrated exposures of 10,000 MPC-hours for nuclides with less than 8 day effective half-lives, are approxi-mately equivalent to 25,000 mrem of whole body exposure.
Integrated exposures of 1,200 MPC-hours for nuclides with greater than 8 day effective half-lives are approximately equivalent to 3000 mrem or whole body exposures.
(11) a.
Lifesaving exposures in excess of 25 Rem but less than 100 Rem shall be on a volunteer basis and left to the judgement of the Health Physics Director and the Chemistry / Health Physics Supervisr.r, if available.
b.
Volunteers should be made aware that whole body doses in the order of 100-200 Rem may result in radiation sickness and that whole' body doses in excess of 200 Rem involve a risk of fatality.
c.
Volunteers should avoid risk where the victim's exposure is known to be at a fatal level or where it is known that the victim's already fatally injured.
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01-29-82
(
TABLE OF EPIP FORMS I
EPIP EPIP j
Form Title Procedure y
01 Emergency Plan Airborne Radiation Survey Record Site Boundary Control Center (03-81) 7.3.1 l
02 Emergency Plan Survey Record Site Boundary Control Center i
(09-81) 7.3.1 03 Dose Factor Calculations for Specific Noble Gas Analysis Results (03-81) 7.3.1 l
04 Status Report on Plant Systems and Controls for Affected Unit (03-81) 1.2 05 Werksheet for Status Report on Radiation Monitoring System l
for Unit (03-81) 1.2 06 Worksheet for Status Report on Radiation Monitoring System for Plant (03-81) 1.2 07 For X/Q Determination (09-81) 1.4 08 Estimated Whole Body and Thyroid Projected Doses (09-81) 1.4 j
09 Estimated Whole Body Dose Calculation Worksheet for Specific Noble Gas Releases (09-81) 1.4 j
p 10 Estimated Ground Deposition Calculation Worksheet for i
(
Particulate Radionuclide Releases (09-81) 1.4 l
11 Summary of Radiological Dose Evaluation Calculations (09-81) 1.4 l
j 12 Unusual Event Incident Report Form (03-81) 2.1 j
13 Alert Incident Report Form (03-81) 3.3 14 Site Emrgency Incident Report Form (03-81) 4.3 15 General Emergency Incident Report Form (03-81) 5.3 t
16 Event Data Checklist (03-81) 5.3 i
17 List of Missing Personnel (03-81) 8.1
[
18 Assembly Area Roster (03-81) 8.1 l
l 19 Drill / Exercise Scenario (03-81) 15.3 l
20 Drill / Observation Sheet (03-81) 15.3 i
~
21 Drill / Exercise Evaluation Report (03-81) 15.3 r
22 Plant and Company Emergency Call List (10-81)
Call List Tab
(
23 Offsite Agency Emergency Call List (01-82)
Call List Tab
[
24a Site Boundary Control Center Emergency Plan Inventory i
Checklist (01-82) 7.4.1
(
24b TSC, South Gate'and OSC Emergency Plan Inventory
}
Checklist (01-82) 7.4.1 24c Emergency Plan Health Physics Supplies at Two Rivers community Hospital Inventory Checklist (09-81) 7.4.1 24d Control Room Emergency Plan Equipment Inventory Checklist i
(09-81) 7.4.1 24e Emergency Vehicle Inventory Checklist (05-81) 7.4.1 l
24f Emergency Plan First Aid Kit Inventory Checklist (03-81) 7.4.1 24g Emergency Plan Bu'a Kit Inventory (03-81) 7.4.1 l
24h Emergency Plan Fitst Aid Room Inventory (05-81)
.._7. 4.1 l
24i Emergency Plan Stretcher Inventory (09-81) 7.4.1 i
i I
i.
Page 2
~
EPIP EPIP Forms Title Procedure 25a Emergency Vehicle Checklist (10-81) 7.4.2 i
25b Monthly Health Physics Instrument and Air Sampler Functional Test Checklist (01-82) 7.4.2 25c Quarterly Emergency Plan Checklist (01-82) 7.4.2 25d Semi-Annual and Annual Emergency Plan Checklist (07-81) 7.4.2 26 Quarterly Communications Test (03-81) 14.1 27 Honthly Communications Test (03-81) 14.1 28 Emergency Plan Instrument Calibration Schedule (05-81) 7.4.2 29 Emergency Plan Counting Equipment and Frisker Calibration 4
Schedule (07-81) 7.4.2 30 Reactor Coolant Post-Accident Sampling Analysis Report (09-81) 7.3.2 31 Containment Atmosphere Post-Accident Sampling Analysis Report (12-81) 7.3.3 Od i
6 4
' O 4
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i i
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l POINT BEACH NUCLEAR PLANT CONTAINMENT ATMOSPHERE POST-ACCIDENT SAMPLING ANALYSIS REPORT l
1.0 HYDROGEN ANALYSIS 1.1 Scale used on gas partitioner I
1.2 Millivolt reading on chart recorder f
i 1.3
% hydrogen from calibration curve i
2.0 RADIOACTIVE NOBLE GAS ANALYSIS l
l 2.1 Decay time in minutes I
2.2 Sample count time in seconds i
2.3 Detector 2.4 Geometry l
2.5 Volume of glass bomb : (x)
}
[
i l
2.6 Common multiplier *
(x)(1) 1075(1) j
. *CM = 0.5
- 0.5 x ( ressure-Temperature Correction) l Pressure-Temperature Correction = (P + 14.7) (T + 459)
P (T + 459) j Where P = Pressure in Containment (psig)
C T
empera re n na ent ( W C
l i
P = Pressure in Laboratory (psi) where,
("" "U}
P = 14.7 X L
760 (mm Hg)
T = Temperature in Laboratory (*F) g 1
i (1) See Section 4.3.9 of EPIP 7.3.3.
Additional dilutions or less dilutions mdy be necessary.
b[s\\
I EPIP-31 l
(12-81) l l
i f.
Page 2 g
l r~
2.7 Results of MCA Isotope Concentration (pCi/cc)
Xe-133 Kr-85m l
Kr-88 Xe-133m Xe-135 Xe-138 Kr-87 Xe-135m Ar-41 Kr-85 i
Xe-131m 3.0 RADIOACTIVE IODINE ANALYSIS 3.1 Decay time in minutes 3.2 Sample count time in seconds 1
3.3 Detector
(
[
3.4 Geometry i
3.5 Common multiplier
- l f
l
- CM = 0 5 =2 f
3.6 Results of MCA I
Isotope Concentration (pCi/cc) l i
I-131 I-132 I-133 I-134 I-135 4.0 ROUTINE AND APPROVAL Date Initials 4.1 Calculations completed by
{
l 4.2 Analysis completed by i
4.3 Chemistry & Health Physics Supe'rvisor
(
4.4 Chemistry / Health Physics Supervisor (TSC) 4.5 Director (TSC)
EPIP-31 (12-81)
$.-. M
['
i 0FFSITE AGENCY EMERGENCY CALL LIST
.s)
,~
FEDERAL AGENCIES:
1.
United States Nuclear Regulatory Commission Telephone Person Time Name Frequency Number Notified Notified Initials NRC Operations All hours Red Phone Center or 1-301/492-8111 NRC Office of All hours 1-312/932-2500 Inspection and (Ask for Enforcement, Duty Officer)
Region III NRC Resident Inspectors:
Plant Ext.
Home a.
W. G. Guldemond 294 682-1064 b.
R. L. Hague 294 388-2856 2.
United States Department of Energy Telephone Person Time gne Frequency Number Notified Notified Initials Chicago Operations Weekdays 1-312/972-4800 Center, Region V (8AM-SPM)
(Radiological Assistance Team)
All other 1-312/972-5731 hours 3.
United States Coast Guard Telephone Person Time Name Frequency Number Notified Notified Initials USCG, Sturgeon All hours 1-743-3366 Bay USCG, Two All hours 793-1304 Rivers s
i,
,,/
EPIP-23 Page 1 of 4 (01-82)
e
[s~? ATE AGENCIES:
t't,/
1.
State of Wisconsin
)
Telephone Person Time Name Frequency Number Notified Notified Initials Wisconsin Dept. of Weekdays 1-608/266-7464 H2alth and Social (9AM-5PM)
Services, Section of Radiation Pro-tection Lawrence J. McDonnell, Home phone Chief Section of Radiation 1-608/873-5483 Protection Wisconsin Division All hours 1-608/266-3232 of Emergency or NAWAS Government Wisconsin State All hours 1-921-0448 Patrol 1-921-0442 l
or NAWAS 1.
Manitowoc County Telephone Person Time Name Frequency Number Notified Notified Initials Manitowoc County All hours 684-4441 Sheriff, County or NAWAS Traffic 2.
Kewaunee County Telephone Person Time Name Frequency Number Notified Notified Initials l
Kawaunee County All Hours 1-388-3100 l
Dispatcher or NAWAS l
PRIVATE AGENCIES:
Telephone Person Time Name Frequency Number Notified Notified Initials l
Kswaunee Nuclear All hours 793-2229 l
Power Plant
,a
(
)
'R,/
EPIP-23 Page 2 of 4 (01-82) l
i e
IVATE AGENCIES: (Cont'd)
Telephone Person Time Name Frequency Number Notified Notified Initials Institute of All hours 1-404/953-0904 Nuclear Power Operations W3stinghouse Electric Corp.
Field Serv. Mgr. Office 1-412/256-3820 (R. Grimm)
Home 1-412/468-6219 Hot Line 1-412/468-6763 Stone & Webster All hours 1-617/973-0008 Engineering Corp.
Bechtel Power All hours 1-415/768-3840 Corporation FIRE AND MEDICAL AGENCIES 1.
Fire Emergency j
Telephone Person Time l
me Frequency Number Notified Notified Initials l
wo Creeks Fire All hours 684-0133 Department (Emergency line) 2.
Medical Assistance Telephone Person Time Name Frequency Number Notified Notified Initials Doctors Clinic, Ltd.
793-2231 S. Lawrence Kaner, M.D.
Stephen L. Weld, M.D.
University Hos-I pital, Madison l
Emergency Room All hours 1-608/262-2398 Frank C. Larson, M.D.
1-608/262-2716 Robert F. Schilling, M.D.
1-608/262-3188 Robert R. Radtke, Ph.D.
1-608/262-8769 (Health Physicist)
/
i
)
G/
EPIP-23 Page 3 of 4 i
(01-82)
4 4
4 RE AND MEDICAL AGENCIES: (Cont'd) l Telephone Person Time I
Name Frequency Number Notified Notified Initials I
i Two Rivers All hours 793-1151 Emergency or 1152 2
Vehicle i
i i
j Community Hos-All' hours 793-1178 j
pital, Two Rivers
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i I
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I EPIP-23 Page 4 of 4 (01-82)
POINT BEACH NUCLEAR PLANT SITE BOUNDARY CONTROL CENTER EMERGENCY PLAN INVENTORY CHECKLIST a
Item No.
Item Required On Hand Sampling Equipment and Supplies i
1.
Air sampler, gasoline operated 1
3.
Electric high volume air sampler 1
l 4.
Poly gas sample bottles 12 5.
Charcoal cartridges for air sampler, high volume 48 6.
Charcoal cartridges for air sampler, low volume 50 7.
Silver zeolite cartridges for air sampler, low volume 5
8.
Filters for air samplers (pkg. of 100) 2 9.
Gasoline and oil for air sampler (gallons) 2 l
10.
Sample tags 50 l
11.
Plastic bags 50 12.
100' extension cord 2
13.
Planchets 20 Respiratory Protection Equipment 14.
Full-face respirators 2
j'~'}
15.
Half-face respirators 2
16.
Full-face filter cartridge 12
(
j 17.
Half-face filter cartridge 10 Fire Protection Equipment 18.
Fire extinguisher, dry chemical 1
7 Radiation Survey and Monitoring Instrument 19.
Victoreen Radgun (.01 mR/hr - 10 kR/hr) 1 20.
Radector III (.1 mR/hr - 1,000 R/hr) 1 21.
Victoreen Model 490 Thyac III 1
22.
PIC-6A survey instrument (1 mR/hr - 1,000 R/hr) 2 23.
RM3C personnel survey frisker 1
24.
Johnson Associates, GSM-5, 0-50k cpm, 0-200 mR/hr 1
25.
MSC-1 sampler holder for GSM-5 1
26.
Check sources 2 - Cs-137 and 1 - Sr-90 3
27.
Filters for smears (pkg. of 100) 2 28.
Nuclear Chicago counter scaler 1
29.
Coin envelopes (box) 1/2 30.
HP-210 probe 2
31.
SH4 probe holder 1
i 32.
Earphones for Thyacc III survey instrument 3
33.
Side window probe 2
34.
Cord, BNC-BNC connector 2
l 35.
Cord, amphenol - BNC connector 2
~
Q,/
I EPIP-24a (01-82)
Page 2 Required On Hand
/
Personnel Monitoring Equipment 36.
Personnel Thermoluminescent Dosimeters (TLD) 100 37.
Radiological dosimeters, 0-5 R 12 38.
Radiological dosimeter charger 2
First Aid and Decontamination Supplies 39.
First aid kit 1
40.
Burn kit 1
41.
Emergency drinking water tablets (bottles; 50 tables per bottle) 5 42.
Water (gallons) 20 43.
Decon soap, powder (5 lb.)
1 44.
Decon soap, liquid (qt.)
1 45.
Hand brush 4
46.
Cotton applicators (box) 1 47.
Potassium permanganate (4 oz.)
1 48.
Sodium bisulfate (1 lb.)
1 4
49.
Kim towels (box) 1 50.
Masselin (pkg.)
1 51.
"409" cleaner (btl.)
2 52.
" Spic'n Span" (box) 2
.)
53.
Masselin mop 1
,/
54.
Regular sponge map 2
55.
Rag mop 1
56.
Wringer 1
57.
Large mop bucket 1
58.
Kim wipes (box) 1 59.
Bucket, plastic 2
60.
Cotton swabs (packets) 5 61.
Gauze sponges, 2" x 2" (100 per pkg.)
1 62.
Nail brushes 4
Radiation Hazard Signs and Supplies 63.
Radiation warning tape (roll) 1 64.
Radiation placards 10 65.
Radioactive material and radiation hazard signs 10 66.
Radiation contamination hazard tags 10 67.
Contamination, high radiation, racicactive material, and radiation area inserts (ea.)
10 68.
Yellow / magenta ribbon (rolls) 8 69.
Yellow / magenta rope (roll) 1 r
I I
EPIP-24a (01-82) t
r-Page 3 Required On Hand b
Communication Equipment and Supplies 70.
Portable 2-way radio KRQ-717 1
71.
Telephone, plan PBX-extension with outside line capability 1
72.
WE telephone book 1
73.
Two Rivers /Manitowoc telephone book 1
Traffic Signs and Equipment 74.
Traffic cones for barricades 20 75.
Traffic lights for barricades 8
76.
Chains and padlocks for barricades 4
77.
Traffic flashlight 4
78.
" Closed Area" placards 6
79.
Traffic warning light batteries (spare)
Clothing and Toiletry Stpplies 80.
Coveralls 25 8:..
Rainwear 6
82.
Rubber boots 10 83.
Shoe covers, plastic 25
)
84.
Overshoes, winter 6
g/
85.
Gloves, rubber disposable 6
86.
Gloves, cotton disposable 6
87.
Mittens, winter 6
88.
Towels 12 89.
Washcloths 12 Stationery and Miscellaneous Supplies 90.
Desk table and chair 1
91.
Writing paper (pad) 1 92.
Pens and pencils Assortment 93.
Tape, masking (rolls) 2 94.
Tuck tape (rolls) 10 95.
Logbook 1
96.
Absorbent paper (roll) 1 l
97.
Paper cups (bag) 1 98.
Plastic bags 50 99.
Scissors 1
100.
Pocketknife 1
101.
Screwdrivers (set) 1 102.
Plastic funnel 4
(
l 103.
Flashlight 1
i 104.
Batteries (for flashlight and survey instruments) 50 l
105.
Flashlight bulbs 6
l EPIP-24a l
(01-82)
Page 4 Requ!!ed On Hand I
Stationery and Miscellaneous Supplies, continued...
i 106.
Bulbs, incandescent 8
l 107.
Electric clock 1
i 108.
Electric heater 5
j 109.
Wet / dry vacuum cleaner 1
110.
Metal drum (55-gallon) 1 111.
Dzl-lene (quart), gasoline stabilizer 1
112.
Lead bricks 12 113.
Safety solvent (low) 1 114.
Metal funnels 2
l 115.
Pencil sharpener 1
l 116.
Chalk 1
117.
Bulletin Board 1
118.
Chalkboard 1
119.
Table (reg.)
1
{
120.
Picnic tables 2
121.
Calculator-1 l
j Emergency Plan Documents j
122.
PBNP Emergency Plan 1
123.
Health Physics Administrative Control Policies
/ ]
124 and Procedures Manual 1
Dose Isopleth/ Map Package 1
l 125.
Personnel Roster 10 l
126.
~Potassiu'n Iodide Approval, Use List 1
127.
DOE, Region V, Radiological Assistance Handbook 1
128.
State of Wis. Peacetime Radiological Response Plan 1
4 EPIP Forms i
129.
EPIP-01, Emergency Plan Airborne Radiation Survey 5
[
130.
EPIP-02, Emergency Plan Survey Record 5
131.
EPIP-03, Dose Factor Calculation Sheet 5
E 132.
- EPIP-04, Status Report on Plant Systems and Controls 5
j 133.
EPIP-05, Worksheet for Status Report on RMS for Unit 5
t 135.
EPIP-07, X/Q Determination 5
134.
EPIP-06, Worksheet for Status Report on RMS for Plant 5
l 136.
EPIP-08, Estimated Whole Body and Thyroid Projected 5
137.
EPIP-09, Estimated knole Body Calculation Worksheet 5
138.
EPIP-10,-Estimated Ground Deposition Calculation 5
I f
139.
EPIP-17, List of Missing Personnel 5
140.
EPIP-18, Assembly Area Roster 5
i
(
141.
Xe-133 Equivalent Release Rate, Worksheet No. 1 5
l i
i I
t t
EPIP-24a l
(01-82).
~l t
t
i Page 5 j
Required On Hand v
EPIP Procedures 142.
EPIP 1.4, Radiological Dose Evaluation 5
143.
EPIP 1.5, Protective Action Evaluation 5
144.
EPIP 7.1.1, Chemistry & Health Physics Personnel Notification and Initial Response when Chemistry &
Health Physics Personnel are On-Site 5
145.
EPIP 7.2.1, Activation of Health Physics Facilities at Site Boundary Control Center 5
146.
EPIP 7.2.2, Activation of Health Physics Facilities at Operations Support Center 5
147.
EPIP 7.2.3, Activation of Health Physics Facilities at Technical Support Center 5
CHP Forms 148.
CHP-02, Iodine Airborne Survey (pad of 50) 1 149.
CHP-21, Miscellaneous Survey (pad of 50) 1 150.
CHP-31, Radiation Work Permit (pad of 50) 1 151.
CHP-34, Dosimeter Rezero (pad of 50) 1 152.
CHP-37, Irregular or Offscale Dosimeter Report (pad of 50) 1 153.
CHP-22, Air Particulate Sample (pad of 50) 1 154.
CHP-25, Counting Log Sheet (pad of 50) 1 Q/
155.
CHP-33b, Visitors' Monitored per 10 CFR 20 (pad of 50) 1 156.
CHP-33c, Visitor Personnel Monitoring Record (pad of 50) 1 l
157.
CHP-35, Dosimeter Summary Sheet (pad of 50) 1 158.
CHP-38, Lost or Damaged TLD Report (pad of 50) 1 159.
CHP-39, Personnel Contamination Report (pad of 50) 1 160.
CHP-40, Visitor TLD Badge Issue Report (pad of 50) 1 161.
CHP-44, Timekeeping Log - High Radiation Work Location (pad of 50) 1 162.
CHP-56, Personal Bioassay Evaluation (pad of 50) 1 163.
CHP-106, Occupational External Radiation Exposure History (pad of 50) 1 164.
Emergency Plan Sampling Kits - Each kit contains the following:
2 1.
Battery powered air sampler 1
2.
Scott cartridge holder 1
3.
Silver Zeolite cartridge holder 1
4.
Stop watch with batteries 1
5.
Air Particulate filters (env.)
1 6.
Silver Zeolite cartridge 5
7.
Scott charcoal cartridge 5
8.
PIC-6A survey meter 1
(%
9.
Water filled gas sample bottle (1 liter) 2 EPIP-24a (01-82)
]
1 Page 6 Required On Hand 10.
Liquid sample cubitainers (1 liter) 2 11.
Scissors 1 pair 12.
Plastic suit 2 sets 13.
Gloves (surgeons) 6 pair 14.
Dosimeters (0 - 5,000 mR) 2 15.
Dosimeter charger 1
16.
Plastic Bags j
12 x 18 inch size 6
5x8 inch size 6
3x5 inch size 12 17.
Flasnlight with spare bulb and batteries 1
18.
Smears (100 each/ box) 2 19.
Tuck Tape (roll) 1 20.
Sharpie, Flair pen, grease pencil and pencil 4
21.
bample ID tags (psd) 1 22.
Sampling Procedures EPIP 7.3.1 Airborne Sampling and Direct Dose Rate 5 ea Survey Guidelines EPIP 7.3.1 Atmospheric Radioactive Iodine Sample 5 ea Attachment collection and Counting 23.
Sampling Forms EPIP-01 Airborne Radiation Survey Record 5 ea EPIP-02 Emergency Plan Survey Record 5 ea Sample Identification Survey Map 5 ea 2 and 5 Mile Sample Identification Survey Map 5 ea 24.
CHP-34 Rezero Sheet 5 ea By Date t
Reviewed By Date (Health Physics Supervisor) i
~
i i
t l
)
i EPIP-24a (01-82) j io
)
POINT BEACH NUCLEAR PLANT TSC, SOUTH GATE & OSC EMERGENCY PLAN INVENTORY CHECKLIST Date TSC OSC Suggested Inv.
Suggested Inv.
Inventory Check Inventory Check Air Sampling Equipment 1.
Low volume air sampler 1
1 2.
High volume air sampler 1
1 3.
AMS-2 cart mounted air sampler 1
N/A 4.
Particulate filters, low volume, box 1
1 5.
Charcoal filters, low volume, box 4
4 6.
Particulate filters, high volume, box 1
1 7.
Charcoal filters, high volume, box 1
1 d.
Silver zeolite filters 15 10 9.
Plastic bottles, 1 liter 12 12 10.
50' extension cord 2
2 l
Dosimetry Equipment (y/12.
)11.
Dosimeters (0-5,000 mR) 20 20 Dosimeters (0-200 R) 6 N/A 13.
Dosimeter charger 1
1 14.
Batteries, Size AA, pkg.
1 1
Survey and Monitoring Equipment 15.
Victoreen Vamp 1
1 16.
Rad Owl II 1
1 17.
Thyac III - side window probe 1
1 18.
Batteries, Size D 12 12 19.
Batteries, Size 9 volt 3
3 20.
Smear filters, box 10 10 21.
Smear envelopes, box 1
1 21a.
h" lead detector shield (teletector) 1 Signs 22.
Three-pocket placards 12 12 23.
" Radiation Area" inserts 12 12 l
24.
"High Radiation Area" inserts 12 12 25.
"RWP Required" inserts 12 12 26.
" Airborne Area" inserts 12 12 Contaminated Area" inserts 12 12 27.
28.
" Radioactive Materials" inserts 12 12 m
N EPIP-24b
~
l (01-82)
)
r -
)
s Page 2 C
Suggested Inv.
No.
Item Inventory Check Inventory Check Respiratory Protection Equipment 29.
Clear-Vue respirator 6
6 30.
Ultra-Vue respirator 6
6 31.
Filter cartridges, box 1
1 32.
Smoke test kit 1
1 33.
Bio-Pak 60 4
3 CHP Forms 34.
CHP-02, Iodine Airborne Survey, pad 1
1 35.
CHP-21, Miscellaneous Surveys, pad 1
1 36.
CHP-31, Radiation Work Permit, pad 1
1 37.
CHP-34, Doimeter Rezero, pad 1
1 38.
CHP-37, Irregular or Offscale Dosimeter Report, pad 1
1 39.
CHP-22, Air Particulate Sample, pad 1
1 EPIP Forms g"N 40.
EPIP-01, Emergency Plan Airborne
)
Radiation Survey 5
5 5\\~> ' 41.
EPIP-02, Emergency Plan Survey Record 5
5 42.
EPIP-03, Dose Factor Calculation Sheet 5
5 43.
EPIP-04, Status Report on Plant Systems and Controls 5
N/A 44.
EPIP-05, Work Sheet for Status Report on RMS for Unit 5
N/A 45.
EPIP-06, Work Sheet for Status Report on RMS for Plant 5
N/A 46.
EPIP-07, X/Q Determination 5
N/A 47.
EPIP-08, Estimated Whole Body and l
Thyroid Projected 5
N/A 48.
EPIP-09, Estimated Whole Body Calculation Work Sheet 5
N/A 49.
EPIP-10, Estimated Ground Deposition Calculation 5
N/A l
50.
EPIP-17, List of Missing Personnel 5
5 51.
EPIP-18, Assembly Area Roster 5
5 52.
Xe-133 Equivalent Release Rate, Worksheet No. 1 5
N/A EPIP Procedures 53.
EPIP 1.4, Radiological Dose Evaluation 5
N/A I
54.
EPIP 1.5, Protective Action Evaluation 5
N/A
[
h55.
EPIP 7.1.1, Chemistry & Health Physics
(,,/
Personnel Notification and Initial Response when Chemistry & Health Physics Personnel are On-Site 5
N/A j
l EPIP-24b (01-82) i
r Page 3 (hItem TSC OSC Suggested Inv-Suggested Inv.
No.
Itg Inventory Check Inventory Check EPIP Procedures, continued...
56.
EPIP 7.2.1, Activation of Health Physics Facilities at Site Boundary Control Center 5
5 57.
EPIP 7.2.2, Activation of Health Physics Facilities at Operations Support Center N/A 5
58.
EPIP 7.2.3, Activation of Health Physics Facilities at Technical Support Center
'S 5
Miscellaneous 59.
Barricade tape, yellow / magenta, rolls 5
5 60.
Tuck tape, rolls 2
2 61.
Hot spot tags 50 50 62.
Radiation material hazard tags 50 50 63.
Radioactive material contamination tags 50 50 64.
Yellow / magenta tape, rolls 6
6 65.
Yellow / black warning tape, roll 5
5 66.
Plastic bags, 3 x 5 50 50 67.
Plastic bags, 5 x 7 50 50 68.
Potassiun iodine use (personnel list) 1 1
i SOUTH GATE Suggested Inv.
Aiic Sampling Inventory Check 69.
Low volume air sampler 1
70.
Particulate filters, box 1
71.
Charcoal filters, box 1
72.
Extension cord 1
Radiation Survey and Monitoring Instruments 73.
Vamp area monitor 1
i j
By _
Date Reviewed By Date (Health Physics Supervisor) l EPIP-24b l
(01-82) t
I'
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POINT BEACH NUCLEAR PLANT
%J QUARTERLY EMERGENCY PLAN CHECKLIST DATE Re ference: EPIP 7.4.1 - Routine Check, Maintenance, Calibration and Inventory of Schedule of Health Physics Emergency Plan Equipment EPIP 7.4.2 - Emergency Plan Equipment Routine Checks, Maintenance and Calibration Instructions SITE BOUNDARY CONTROL CENTER RESPIRATORY EQUIPMENT Item No.
Type Serial No.
Inspection 1.
Full-face 2.
Full-face
[
3.
Half-face
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4.
Half-face COMMUNICATIONS Portable Radio KRQ-717 Functional check with control room WARNING LIGHTS, TRAFFIC Traffic Warning Lights All traffic warning lights functioning l
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R.j EPIP-25c Page 1 of 4 (01-82)
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DRY CELL BATTERY REPLACEMENT
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NOTE:
If Alkaline batteries are used, battery changeout is required annually rather than quarterly.
Item Battery No.
Type of Equipment Tyge Quantity Changed Date Due 1.
Traffic Warning Light 2.
Survey /Frisker Instruments 3.
Flashlights 4.
Portable Radio 5.
Dosimeter Charger CONTROL ROOM RESPIRATORY EQUIPMENT
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Item Type of Serial Functional ex No.
Equipment Number Inspection Test
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1.
Bio-Pak 2.
Bio-Pak 3.
MSA-SCBA 4.
MSA-SCBA 5.
Supplied Air Mask 6.
Supplied Air Mask 7.
Supplied Air Mask 8.
Supplied Air Mask l
9.
Supplied Air Mask 10.
Supplied Air Mask 11.
Supplied Air Mask Hose 12.
Supplied Air Mask Hose 13.
Supplied Air Mask Hose 14.
Supplied Air Mask Hose 15.
Supplied Air Mask Hose 16.
Supplied Air Mask.90se 17.
Supplied Air Valve 18.
Supplied Air Valve 19.
Supplied Air Valve 20.
Supplied Air Valve 21.
Supplied Air Valve 22.
Supplied Air Valve Ob 3
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EPIP-25c Page 2 of 4 (01-82)
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Control Room Respiratory Equipment, continued...
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Item Type of Serial No.
Equipment Number Inspection 23.
Supplied Air Hose 24.
Supplied Air Hose 25.
Supplied Air Hose 26.
Supplied Air Hose 27.
Supplied Air Hose 28.
Supplied Air Hose
'29.
Spare Mask 30.
Spare Mask 31.
Spare Mask 32.
Spare Mask TECHNICAL SUPPORT CENTER RESPIRATORY EQUIPMENT Item Type of Serial Serial No.
Equipment Number Inspection Number Inspection 1.
Clear-Vue 1.
4.
2.
5.
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3.
6.
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2.
Ultra-Vue 1.
4.
2.
5.
3.
6.
3.
Bio-Pak 1.
3.
2.
4.
GATEHOUSE COMMUNICATIONS Portable Radios KRQ717 Functional Test with (2 units)
Control Room l
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EPIP-25c Page 3 of 4 (01-82)
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RESPIRATORY EQUIPMENT Item Type of Serial Serial No.
Equipment Number Inspection Number Inspection 1.
Clear-Vue 1.
4.
2.
5.
3.
6.
2.
Ultra-Vue 1.
4.
2.
4.
3.
6.
3.
Bio-Paks 1.
3.
2.
COMMUNICATIONS Portable Radio KRQ717 Functional Test with (Located in DTA Quartars)
Control Room REMARKS:
J NOTE:
Include maintenance request numbers for all items requiring repairs.
Inventory By Date 4
Reviewed By Date J
i EPIP-25c Page 4 of 4 (01-82)
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